SOVIET ATOMIC ENERGY VOLUME 15, NO. 4

• Document Type: CREST
• Collection: General CIA Records
• Document Number (FOIA) /ESDN (CREST): CIA-RDP10-02196R000600110002-5
• Release Decision: RIFPUB
• Original Classification: K
• Document Page Count: 113
• Document Creation Date: December 23, 2016
• Document Release Date: February 25, 2013
• Sequence Number: 2
• Publication Date: October 1, 1963
• Content Type: REPORT

,
Declassified and Approved For Release 2013/02/25 : CIA-RDP10-02196R000600110002-5
Volume 1,5, No. 4
:October, 1963
$0111ET,
TOM I.
ENERGY'
ATOMHAFI 3HEP11411
(ATOMNAYA iNERGIYA)
TRANSLATED FROM RUSSIAN
CONSULTANTS BUREAU
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
??`'??
? ? ? *
ADVANCES IN TRACER METHODOLOGY
Volume 1
Edited by Dr. Seymour Rothchild,
Technical Director, New England Nuclear Corporation
Proceedings of the Fifth Annual Symposium on Advances in Tracer Methodology, held October
20, 1961, in Washington, D. C., and selected and up-dated papers from the first four Symposia
held from 1957-1960, sponsored by the New England Nuclear corporation in collaboration with
Packard Instrument Co., Inc.
The interest in tritium as a tracer isotope, which has.. developed to major, proportions in recent
years, is reflected in the first two symposia, concerned solely with tritiumi, and in succeeding sym-
posia, which contain a large number of papers on tritium. Of special interest are:
Liquid Scintillation Counting of Tritium
Gas Counting of Tritium
Tritium in Biochemical Studies
Tritium Recoil Labeling of Linseed Oil
Some Aspects Of Stereoselectivity in the Introduction of Tritium into Sterokds.
, Among the other aspects of tracer ,methOdology described, special attention has been devoted to
recent developments in the, synthesis of labeled compounds:
The Gas Exposure Technique for Tritium Labeling
Experiences with Tritiated Compounds Prepared by'Exposure to Tritium Gas
Reaction of Unsaturated Organic Compounds with Tritium Gas
Preparation of Tritium Labeled Paromomycin (Humatin)
by Biosynthesis in a Medium Containing Tritiated Water,
to tracer applications and methods:
Use of Radioisotopes in Steroid Methodology
, Metabolism of DL-Epinephrine-7-H3 D-Bitartrate
Application of Tritium in the Determination of Gibberellins
The Efficiency of Autoradiographic Stripping-Film Applied to
Tissue Sections Containing Tritiated Thymidine
Application of Whole-Body Liquid Scintillation Counters
to Pharmacological Studies,,
and to radioisotope analysis methodology:
Monitoring Gas Chromatography for H3- and C"-Labeled
Compounds by Liquid Scintillation Counting
Determination of Radioactive Sulfur in BiologicalMaterials
Scintillation Counting of C"-Labeled Paper Chromatograms
Liquid Scintillation Counting of C1402 in Aqueous Carbonate Solutions
Parr Bomb Combustion of Tissues for Carbon-14 and tritium Analyses
Determination of Tritium and Carbon-14 in Biological
Samples by Rapid Combustion Techniques
? 50 reports * fully illustrated ? indexed ? literature references ? 343 pages, $12.00
Contents on request
CP PLENUM PRESS 227W. 17th St., New York; N.Y. 10011
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
ATOMNAYA ENERGIYA
EDITORIAL BOARD
A. I. Alikhanov A. I. Leipunskii
A. A. Bochvar M. G. Meshcheryakov
N. A. Dollezhal' M. D. Millionshchikov
K. E. Erglis (Editor-in-Chief)
V. S. Fursov
1.1. Novikov
I. N. Golovin
V. B. Shevchenko
V. F. Kalinin
A. P. Vinogradov
N. A. Kolokol'tsov
N. A. Vlasov
(Assistant Editor)
(Assistant Editor)
A. K. Krasin
I. F. Kvartskhava M. V. Yakutovich
A. V. Lebedinskii A. P. Zefirov
SOVIET ATOMIC
ENERGY
A translation of ATOMNAYA iNERGIYA
A publication of the Academy of Sciences of the USSR
? 1964 CONSULTANTS BUREAU ENTERPRISES, INC.
227 West 17th Street, New York 11, N. Y.
Vol. 15, No. 4 ' October, 1963
CONTENTS
The Use of High Frequency Electromagnetic Fields to Contain and Stabilize
PA
ENG.
GE
RUSS.
a Plasma?S. M. Osovets
997
283
Calculation of the Thermodynamic Properties of Cesium Yapor up to 1500? K and a Pressure
of 22 bars?N. I. Agapova, B. L. Paskar' and L. R. Fokin
1007-
292
Enlarged Radiochemical Equipment Using the Radiation from Spent Nuclear Reactor Fuel
Elements?V. L. Karpov, A. Kh. Breger, M. E. Eroshov, V. E. Drozdov, G. N. --Lisov,?
S. G. Stoenko, D. M, Torgovitskii, B. I. Vainshtein and N. P. Syrkus
1018'
, 302
A Radiochemical Investigation of the Yields of Rare-Earth Elements from U238
Photofission?K. A. Petrzhak and R. V. Sedletskii
1025
308
The Effect of the Iron Minerals in Ores on Oxidation of Uranium in Acid?G. M. Alkhazashvili,
G. M. Nesmeyanova and L. N. Kuz'mina
1031
313
LETTERS TO THE EDITOR
Study of the Motion of Individual Charged Particles in Corrugated Magnetic
Fields?V. M. Balebanov, V. B. Glasko, A. L. Groshev, V. V. Kuznetsov, A. G. Sveshnikov
and N. N. Semashko
1036
318
The Over-All Kinetic Energy of U233 and Th232 Fragments?S. S. Kovalenko, K. A. Petrzhak
and V. M. Adamov
1039
320
Delayed Neutrons from Fission of U233 by 15-MeV Neutrons?B. P. Maksyutenko
1042
321
Determination of the Partial Alpha-Decay Period of Pu241?R. B. Ivanov, A. S. Krivokhatskii,
L. M. Krizhanskii, V. G. Nedovesov and M. I. Yakunin
1043
322
The Fast-Neutron Capture Cross Sections of Copper and Zirconium?Yu. Ya. Stavisskii
and A. V. Shapar'
1045
323
Use of Large Area Semiconducting Detectors in a-Spectrometry?V. F. Kushniruk,
t. Z. Ryndina, S. M. Solov'ev and I. I. Chuburkova
1047
324
The Attenuation of a High-Energy Neutron Flux. in Shielding?M. M. Komochkov
and B. S. Sychev
1049
325
The Effect of Reflectors Made of Various Materials on the Increase in the Number of Neutron
Captures in the Uranium Carbide Blanket of a Fast Reactor?V. I. Golubev, A. V. Zvonarev,
M. N. Nikolaev and M. Yu. Orlov
1053
327
Calculation of the Spectral and Angular Distribution of Scattered y-Quanta from a Point
Monodirectional Cs137 Source in Iron?L. R. Kimel', A. M. Panchenko
and V. P. Terent'ev
1055
328
(continued)
Annual Subscription: $95
? Single Issue: $30 Single Article: $15
All rights reserved. No article contained herein may be reproduced for any purpose what-
soever without permission of the publisher. Permission may be obtained from Consultants
Bureau Enterprises. Inc., 227 West 17th Street, New York City, United States. of America.
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
CONTENTS (continued)
The Effect of Shield Shape on the Attenuation of y-Rays from Volume
PAGE
EN6. I RUSS.
Sources?D. P. Osanov
1059
331
Measurement of the Frequency Characteristics of an IRT-1000 Reactor by the Oscillation
Method?L. V. Konstantinov, A. I. Efanov and V. V. Postnikov
1060
332
Photoneutron Method for Beryllium Determination in the Laboratory?V. N. Smirnov
and D. V. Tokareva
1063
334
Displacement of Uranium from Chloride Melts by Zinc?I. F. Nichkov, S. P. Rasponin
and A. F. Tsarenko
1066
336
A New Type of Porous Bed Model for Neutron Logging?N. K. Kukharenko, Ya. N. Basin,
Yu. P. Bal'vas and Yu. V. Tyukaev
1069
338
Secondary Dust Component of Radioactive Contamination in the Surface Layer
of the Atmosphere?B. I. Styro, Ch. A. Garbalyauskas, V. I. Luyanas, V. P. Matulyavichus,
T. N. Nedvetskaite and I. S. Tomkus
1072
339
NEWS OF SCIENCE AND TECHNOLOGY
Conference on Electrostatic Generators and Direct-Voltage Accelerators?G. M. Osetinskii.
1075
342
International Conference on Sector-Focused Cyclotrons and Meson Factories?P. Lapostol
1078
343
IAEA Symposium on Thermodynamics of Nuclear Materials?V. V. Akhachinskii
1082
346
The Use of Gamma-Ray Sources in Nondestructive Testing at the Csepel Metallurgical
Combine (Hungary)? E. Fenyvesy, K. Scserbak and K. Vara
1090
351
BIBLIOGRAPHY
New Literature
1093
354
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
THE USE OF HIGH FREQUENCY ELECTROMAGNETIC FIELDS
TO CONTAIN AND STABILIZE A PLASMA
S. M. Osovets
Translated from Atomnaya Energiya, Vol. 15, No. 4,
pp. 283-292, October, 1963
Original article submitted February 26, 1963
This paper discusses the basic proposals that have been made up to the present time by Soviet and
foreign scientists relating to the interaction of a plasma with high frequency electromagnetic fields.
These proposals deal with the problem of controlled thermonuclear reactions, and are in the di-
rection of overcoming the difficulties that arise in containment and stabilization of a plasma. The ?
paper sets forth the ideas forming the basis of these proposals, and the important equations and dia-
grams are given,which illustrate the principles on which they operate.
Introduction
Studies on the magnetic containment and thermal insulation of a hot plasma are being carried out along sev-
eral lines in connection with the problem of controlled thermonuclear synthesis. What is characteristic of each of
these lines of work is the way in which the magnetic field acting on the plasma varies with time. From this point
of view, the important directions of study may be classified in the following way:
1. Methods in which the plasma is contained by means of stationary magnetic fields. The devices based on
these methods are called traps, and the function of the magnetic field is simply to hold the plasma inside the trap.
2. Quasistationary methods, in which the magnetic fields used vary slowly with time. In this case, the rates
of change of the field arc small in comparison with the velocities determining the processes in the plasma?the vel-
ocities of the ions, the velocities of propagation of the magnetOhydrodynamic waves, and the rates at which insta-
bilities of magnetohydrodynamic type develop. What is characteristic of these methods is that induced currents are
produced which flow in the plasma, and these are used both to contain the plasma and to heat it by Joule heat.
3. One-shot pulse methods involving the use of rapidly varying magnetic fields, changing at rates comparable
with the rates of the processes occurring in the plasma, the principal ones of which have been recounted above. In
this method, the plasma is heated either by a shock wave or by adiabatic compression of the plasma.
4. Methods using high frequency magnetic and electric fields. This paper is devoted to a discussion of these
methods.
Before we begin presenting what methods of this last type consist of, we shall give a brief discussion of the
reasons which have made it necessary to look for new Methods of investigation in the containment of a hot plasma.
With the exception of one-shot pulse methods, all the other lines of work involve producing magnetie fields of a
configuration such that the plasma as a whole is in an equilibrium state, where the equilibrium is stable to magneto-
hydrodynamic perturbations. It is further necessary not to have large particle losses in any definite directions. The
stability equations are no less important than the plasma containment itself. For an equilibrium plasma formation
to be stable to perturbations of the surface or changes of shape the magnetic field intensity must increase every-
where from the center of the chamber holding the plasma to the periphery.
Building devices using quasistationary or stationary magnetic fields with a configuration approximating the
ideal trap, and at the same time satisfying the stability conditions, is fraught with considerable difficulties. The
difficulties are due to the fact that the charged particles move freely along the lines of force in the field, and if the
lines of force go beyond the trap, the particles are in no way hindered from striking the walls of the chamber. Ac-
cordingly, an effort is made to produce a magnetic field such that either the lines of magnetic force are closed in-
side the chamber, or the particles will find it difficult to get to the points where the lines of forCe leave the trap.
The simplest configuration in which the lines of force are closed inside the chamber is the toroidal system,
In which the magnetic field is directed along the large circumference of a torus. However, this system is not an
997
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Solenoidal
winding
Flnax
Fig. 1. Distribution of longitudinal mag-
netic field intensity in the "Tokamak"
systems.
Fig. 2. Configuration of the lines of force
in the magnetic field in an adiabatic trap.
ideal trap, since the field intensity drops from the inner circum-
ference to the outer circumference of the torus (Fig. 1). As a re-
sult of this there is a difference in magnetic pressures, and the plasma
goes out of equilibrium (the so-called toroidal effect). To com-
pensate for this effect in systems of "Tokamak' type, an induced
current is produced in the plasma in the same direction as the lines
of force in the magnetic field. The interaction between this cur-
rent and the image current in the metallic wall of the chamber pro-
duces a quasiequilibrium configuration for a time of the order of
the field penetration time through the metal wall. Thus, having
the induced current present makes it possible to produce conditions
approximating the conditions in an ideal trap. However, as the in-
duced current flows through the plasma, it can lead to the develop-
ment of other forms of instability.
The first form is current instability of magnetohydrodynamic
type. The current thread is unstable to perturbations that change its
shape. To suppress this type of instability, the "Tokamak" systems
use a strong longitudinal magnetic field, which, while compensating
for the magnetohydrodynamic instabilities of the lower modes with
m= 0 (lateral displacements), and m=1 (bending), can lead to in-
stabilities in the higher modes. Further, an induced current flowing
in a strong magnetic field produces a large distortion in the elec-
tron velocity distribution function. A group of strongly accelerated
electrons is formed with energies of many kiloelectron-volts. Hav-
ing a large number of electrons with energies greatly in excess of the
thermal value produces kinetic instabilities, which in turn increase
the transfer coefficients. Using rotational transformation of the mag-
netic field lines as in systems of stellarator type would seem to make
it possible to avoid toroidal drift, and in this way get closer to the
conditions for an ideal trap, where the magnetic field lines close
inside the chamber. However, the experiments made so far do not
provide the basis for drawing any definite conclusions, since they
have only been made with an induced current present. Under these
conditions, no essential difference can be seen between the stellarator
and the "Tokamak".
In traps where the magnetic field lines leave the chamber,
Fig. 3. Configuration of the lines of force there are "holes" through which the particles can escape from the effec-
in the magnetic field of a trap with sharp tive volume. The conditions under which the particles escape are
point geometry. determined by the configuration of the magnetic field. In traps of
adiabatic type (the shape of the magnetic force lines is shown in
Fig. 2) it seems to be possible, under certain conditions, to reduce
the losses from particles flowing out along the magnetic field lines to allowable values. However, the shape of the
magnetic field is here such that the field intensity is everywhere dropping from the axis of the trap toward the per-
iphery. It is well known that a plasma in a field of this sort develops instability of convective type, as a result of
which the plasma moves comparatively rapidly across the magnetic field to the walls of the chamber. To produce
conditions in a trap such that the plasma remains stable to perturbations of this type, the field intensity must every-
where increase from the center toward the periphery. To this end, traps have been proposed with a sharp point mag-
netic field geometry, having lines of force of the shape shown in Fig. 3. The field intensity at the center of such
traps is equal to zero, and increases toward the walls. However, here, instead of the holes characteristic of an adia-
batic trap, there is a circular "gap" through which it is easy for the particles to get out of the vessel. Accordingly,
although a trap of this sort gives better conditions for stability than the adiabatic trap, it is still less "ideal" in the -
sense of particle loss through the gap. Thus, in all the types of traps best known at the present time, there are con-
flicts between the plasma containment conditions and the stability conditions. The need to produce magnetic field
998
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
configurations such as to satisfy the stability conditions with res-
1-1 1-\ P.\
pect to even the most dangerous types of perturbations leads to a
worsening of the conditions under which the particles are con-
tained in a given volume. However, the effort to approximate
the conditions in an ideal trap may lead to worsening of the sta-
bility conditions. This forces us to look for new solutions, where
the conflicting requirements do not exist. One of the ways offer-
ing new possibilities involves using high frequency magnetic fields
to contain and stabilize the plasma. Up to the present time, sev-
eral proposals have been made for using high frequency fields
both to construct traps and to stabilize the instabilities. The the-
oretical assumptions on which these proposals are based allow
some systematization to be made of the directions being followed
by existing studies involving the use of high frequency fields. As
far as experiments are concerned, since the first proposals for us-
ing high frequency fields were only made in the Soviet Union in
1957, it is natural that less has been done along this than along
other familiar lines, the more so since building high powered
high frequency equipment involves great engineering difficulties
(some of the existing experimental results are given below).
The purpose of the present paper is to systematize the funda-
mental work that has been done on the interaction of a plasma
with high frequency fields. The work of foreign scientists in this
field is not sufficiently well known: several papers of a the-
oretical nature, and only one experimental paper [13] have been
published.
High frequency fields may be used in the problem of con-
trolled thermonuclear synthesis for several different purposes (for
example, they may be used for heating the plasma). Although
this line of work was started some time ago, it is not discussed
in the present paper. Here, we are interested in proposals for us-
ing high frequency fields in two other ways. First, it was pointed
out in some of the proposals that the method can be used to pro-
duce field configurations that are nearly the same as the field
configuration in an ideal trap. In this case, we are dealing with
methods of containing the plasma both by high frequency fields
alone, and in combinatioh with stationary or quasistationary
fields. Second, in systems in which the plasma is contained by
stationary or quasistationary fields, high frequency fields are used
to stabilize the most dangerous types of instability. Here, the
functions of the high frequency fields are limited solely to maintaining stability in the system. The plasma is contained by
fields that do not change with time, or else change quite slowly. The methods in which stability is achieved by high
frequency fields acting on an equilibrium plasma we shall give the name of dynamic stabilization methods.
This classification is what determines the direction of study. As far as the methods of causing the high fre-
quency fields to act on the plasma are concerned, there are also two ways that need to be distinguished:
1) acting on the plasma with fields of comparatively low frequency, where the characteristic dimensions of the
system are much less than the wavelength in vacuum. In this case, the plasma is acted upon solely by the magnetic
field, since the electric field is small in comparison with the magnetic field (in the ratio E?,,:41(//X)H,);
2) the plasma is placed in a system of endovibrator type, and is acted upon by an electromagnetic wave with
H,..,. The first method may be given the name lumped constant method (inductance L and capacity C), while
the second may be called the distributed constant method.
Fig. 4. Arrangement of windings, and instan-
taneous magnetic field intensity distribution
in a traveling wave system.
Walls of chamber
Fig. 5. Magnetic field distribution over the
cross section of the discharge chamber in a
system with sharp point geometry (1), and
in a traveling wave system (2).
Fig. 6. Magnetic field intensity distribution
in a toroidal traveling wave system.
999
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Plasma Containment and Stabilization By Means of High Frequency Fields
Lumped constant systems. It is clear that when using lumped constant systems, the oscillational frequency of
the field must be kept as low as possible, since increasing the frequency (for a fixed total field energy) raises the ac-
tive power taken from the generator supplying the oscillations. The lower limit of the frequency will be approxi-
mately the thermal velocity of the ions divided by the characteristic dimension of the system. This is due to the
fact that during one period of change in the high frequency field, the perturbation of the plasma surface must not
exceed the allowable limits. In other words, as the field pressure on the plasma surface varies from zero.to its max-
imum value, the perturbation of the surface must be small in comparison with the distance from the surface to the
walls of the chamber: This condition holds both for systems in which the action on the plasma comes exclusively
from the:high frequency field, and for combined systems. In the latter case, the rate of perturbation of the surface
may be determined by the velocity of propagation of Alfven waves for the stationary wave VA =H0/471?rp, while in
the first case it is determined by the thermal velocity of the ions. For the conditions under which studies are being
made or are being proposed, the appropriate frequencies lie in the 1-10 Mc range, i.e., in the 300-30 m wavelength
range. These values are many times greater than the dimensions of the equipment used, and are thus simply lumped
constant systems. They are characterized by the use of vacuum tube oscillation generators and ceramic circuit con-
densers. The inductance is the winding on the gas discharge chamber. Let us consider how these systems may be
used to contain a plasma. As a typical example take the traveling wave system [1].
1
Fig. 7. Trap with high frequency mirrors: 1) mag-
netic winding; 2) endovibrator; 3) plasma; 4) lines
of force of electric field.
Fig. 8. Bending of a
plasma spiral carrying
current ,for n=3.
It was pointed out above that in traps with sharp point geometry in the magnetic field, the conditions are satis-
fied for stability to perturbations of convective type, which are one variety of magnetohydrodynamic instability. The
windings producing the magnetic field are connected bucking, i.e., the currents in the windings are of opposite sign.
As a result of this, the magnetic field intensity is zero at the center of the chamber, and is everywhere rising toward
the periphery. However, there are gaps in these traps through which particles can escape. Assume that the magnetic
field is produced by a winding in which the alternating currents in neighboring turns are displaced in phase by some
angle (Fig. 4).
lithe phase shift angle (p between the current in neighboring turns lies between zero and 7r, the amplitude value
of the magnetic field intensity will change in the direction of the z axis (see Fig. 4), so that the waves seem to travel.
If the system is wound into a torus, the wave will rotate in the same way as in an induction motor. In this case, the
gap, i.e., the place where the magnetic field intensity is small, will move along with the wave. If the velocity of
the wave is quite large, the particle is not able to get out of the effective volume. The velocity of the wave is v.w/-x,
where It is the wave number 2rA, and X is the wavelength in space. The condition for the smallness of the plasma
surface perturbation because of the presence of the moving gap reduces to w < ru// , where u is the velocity of sound
in the plasma, and isequal in practice to the thermal velocity of the ions.
For a phase shift of r, i.e., in a system with sharp point geometry, the field intensity varies over the cross
section of the chamber (without plasma) as shown by curve 1 of Fig. 5. If the current flows in the same direction in
all the turns, the field will be practically uniform. It is clear that if the phase shift angle between neighboring wind-
ings is 0< < r, some intermediate case will occur (for example, curve 2 of Fig. 5). Here the field does not drop to
zero, but it is a minimum in the center, and increases toward the periphery everywhere. Accordingly, the plasma is
in a "well," the depth of which is determined by the phase shift angle q), the values of R (the radius of the turn), and
1000
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Fig. 9. Magnetic field intensity
distribution in a system with
dynamic stabilization of a plasma
spiral. 1) Field intensity H; 2)
plasma spiral.
/ (see Fig. 4). The increase in field on going away from the plasma bound-
ary favors stability: if the plasma surface is deformed, the resulting addi-
tional field pressure tries to bring the plasma boundary back to its previous
state [2]. If the cylinder is wound into a torus (see Fig. 4), the toroidal effect
causes the magnetic field distribution to become asymmetric Over the cross
section: the field intensity about the inner surface of the chamber will be
greater than about the outer surface, but the "well" is still there, and the
equilibrium conditions are maintained (Pig. 6). Other Modifications of the
traveling wave system are possible; for example, the field may rotate along
the small radius of the torus. Other types of discharge using rotating fields
are not impossible [3, 4].
The system just described has been realized in experimental setups
on which a series of studies have been made. Some of the results of these
studies are given below. It is important to nbte that using high frequency
fields opens up new possibilities in the direction of changing the field configuration with time so as to get rid of
the defects inherent in stationary fields. If the changes in field configuration are rapid enough, a state of affairs
may be reached where, on the average, conditions are satisfied which approximate the conditions for an ideal trap,
at the same time satisfying the requirements needed to maintain stability. It is not impossible however that these
requirements are insufficient.
Using rotating magnetic fields does not of course exhaust all the possibilities for containing a hot plasma with
high frequency fields in lumped constant systems. An attempt may be made to combine rotating fields with station-
ary or quasistationary fields. However, this case does not show any essential advantages, since having stationary -
fields present, together with the associated spatial irregularities and the possibilities for particle drift, can reduce to
nothing the positive features inherent in high frequency fields. In any case, we do not at the present time know of
any well-founded proposals that are substantially different from those described above.
Distributed constant systems. In plasma containment in distributed Constant systems, we have EH, and
the effect on the plasma is caused by the pressure of both the magnetic and the electric field. Accordingly, there
is no instant of time at which the field pressure on the plasma is near zero. It has been shown in [5] that a plasma
may be contained by means of a standing wave. An attempt may be made to compensate for the toroidal effect by
using the pressure of a wave of this type.
The following possibility is discussed in [6]. Along the outside of the periphery of the torus (see Fig. 1) is
located a system of endovibrators, the fields from which produce electromagnetic wave pressure in a direction op-
posite to the difference in magnetic pressures arising from the toroidal effect. In this case it is possible to get a
resultant field configuration which satisfies the conditions for equilibrium of the plasma. The same paper gives a
method for containing the plasma by means of endovibrators located at the ends of a trap with a constant main field
(Fig. 7). It would seem possible in this system to make a considerable increase in the length of time the particles
exist in the trap. This proposal has been realized in an experimental setup on which studies are being made [7, 8].
The question is left unresolved of particle drift at the points where the lines in the constant magnetic field inter-
sect with the lines in the wave field.
In addition to these proposals, the paper [4] was given at the Second International Conference on the PeaCe-
ful Uses of Atomic Energy. This paper describes a system consisting of a spherical endovibtator, which produces
electromagnetic fields rotating about all three axes. The extent to which this proposal has been realized is not
known.
This essentially exhausts the basic proposals made up to the present time on plasma containment by high fre-
quency fields.
Dynamic plasma stabilization Methods. At the present time, proposals have been made for using dynamic sta-
bilizing methods: first, for stabilizing the magnetohydrodynamic current instabilities in a qUasistationary plaSma
spiral, and, second, to stabilize the instabilities of convective type in adiabatic traps.
The system for dynamic stabilization of a plasma spiral carrying a current [9, 10] may be represented in the
following way. It is well known that a plasma spiral with a current induced in it from an external Magnetic field
can be in equilibrium with the field producing it if certain definite conditions are satisfied which are superimposed
on the form of the field, thus:
1001
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Fig. 10. Schematic diagram of the Blevin and
Thoneman system [13].
'orb =-4-(1
where Horb is the magnetic field intensity at the place where
the spiral is located on the equilibrium orbit, H is the mean
8R
field intensity inside the spiral, and 1 = 2 (In ?r -2) is the in-
ductance per centimeter length of the spiral.
If the derivative of the field along the radius in the re-
gion of the equilibrium orbit has a quite small negative deriva-
tive, the spiral will be stable in both the vertical and the hori-
zontal plane for the condition that circular form is maintained.
But it is also known that a spiral of this sort carrying current is
unstable to deformations tending to distort the circular form.
The most dangerous deformation in this case is bending. Figure
8 shows the typical picture of deformation of a current spiral.
Deformations of this type may be compensated for by a magnetic field in a direction perpendicular to the
plane of the spiral.
The degree of compensation is determined by the magnitude of the derivative of the field intensity along the
radius a H/a R in the vicinity of the equilibrium orbit. We shall call the quantity awaR the steepness of change
of the field. It has been shown that the smaller the wavelength of the bending, the greater will be the steepness
of the field required to compensate for the deformation. Compensating for deformations in the plane of the spiral
requires the field intensity to increase with radius, i.e., awaR must be positive (Fig. 9, solid line). However, in
this case the spiral becomes unstable to bending in the direction perpendicular to the plane of the spiral. To com-
pensate for this deformation, the field intensity must drop off with radius, i.e., min (see Fig. 9, dotted line) must
be less than zero. Obviously, these conditions are mutually contradictory. They may be satisfied if the form of the
field varies with time in such a way as to compensate for the instability in the plane of the spiral in one half-period,
and for the instability in the plane perpendicular to it in the next half-period. The equation describing the behavior
of such a system is similar to the equation for the oscillations of an overturned pendulum on a vibrating suspension,
the equations for the stability of which are well known (see for example [11]). These conditions, as applied to the
problem under discussion, reduce to the inequality
ail 21 2in =HI) ;120 n2ln --jtXr0
aR > cR2n
Aro
or, if we assume that the maximum value of the variable component of the field in the region of instability of the
orbit varies linearly with the radius, the inequality is of the form
2
- > aro ( .?1? ) 1n-
For the frequency of the alternating field it is necessary to have
47tu V, X
> in?nro .
Here H- is the maximum intensity of the high frequency component of the magnetic field, I is the current in the
plasma spiral, R is the large radius of the torus, a is the small radius of the torus, X is the wavelength of the per-
turbation, n is the number of lengths of the perturbation that fit on the perimeter of the spiral (for example, for the
deformation in Fig. 8, n.3), ro is the radius of the cross section of the plasma spiral, and to is the angular frequency
of the high frequency component of the field.
It may be seen from the last inequality that this frequency is, in order of magnitude, equal to the thermal ve-
locity uof the ions divided by the characteristic dimension of the system. Thus, we get the same range of frequencies
as that required to contain the plasma with a traveling wave field.
?
At the present time, experimental studies are being made on this method, the results of which for the most
part support the initial assumptions. Details of these experiments will be published later on.
1002
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
We shall now give a short discussion of the proposals relating to compensating for convective instability in
adiabatic traps in toroidal systems. These proposals have been formulated in [7]. In essence, they reduce to com-
pensating for the convective instability which leads to the formation of plasma "tongues" by electron drift currents
in the plasma. These currents are produced on the plasma surface by the action of high frequency fields. It has
been shown that the pressure of the high frequency electromagnetic fields on the plasma surface leads to drift of the
electrons in the surface layer of the plasma in a direction opposite to the direction of the drift resulting from irregu-
larity in the stationary magnetic field. The drift currents from the high frequency field have a component constant
in time, since they occur as a result of quadratic effects. These currents are proportional to vector products of the
type [H_ rot HA and[E?_, rot E?], as well as to the product E div E. If the high frequency fields are of sufficiently
large amplitude, they can compensate for the deformation of the surface occurring as a result of instabilities of con-
vective type. The compensation conditions reduce to the inequality
112
A (tR ( Tim a x 1) ,
81tpi 4 L min
where A is a coefficient of the order of unity, R is the radius of the plasma, L is the distance between the mirrors,
po is the plasma pressure, and Hmax/Hmin is the mirror ratio.
A proposal for compensating for instabilities of the plasma surface in adiabatic traps has also been described
in [12], in which the suggestion is made of using comparatively low frequency fields with a frequency of the order
of several megacycles. In this case, the only thing that is important is the effect of the magnetic field, in com-
parison with which the electric field intensity is small. The paper only gives theoretical studies made on quite
reasonable assumptions. It is assumed that both high frequency and stationary fields are absent inside the plasma.
Apparently, these assumptions were made for convenience of theoretical treatment, but there is some doubt as to
whether or not they hold.
Definite interest attaches to the proposal made in [13], on the basis of which experiments are being made at
the present time. This proposal may be realized both in adiabatic traps and in toroidal systems. The content of the
proposal is as follows. A plasma in a longitudinal stationary magnetic field is acted upon by an additional high fre-
quency rotating magnetic field, which is produced by currents from the attenuating discharge of a condenser battery,
flowing in a system of rods running in the direction of the main field (Fig. 10). The high frequency rotating field
produces drift currents in the plasma in the direction of rotation of the field, i.e., in the 99 direction. These currents
have a component constant in time, since they arise as a result of a quadratic effect, and are proportional to [fi??
rot H?]. An additional stationary field Hz is produced by the drift currents flowing inside the plasma. If the direc-
tion of rotation of the high frequency field is taken such that the field from the drift current combines with the main
field inside the plasma, the plasma becomes paramagnetic. Paramagnetism of the plasma is known to exert a bene-
ficial effect on the stability. Actually, in the experiments that have been made a stable plasma formation has been
observed, separated from the walls of the vessel, as ascertainedby superhigh-speed?hotography, as well as by means
of probes and microwave measurements. However, the experiments have so far been made on a straight tube with a
uniform field, so that there was nothing to prevent free outflow of particles along the field lines to the ends of the
tube. The question of whether or not stability is maintained in adiabatic traps and toroidal systems is still open.
Discussion of Experimental Results and Conclusions
A short presentation has been given above of the basic proposals made up to the present time on the use of
high frequency electromagnetic fields to contain and stabilize a plasma. Experimental studies have been started on
the basis of some of these proposals. The results of the studies made were reported at the International Conference
on Plasma Physics and Controlled Thermonuclear Synthesis held in Salzburg in September 1961, and were published
in part in [14-16].
The experimental results obtained still do not give any basis for drawing definite conclusions as to the under-
lying possibilities of using the methods given above. Only the first steps have been taken along these lines. Never-
theless, the results are of great interest since new physical phenomena have been discovered which form no part of
our original ideas.
Mention was made above of the drift currents occurring as a result of quadratic effects. It hasbeen discovered in
experimental studies on the traveling wave system that the presence of such currents has a substantial effect on the
characteristics of the system. The drift current, to a considerable degree, determines such parameters as the effec-
tive conductivity of the plasma, and the way in which the high frequency field penetrates the plasma.
1003
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
For the simplest case, where the high frequency fields are relatively small while the gas densities are large,
the constant component of the drift current is given by the equation
eoroxn2
'dr =
8mv
where 1'0 is the plasma radius, x is the wave number for the wavelength in space, 6 is the thickness of the skin layer
assuming normal skin effect, i.e., for the case where the thickness of the skin layer is greater than the electron mean
free path, v is the effective frequency of collisions between an electron and the neutral and charged particles, and
H is the maximum value of the magnetic field component in the direction of motion of the wave. The value of the
field is taken at the plasma boundary. The measured values of the drift current for small fields and large initial pres-
sures are quite close to the calculated values. The measurements made on the thickness of the skin layer with mag-
netic probes are also in good agreement with the calculated values. However, the state of affairs changes radically
as the magnetic field intensity is increased and the initial gas pressure is lowered. It turns out that having a drift
current present leads to a condition where the conductivity ceases to increase with increase in the degree of ioniza-
tion of the plasma and in the electron temperature. The expression for this anomalous effective conductivity oeff
may be written in the form
1:1 n
creff
172-racy/
1+ coxf/2
where on is the normal conductivity.
e6x
Hence it follows that for _ > 1 , the conductivity lowering effect becomes substantial. Physically,
y2 mcv
this means that when the radial component of the magnetic field flr=velz becomes such that the Larmor frequency
in the field exceeds the collision frequency, "magnetization" of the electrons occurs. The expression for Hr is ob-
tained from the equation div H.0, for the condition that the z dependence is of the form cos (cot+ xz), while the r
dependence is of the form er/6.
Actually, the reduction in conductivity as a result of magnetization of the electrons decreases the Q of the cir-
cuit, and leads to excessive consumption of plasma energy. The magnetization also affects the magnitude of the drift
current, the expression for which takes the form
I nrooenev f eoxil
dr ?
1
Mxii )2 17 MCV
2-WV
where n is the electron density, and vf is the phase velocity of the wave in the direction of the rotation of the field,
Vf = UV-X. It may be seen from the above equation that the directed velocity of the electrons in the drift current can-
not exceed the phase velocity of the wave, which, in the system studied, was about 5. 107 cm/sec. Accordingly, hav-
ing a drift current flowing can scarcely start up electron oscillations in the plasma, since the above velocity is much
less than the thermal velocity of the electrons.
However, as far as the electrodynamic current instability is concerned, it may be shown that the magnetic field
of the drift current is always considerably less than the intensity of the main high frequency field, so that it is again
in this case scarcely possible for instability to occur. Nevertheless, the presence of the drift current has such a large
effect on all the processes that it is difficult to say what effect it will have if the high frequency magnetic field in-
tensities are subsequently increased to any considerable extent. The example given provides a clear illustration of
the importance of nonlinear effects in systems using high frequency magnetic fields. As was shown above, such non-
linear effects occur, and are used in other systems: in compensating for the instabilities in adiabatic traps, in systems
using a rotating magnetic field with a stationary longitudinal field present, etc. Thus, new theoretical problems arise,
along with the need to look for new theoretical methods of investigating nonlinear effects.
However, as far as experimental methods for the subsequent development of high frequency systems are con-
cerned, difficulties arise having both engineering and fundamental aspects. The existing engineering methods make
it possible to carry out physical investigations that clear up a number of fundamental questions in the process of look-
ing for the most promising lines of work. This of course requires complex engineering developments, which, however,
1004
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
are completely attainable with the present day level of development of engineering. What are needed are more
highly developed and more powerful generators (approximately up to 1000 MW for a pulse length of ?1 msec), cir-
cuit condensers with an energy capacity per unit volume a factor of 50-100 greater than those in existence, develop-
ment of methods for increasing the dielectric strength of circuits, development of ceramic chambers meeting the
operating requirements in high vacuum, etc. All these problems have to do with engineering. However, the choice
of suitable materials, and the development of the technology of preparing samples requires serious physics studies.
The fundamental side is more important. Even in case the physics studies show that the action of high fre-
quency fields on a plasma lead to the desired results in containment and thermalization of a hot plasma, it turns out
that satisfying the energy balance conditions in a future thermonuclear reactor is considerably more difficult than is
the case with stationary or quasistationary fields.
It was shown in [1] that for the existing conducting materials at normal temperature, the ohmic losses from a
greatly enhanced skin effect are such that the losses themselves will be mainly what determines the energy balance.
The Q values obtainable at the present time in radio systems using either lumped or distributed constants are funda-
mentally not good enough to make an energetically favorable nuclear synthesis reaction possible. Accordingly, the
lines of work involving high frequency methods of containing and stabilizing the plasma can only be said to be prom-
ising if it is possible to make a marked reduction in the losses in the circuits and endovibrators. Fundamental pos-
sibilities are opened up by the use of superconductors in which a superconducting state is maintained at high mag-
netic field intensities. Such superconductors have been obtained quite recently, and success in their further develop-
ment may exert a decisive influence in the problem under discussion.
Of course, at the present time, the greatest amount of attention must be concentrated principally on making
physics studies and looking for physical ways of making a fundamental solution of the problem. As for the engineer-
ing development possibilities, it would be premature at present to set up any projects in this direction based on exist-
ing engineering facilities. There is every reason to assume that by the time physical meanshave been found of solving
the problem, new engineering methods will have appeared, since the rapid development of engineering in general,
and of radio-engineering in particular, is such that it is at present difficult to imagine what the possibilities will be
in the comparatively near future.
It should be noted in conclusion that the lines of work involving the use of high frequency electromagnetiqfields
in the problem of controlled thermonuclear synthesis have only begun to develop. Further studies are needed athigher
field intensities. More powerful generating equipment must be built, along with circuits with higher breakdown
strength, more heat resistance discharge chambers, etc. It may be assumed that even in the next few years our knowl-
edge in the field of study of the interaction between a plasma and high frequency electromagnetic fields will be-
come substantially more complete, and that this very interesting line of investigation will occupy a permanent place
among the other lines in which a search is being made for means of controlling thermonuclear synthesis.
LITERATURE CITED
1. S. M. Osovets, In Collection: Plasma Physics and the Problem of Controlled Thermonuclear Reactions, Vol.
4 [in Russian], Moscow, Academy of Sciences Press, USSR, p. 3 (1958).
2. T. F. Volkov, ibid., p. 109.
3. B. A. Trubnikov, ibid., p. 309.
4. J. Butler, A. Hatch, and A. Ulbrich, Paper No. 350, presented by the USA at the Second International Con-
ference on the Peaceful Uses of Atomic Energy, Geneva (1958).
5. R. Z. Sagdeev, In collection: Plasma Physics and the Problem of Controlled Thermonuclear Reactions, Vol.
3 Fin Russian], Moscow, Academy of Sciences Press, USSR, p. 346 (1958).
6. A. A. Vedenov, et al., In the book: Transactions of the Second International Conference on the Peaceful Uses
of Atomic Energy. Papers by Soviet scientists,Vol. 1[in Russian], Moscow, Atomizdat, p. 143 (1958).
7. T. F. Volkov, V. M. Glagolev, and B. B. Kadomtsev, Paper No. 228 at the International Conference on Plasma
Physics and Controlled Thermonuclear Synthesis [in Russian], Salzburg, MAGATE (1961).
8. Yu. I. Arsen'ev, et al., ibid. paper No. 218.
9. S. M. Osovets, Zh. eksperim. i teor. fiz., 39, 311 (1960).
10. M. L. Levin and M. S. Rabinovich, See [7], paper No. 251.
11. L. D. Landau and E. M. Lifshits, Theoretical Physics, Mechanics, Vol. 1 [in Russian], Moscow, Fizmatgiz, p.121
(1958).
1005
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
12. E. Weibel, The Physics of Fluids, 3, 945 (1960).
13. H. Blevin and P. Thoneman, See [7], paper No. 65.
14. V. G. Andreev, ibid. paper No. 250.
15. R. A. Demirkhanov, Zh. 4ksperim. i teor. fiz., 42, 338 (1962).
16. R. A. Demirkhanov, et al., Zh. fiz., 32, 180 (1962).
All abbreviations of periodicals in the above bibliography are letter-by-letter transliter-
ations of the abbreviations as given in the original Russian journal. Some or all of this peri-
odical literature may well be available in English translation. A complete list of the cover-to-
cover English translations appears at the back of this issue.
1006
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
CALCULATION OF THE THERMODYNAMIC PROPERTIES
OF CESIUM VAPOR UP TO 1500?I< AND A PRESSURE OF 22 BARS
N. I. Agapova, B. L. Paskar', and L. R. Fokin
Translated from Atomnaya gnergiya, Vol. 15, No. 4,
pp. 292-302, October, 1963
Original article submitted December 27, 1962
This paper gives an analysis of the original data, together with tables of the thetmodynarnic properties of
cesium on the saturation curve and in the superheated and wet vapor region, and an estimate is made of the accuracy
of the results. An attempt is made to calculate the thermodynamic properties of cesium vapor up to 1500?K and 22
bars.
The method of calculation is the same as that Used previously in determining the thermodynamic properties
of potassium [1]. Here, the cesium vapor is regarded as an equilibrium dissociating mixture of mon- and diatomic
ideal gases (Cs2,--_2Csi),* while the wet vapor (in calculating the velocity of Sound) is regarded as a medium that is
uniform from the gas dynamic point of view. In calculating the properties of the saturated Vapor, the specific volume
and the compressibility of the liquid have been neglected.
Initial Data
The caloric functions of the dondensed phase needed fOr the calCulatiOnt?the heat Capacity, the entropy, and
the enthalpy? were taken from [2, 3],in whith the melting point is taken to be 301.81K (41 while the heat of fusion
is taken as 61?301.8= 2137.2 J/g-atom (here, and in the rest of the paper, the Condensed phase is atsumed to be mon-
atomic, while the molecular mass is fic=iii r: 132.91).
The heat capacity epc has been studied experimentally at temperatures from 20 tO 310?K in [5], where the Char-
acteristic temperature was found to be OD(Cs)= 44?K. These data have been used in [2, 3] to calculate the enthalpy
/o298.15"ioo
2.j/g atom, and the entropy SOd298.15= 84.35 ? 1.7 I/g-atom ?
In addition to this, the heat capacity of liquid cesium had been measured in 1913 (61 at temperatures from 28
to 100?C, and the equation found was
--= 33.47 ? 0.0188 J/g-atom ? deg.
It is known that beyond the melting point, epc of the liquid first decreases (as a result of destruction of the
quasicrystalline structure), and then increases, and in the critical range C4,6. There is Very little experimental
data on the heat capacity in the liquid state for cesium and other alkali metals, which makes it difficult to sample
and extrapolate the values by similitude Methods.
We consider that the calculation of the caloric functions of liquid ceSiurn Made in (21 assuming that the heat
capacity is constant (epc= 31,80 J/g-atom ? deg) from the Melting point to 1500?K, represents the present day level
of knowledge since any other extrapolation can be just as inaccurate. 'the method thai we have used for calculating
the saturation pressure [1] is based on determining the partial pressures of mon- and diatomic ideal vapor over liquid
cesium from a consideration of the appropriate phase equilibrium conditiOns. The original data used in this case were
those on the heats of sublimation of the components, and the heat capacity epd. Brute force extrapolation of the lat-
ter to the high temperature range is, in our opinion, more justifiable than straight extrapolation Of the different pieces
of experimental data on the saturation preSsure since it is clear in the first Method what liquid and vapor model is
being used to obtain the results.
The heat of sublimation ,6,1901 of Csi Vapor from the condensed phase at (PK is given in a number of papers
and varies from 79690 J/g-atom [2, 3] to 78619 J/g-atom [1]. The value of 4i is found from an analysis of the
experimental data on the saturation pressure, which, for cesium, were taken in the temperature range 3O1.5-943K[7].
? The subscripts 1, 2 and ?c^ refer to atoms, molecules, and the Condensed phase respectively. The index 0 (at the
top) designates the standard state.
1007
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 1. Saturated State of Cesium Vapor (Temperature Table)
E-7
ri
.0
Pe'
3
bo
x
...,
me
.
0 -
-
,,
v", M 3/ng
.f::
.
0
_
..%
3i
?4
.x
3i
-
Z
:17
.24
3i
?4
.
.24
3i
500
2.489.10-4
0.9930
133.38
0.586
652
45 ?
122.878
0.81153
553.77
676.65
1.9191
550
1.246.10-3
0.9872
133.77
0.596
274.5
41
134.841
0.83433
548.63
683.47.
1.8318
600
4.723.10-3
0:9792
134.31
0;607
78.65 .
39
446.803
0.85515
543.09
689.90
1.7603
650
1.450.10-2
'0.9689
135.01
0.617
27.61
36
158.766
0.87430
537.16
695.93
1.7007
700
3.771.10-2
0.9567
135.85
0.628
11.36
? 34
170.729
0.89203
530.90
701.63
1.6505
750
8.602.10-2
0.9430
136.81
0.639
5.299
31
182.692
0.90854
524.37
707.06
1.6077
800
1.761.10-4
0.9283
137.85
.0.649
2.740
29
194.654
0.92398
517.63
712.29
1.5710
850
3.304.10-'4
0.9128
138.97
0.660
1.539
28
206.617
0.93848
510.74
717.36
1.5394
900
5.767.10-1
0.8963:
140.13
0.670
0.9260
? 26
218.579
0.95216
503.82
722.40
1.5119
950
9.464.10-4.
0.8814
141.29
0.681
0.5907
24
230.542
0.96509
496.93
727.47
1.4882
1000
1.474
0.8662
142.44
--
0.3961
--
242.505
0.97737
490.08
732.59
1.4675
1050
2.195
0.8513
A43.58
--
0.2770
--
254.467
0.98904
483.29
737.76
1.4493
1100
3.147
0.8370
144.70
-- .
0.2008
--
266.430
1.00017
476.60
743.02
1.4334
1150
4.363-
0.8236
145.77
0.1504
278.393
1.01081
470.05
748.44
1.4195
1200
5.878 -
0.8110
146.78
0.1156
290.355
1.02099
463.66
754.01
1.4074
1250
7.712
0.7993
147.73
--
0.09122
302.318
1.03075
457.41.
759.73
1.3967
1300
9.897'
-0.7883'
148.65
--
0.07347
--
314.280
1:04014
451.29
765.57
1.3873
1350
12.45..
0,7780
149:51
0.06032
--
326.243
1.04917
445.29
771.56
1.3790
1400
15.36
0.7685
150.31
0.05041
? --
338.206
1.05787
439.43
777.64
1.3717
1450
18.66
0,7598
151.05
--
0.04277
--
350.169
1.06627
433.73
783.90
1:3654
1500
22.35
.0.7519
: 151.73
.0.03677
.
362.131
1.07438
428.18
790.33
1.3598
c' kl/kg ? deg '
s
? bo ?
? ?.
c"sP ,?
kJ/kg - deg
sP,degibar
th
a" P, in/sec
-o;
0
ioo .
..610
. -
!..R
'Un
,.. bO?
- ..,pa..
- ,., ?
? . 'ti'.a
.c., . .
-tIII'
.C) .
li
2 -..
51'
.9-.
.
. ?
500:.
.0;23925'
'7-0.9674
0:1821
..0.1152 17.628-
2604..10
1130.102
221.6
166.6
1..575
1.116
550
0,23925 .
-43.8652
0,1952
0;1254. -14.1.8';3
8855, ;
2752.10
229.9
196.5
1.546
1.129
600.
-0.23925.
-.7-0,7806
0.2092
-.0.1359 11.598 .
-3512
8669
-237.9
205.9
1.524
1.141
650
:0.23825
-0.7092
0.2229
.0.1457 . . 9.616
-1584..
3341
245.6
214.9
1.507
1.153
700
0.23925 ?
-4.6474-
0.2352
0.1540. 8.067
-791.0
1498
253.2
223.5
1.496
1.166
750
.0.23925'
0.2452
.0.1602 6:82.8
.-A294 .
757.9
260.7
231.8
1.491
1.178
8(X)
0.23925
.--0.5929
-0.5439-
0.2528
0.1643 - ,5832
.250.7 .
423.4
268.1
239.7
1.489
1.190
850
0.23925 .
-0,4996
0.2581
0;1666 - 5:018
155.6- .
-256.1.
275.3
247.4
1.490
1.203
900-
0.23925 -
--.0A591
-0:2612
-0:1673.4.346-
'401,7-
.165.4
282.3
254.8
1.492
1.215
950
0.23925
-70.4218
0.2622
0.1666 .3.787
' 69.32
112.9
289.2,
262.1
1.496
1.228.
1000
0.23925
-03874
0.2618
0.1649 3.316
49,13
80.83
295.9
269.2
1.500
1.241
4050
0.23925.
--0.3557
0.2602
0.1627 . 2,918
36,00
60.18
302.4.
276.2
1.504
1.254
1100
. 0.23925
--0.3264
0.2578
0.1600 2.579
27.14
46.35
308.8
283.1
1.508
1.267
1150
0.23925 .
-0.2993
0.2548
0.1571 2.288
20.97
36.78
315.0
289.9
1.512
1.280
1900
0.23925
-0.2741
0.2513
0.1540 2:038
16.56
29.93
321.0
296.6
1.516
1.293
1950
0.23925
--0.2508
0.2476
0:1509 1.821
13.33
24.93
326.8
303.3
1.519
1.307
130f1
0.23925-
:.-0.2292
? 0.2438
0:1480 '4.632
10.92
21.16
332.5
309.9
1.521
1.320
1350
0.23925
-0.2091
?0.2401
0.1451 1.467
9..086
18.29
338.1
316.5
1.522
1.334
1400
0.93925
-0.1904
0.2364
0.1425 1.323
7.069
16.06
'
443.5
323.1
1.523
1.347
1450
0.23925
-70.1730
0.2327
0.1400. 1.120
6.550
14.30
348.8
326.6
1.524
1.360
1500
0.23925
--0.1567
0:2293.
0.1376 4.083
5.652
12.88
153.9
336.1
1.524
1.373
_ .
1008
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 2. Thermodynamic Properties of Cesium (Superheated Vapor)
Ho
E
bO
b.? !
< <
8
650
706
8 00
850
006
1001)-
1050
1100
1150;
1200
1250
1300
1 350
1400
1450
1 500
700
750
80?-
850
100
950-
1000
1050
1-100
1150-
1200
1250
130-4
1350
1400
1450
15'00
700
750
800
850
900
051.8
1000
1050
1100
1150
1200.
1-259
1-300
1.9
(r)
159::
, 0.0763,2 40.221 697.56
; 0.98801 43.527 707.04 ;
I0.99287 46.750 715.70
0.99549 49.932 723.98
0.99700 53.093- 732.06
0.99791 56.242 7411.041
,0.99849 59.384 747.961
755.84i
763.701
771.561
-0.99887 62.521
0.99911 65.656
0.99933 68.789
0.90946: 71.920 779.40!
0.99056 75.051 787.2.4 1
0..99963 75,181 795.08 !
0.99969 81.341 802.91 :
0-.99974 84.440 810.71
0.03077 57.569 818.58;
0.9980 90.698 826.421
0.09983 03.827 834.261
0.97643 1 21.637 705.04
0.08580123.293 ' 714.4 9!
u.99105 124.911 723..20
0 .99403 ! 26 . 50T 731 .5.4 ;
0.99584 ! 28.092 7:39.67
0.99690 29.669 747.09
0.99776 31.243 755.65
0.90828 1 3-2.814 763.55-
0.99865 ! 34.383 771.44,
0.99892 I 35:951 779.51!- '
0..99912 ; 37.517 787.161
0-99927 ,? 3.0.083 795.01 1
0.99u39 I 40.1149 802.86
0.99948 142.215 810.70 1
43.780 815.54'
0.11961:45.345 826.39!
0.99966 46.909 834.23
0.96526 14.343 ! 793.1.1
0.97906!15.475713.31
0-.98666 16.571 1 722.44.!
0.99108 07.64 5 731.02 !
'3.99378 11,8.709 ? 739.31
0.90550 j 19.765- 7-47.4.3 !
0.99664 20 .817 1 755.40
0.90742 21.867 763.40
0.99798 22.914 1 771.33 I
0.99838 23.961 ! 779.21 1
0.99868 25.006 ' 787.09 !
I
0.99891 20.0DI 794..05
0.99908. 37.005 802_81
0.00022 28.139 810.65 !
0.99933 29-.183 ! 818.50
..99941 30.227 . 826.35
31.270 ,734
1 a4 to
I 0 (1)
I ? -1,
00 60_
X X 00 00
ii
I
...
\ i
/)=.0.01 bars bars
.726210.203-45 0.13070. 1.5402 248.9
.7402, 0_17930 ft.11156 1.5977 263.7 0.08217 7_06.03
):2.:
.7136 - 0.19014 0.11988
.5723 261.2
.7522 0-.16510:0.10299 1.6293 276.0 ?. 0.951.119 31.112 715.09
.7261 ! 0.17421- ? u.10740
'71_4
.7628 0.163120.09889 1.6450 286.7 ! 0.09326
723.59
.7371 0.1.6642 0.100:36 ,
.6364 2s5.7
.7727 0.t6040; 0.09679 1.6546 i.0.99554
(1:$5; 653:11
731.80
.74.70 0.10236 0.1,0526
.6489 295.s
.7818 0.15889.0.09565 1.6594 305.5 0.90687
17.47.5
739.85
.7562 0.16012-0.09655
.6559 05.1
.7903 0.15802,0.0950u 1.6621 311.2 0.90774
747.82-
?7649 11.15882 0.09557!
.6599 13.9
.7984 0.15740] 0.09461 1.6637 0.99832
41.669 75-5.74
.7730 0.15804 5.00500
.6622
.8061 0_15716 0.09437
4)03..57674)
1.6646 330.6 0.99571 763.G3
.79t7 0.15754 0.09464
.6636 30.3
.8134 0.156950.09422
1.6652
3:18 .4 57.
.7880 0.15723 0.09441
.6645 38.4
.520410.1568213.09413
1.6655
.0.99899 .771.0
98451
346 .1 0.90919 0 1770.36
.7950 1.15702. 0.00427
.6450
16.0
.827!1u.156740.974uS
.8335
1 0.1.5669
0.09405
1.6657
1 .6657
353.6 0.99931 787.20
5529 U8
36,1.9 0.99945 1-21 6 1705.05
)8017 . 0.15689 .09,4t
0.156S0 0.09413
.6653
.6654
353.5
360:8
.8396 0.15667
0.00405
1.6656
368.0 .0.99954 D4.203 8.02.80
:81.42 0.15670 '0.09411
.6654
3(56 .4)
.855 0.15669
0.09108
1.6653
? 0 -99901 ! 50.290
.8201 '0-1567(1 0.09412!
.6651
375.0
.8-512
0.15672
0.09112
1.6649
381.6 0.99966 58.370 818.56
.8258 0.15078 I 0.09416 1
.6645
361.5
.8567
0.15679,0.09420
1.664.3
388.5 0.99971 60.462 ! 826.40
.83-13 ; 0.15684 0.1)9423
.66-42
385.5:
.8620
0.15659'0.09430
1.6635
395.1 0.00974 , 62.548 183i.25
.8307 1 0.15603 1 0.09433 1
.6634
395.t
p==0.02 bars p = 0.025 bars
.6044:0.20061'1 0.12787 , 1 -5510
259.1
'0.97080 17.260 704..07 1.6792
0.21071 0.13554 , 1.5328
257.2
.71474 ' 0.17989, 0.11170 1.5904
273.0
0.08246 16.602 713.94 t .69 28
0.185.46 0.11300 1.5865
271.6:
..7157 0.46967:0.10379' 1.6276
284.8
0.98854 19.906 722.82 1.7063
0.07288 0.10018- ' 1.0193
283.9
.728510.1643110.09969 1.6435
295.2
0.99-255- 21.190 731.2s I .7t 46
0.16624 0.10110 1.6382
294.6
.7381 10.16135 0.09744. 1.6525:
304.7
0.09451 22.462 739.49 1.7230
0.16256 0.09832.! 1.6492
30.4.3
.7167:0.15062'0.09615 1.6577
313.6
0.99625 23.727 747-56
1.7397
0.16042 0-.09072 , 1.6556
313.4
.7540 0.15858,0.0953-5 1.6605-
322. t
0.90720 24.955 755.55
1.74-00
0.15912 0-.00576, 1.6594
322.0
.7620, 0.1 57921 0.09490 1 .6627
330.3
0.. 99785 26.246 763.48
1.74S6
0.05830- 0.09510
1.661.7
330.2
.7790,! 0.15750, 0.09460 1.6038
338.2
0.99832 27.542 771 .3S
1.7560 0.15777 0.09478 1
1.6632
335.2
.7770 ! 0.15722! 0?094-40
1-6646
3/5.9
0.09865 26.757 779.26
1.71530' ? - ".09453 1.6641
345_9
.7830 0.157041 0.09428
1.6650
353.4
0.99890
30.011
787.13
1.7697 0.1571-0
15-509438 1.111146
353..4
.79013 0.15692 0-.09420
1.6652
360.5
0.99909
31.264.
794.98
1.7761 6.15703
0.09428 1.6649
360.7
.7962111.1368:,. 0-.09407
1.005,2
361.9
0.09923
32.517
802.83'
1.7822' 0.15604
0.09423 1..6650
367.9
.8021 1 0.I5a3 u.09.417
1.0650
371.9
0..999,35
33.770
R,10. 65
1.7884 u. 15690
0.09 421 1.4640
1
374-.9
.5078 ! 0-.15684; 0.094.19
I. .664-7
3181.8
0.99944 35.022
818.52
1.7939'
0.15639
15.i94251 1.6645.
381.8
.8133 I 0-.1568 0; 0.09426
I .6641
388.5
0.99951 36.274 826.37
1.7994
0.05093
0.09428 1 1.6641
358..5
.81861 0.15097, 0.09435
1.6634
395.0.
0.99957 37.526 534.22
1.8047
0.15.701
0.09437 I 1.66:1:1'
395.0
p= 0,03 bars
p=0-.04 bars
.66605 0.22046, 0.04202! 1.5.171 255.5
.6007' 0.1999.215.1:090.: 1.5748 270.4
0.97237 11.567 71-2..15
.6614 0.20148
0.12791 1.5543
268.2
.6925.! 0.17604, 0.10853 t .0)14':)'
0.98233 12_401 721.60
.6737
0..8225
0-.11314 1.5970
281.5
.71320'0.10816' 0.111251'' i -6-352
-94.0
0.98816 I 13.814 730.52
.6844
0.
7194
0.10528
1.6236
293.15
.7)24 ' 0. t 0:i 77-0.0991 9 I 1.6459
- 03.9
0-99173 1-4.017 738.95
.6910'
U.
6617
0.10093
1..6397
303.2
.7212 ? 0.161 21. 0.09728 ; 1.6 535
t 3.1
0.90491 1.4.813 747.17
.7029
0.
6279
0.00841
1.6493
312.6
.7294 0.15900' 0.09614 ; 0_6580
.21.8
0.09553 15.604
755.26
.7112
0.
6073:
0.09689
1.6552
321.4
.7372 0.15868! 0.0954.2 ; 1.6008
130.1
0.99 657 ? 1'6.393
763.95
? .7190
0.
5943
0.00594
(.6589
29.8
.7445 . 0.1 5804 0.69,497 , .61125
338.1
0.1'0731
17.184
771.21
.7261
0.
5858
0.0053-3
1.6612
3.7 . 9
.751-5 ! 0.15762 0.09467 1.66311
145.8
0.99754
17.965
779-.12
..7335
0.
5802
0.03194
(.6620
45.7
.7582 i 0.15734, 0.09447 ' 1.6643
453.3
0.99824
18:750 757.01
,.7402
0-
5764
0.09467
1.6636
53.2
.7646 I 0.15715! 0.1)9435 ? 1 .6046
166.7
0.99854
19.535 704.88
.7466
0.
5738
0.09450
1.6641
1110.6
.7708 0.15-705. 0.09128 .6648
367.9
0.99577
20.318 809.75
.7528
O.
5721
0.09440
1.6614
367.8
)7.767 !i).15697 0.09426 1.0047
374.9
0.90895
21.102 81.0.61
.7587
5711
0.09435
1.6644
17.4.8
.782411,151195! 0.09427 ' 1 .6644
381.7
0.99910
21.sx5 818.46
.7644
0.
5707
0.09434
1.6642
81 7
.7980;0.1.56:810 00431 1.66.0 3ss.4
0.99922
22.1148 '826.32
.7699
0.
5707 0.09437
1.1637
3.61)
.7933i0.15704 0.09140
1.6632 :1U-5 U
0 99931
23.450 1834.17
.7753
O.
5712
0-.09444
1.6631
95 I,
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Table 2. (Continued)
,
W
E.:
00
44
-i,..i.-
be
44
-......
?:
?4
?
be
44
....?
.;
too
0
11
be
44
.,
j41.2
too
0
12
bo
?..%
.- .
m/sec
be
44
1
te
44
.,
'2
...:'
?
bo
44
......
.2
be '
0
iv
-
too
..?
kJ/kg ? deg
a, m/sec
1) == 0 . 05 bars
p = 0.06 bars
750
0.96581
9.2231
711.01
1.6461
0.21162
0.13546
1.5369
266.2
0.95939
7.6608
709.89
1.6334
0.22135
0.14266
1.5219
264.5
800
0.97805
9.8992
720.94
1.6589
0.18829
0.11760
1.5841
280.0
0.97383
8.2317
720.21
1.6464
0.19418
0.12194
1.5723
278.7
850
0.98526
0.556
730.01
1.6699
0.17566
0.10800
1.6147
291.9
0.98239
8.7841
729.52
1.6579
0.17931
0.11067
1.6064
291.0
900
0.98969
1.202
738.60
1.6798
0.16854
0.10264
1.6337
302.5
0.98767
9.3256
738.25
1.6680
0.17088
0.10433
1.6280
301.8
950
0.99253
1.841
746.61
1.6888
0.16435
0.00952
1.6453
312.1
0.99106
-9.8605
746.66
1.6771
0.16590
0.10062
1.6415
311.6
1000
0.99442
2.476
755.06
1.6971
0.16180
0.09764
1.6525
321.1
0.99332
10.391
754.86
1.6856
0.16285
0.09838
1.6499
320.7
1050
0.99572
3.109
763.11
1.7050
0.16018
0.09646
1.6570
329.6
0.99487
10.919
762.96
1.6034
0.16092
0.09697
1.6552
329.3
1100
0.99664
3.739
771.09
1.7124
0.15912
0.09570
1.6599
337.7
0.99597
11.446
770.97
1.7009
0.15966
0.09607
1.6586
337.5
1150
0.99731
4.369
779.02
1.7194
0.15841
0.06520
1.6618
345.5
0.99677
11.971
778 93
1.7080
0.15881
0.09547
1.6608
345.4
1200
0.99780
4.907
786.93
1.7262
0.15794
0.09487
1.6629
353.1
0.99736
12.495
786.86
1.7147
0.15823
0.09507
1.6622
353.0
1250
0.99818
5.625
794.82
1.7326.
0.15761
0.09465
1.6636
360.5
0.99781
13.018
794.76
1.7212
0.15784
0.09480
1.6631
360.4
1300
0.99847
6.252
802.69
1.7388
0.15739
0.09451
1.6640
367.7
0.99816
13.541
802.64
1.7274
0.15757
0.09463
1.6636
367.6
1350
0.99870
6.879
810.56
1.7447
0.15725
0.09444
1.6641
374.8
0.99843
14.064
810,51
1.7333
0.15739
0.09453
1.6638
374.7
1400
0.99888
7.506
818.42
1.7504
0.15718
0.09441
1.6639
381.6
0.99865
14.587
818.38
1.7390
0.15729
9.09448
1.6637
381.6
1450
0.99902
8.132
826.28
1.7560
0.15716
0.09443
1.6636
388.4
0.99883
15.109
826.24
1.7445
0.15725
0.09448
1.6634
388.3
1500
0.99914
8.759
834.14
1.7613
0.15720
0.09449
1.6629
394.9
0.99897
45.631
834.11
1.7499
0.15727
0.09454
1.6628
394.9
p..0.08 -bars
/I= 0 . 10 bars
750
0.94691
5.7090
707.73
1.6130
0.23965
0.15611
.4975
261.5
800
0.96556
6.1479
718.77
1.6272
0.20549
0.43023
.5521
276.3
0.95749
4.8981
717.37
1.6118
0.21624
0.13805
1.5351
274.2
850
0.97672
6.5693
728.52
1.6391
0.18642
0.11584
.5912
289.2
0.97116
5.2406
727.55
1.6241
0.19329
0.12381
1.5779
287.5
960
0.98366
6.9801
737.54
1.6494
0.17547
0.10763
.6173
300.5
0.97970
5.5729
736.85
1.6348
0.17996
0.11084
1.6075
299.3
950
0.98813
7.3845
746.14
1.6587
0.16896
0.10279
.6341
310.7
0.98523
5.8990
745.64
1.6443
0.17196
0.10492
1.6272
309.8
1000
0.99112
7.7848
754.48
1.6672
0.16495
0.09985
.6448
320.0
0.98894
6.2210
754.10
1.6530
0.16702
0.10129
1.6399
319.4
1050
0.99318
8.1825
762.66
1.6752
0.16239
0.09799
.6516
328.8
0.99149
6.5405
762.37
1.6610
0.16386
0.09900
1.6482
328.3
1100
0.99464
8.5785
770.74
1.6827
0.16072
0.09679
.6561
337.1
0.99331
6.8582
770.51
1.6686
0.16178
0.09751
1.6536
336.7
1150
0.99570
8.9732
778.74
1.6898
0.15960
0.09600
.6590
345.1
0.99464
7.1747
778.56
1.6758
0.16038
0.09652
1.6572
344.8
1200
0.69649
9.3670
786.70
1.6966
0.15883
0.09546
.6609
352.8
0.99562
7.4903
786.55
1.6826
0.15942
0.09585
1.6596
352.6
1250
0.99709
9.7602
794.63
1.7031
0.15829
0.09510
.6621
360.2
0.99636
7.8054
794.50
1.6891
0.15875
0.09539
1.6611
360.1
1300
0.99755
10.153
802.54
1.7093
0.15793
0.09486
.6629
367.5
0.99694
8.1199
802.43
1.6953
0.15828
0.09508
1.6621
367.4
1350
0.99791
10.545
810.42
1.7152
0.15768
0.09470
.6632
374.6
0.99739
8.4341
810.33
1.7012
0.15796
0.09488
1.6626
374.5
1400
0.99820
10.937
818.30
1.7210
0.15752
0.09462
.6632
381.5
0.99775
8.7481
818.22
1.7070
0.15775
0.09476
1.6628
381.4
1450
0.99844
11.329
826.18
1.7265
0.15744
0.09460
.6630
388.2
0.99805
9.0618
826.11
1.7125
1.15762
0.09471
1.6626
388.1
1500
0.99863
11.721
834.05
1.7318
0.15742
0.09463
.6624
394.8
0.99828
9.3754
833.99
1.7178
0.15757
0.09472
1.6621
394.7
p ..0. 12 bars
p=0.16 bars
800
0.94962
4.0654
716.00
.5989
0.22644
0.14544
.5206
272.4
0.93445
3.0253
713.36
1.5782
0.24538
0.15901
.4972
269.2
850
0.96568
4.3550
726.60
.6118
0.1.9692
0.12558
.5660
286.1
0.95500
3.2485
724.74
1.5920
0.21252
0.13460
.5456
283.4
900
0.97578
4.6349
736.17
.6227
0.18433
0.11397
.5985
298.2
0.96809
3.4627
734.83
1.6035
0.19277
0.11997
.5823
296.1
950
0.98236
4.9087
745.13
.6324
0.17491
0.10700
.6205
309.0
6.97668
3.6710
744.14
1.6136
0.18065
0.11105
.6085
307.4
1000
0.98677
5.1786
753.72
.6412
0.16906
0.10272
.6352
318.8
0.98247
3.8755
752.97
1.6226
0.17305
0.10550
.6263
317.6
1050
0.98982
5.4458
762.07
.6494
0.16530
0.09999
.6448
327.9
0.98650
4.0775
761.48
1.6310
0.16815
0.10195
.6384
327.0
1100
0.99199
5.7114
770.27
.6570
0.16283
0.09822
.6512
336.4
0.98936
4.2779
769.81
1.6387
0.16490
0.09963
.6465
335.7
1150
0.99357
5.9757
776.37
.6642
0.16115
0.09704
.6554
344.5
0.99146
4.4770
777.99
1.6460
0.16269
0.09807
.6520
344.0
1200
0.99475
.6.2392
786.40
.6711
0.16000 0.09624
.6582
352.3
0.99302
4.6754
786.09
1.6529
0.16117
0.09701
.6557
351.9
1250
0.99564
6.5021
794.37
.6776
0.15920 0.09569
.6601
359.9
0.99420
4.8730
794.12
1.6594
0.16010
0.09627
.6582
359.7
1300
0.90633
6.7645
802.32
.6838
0.15863 0.09531
.6613
367.2
0.99512
5.0703
802.11
1.6657
0.15933
0.09576
.6598
'366.9
1350
0.99688
7.0266
810.24
.6898
0.15824
0.09506
.6620
374.3
0.99584
5.2672
810.05
1.6717
0.15880
0.09541
.6608
374.1
1400
0.99731
7.2884
818.14
.6955
0.15797
0.09490
.6623
381.3
0.99642
5.4639
817.98
1.6774
0.15842
0.09518
.6614
381.1
1450
0.99766
7.5501
826.04
.7011
0.15781
0.09482
.6622
388.1
0.99688
5.6603
825.90
1.6830
0.15817
0.09505
.6615
387.9
1500
0.99794
7.8115
833.92
.7064
0.15773
0.09481
.6618
394.7
0.99726
5.8566
833.80
1.6884
0.15803
0.09499
.6612
394.5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 2. (Continued)
t:10
;;???
00
Z
00
0
b0
00
77
00
r
00
-X
0
^0
,-X
., -...,
bk)
0
"0
-%
. --,
E
8
850-
900
950
1000
0.044671' 2.5851
0.96058 ! 2.7596
0.0.71101 2.9285
0.97823 1 3.0938
722.94
733_51
743.16
752.22
1050
0.90320 3.2566760.91
1100
0.98670 3.4178 ,-760.35
1150
0.98936 3.57791777.62
1200
0-.99129 3.7370;785.79
1250.
0.99277 3.89561793.87
1300
0.99391 4.0538 1 801.89
13.50.
0.99481 4.2116;809.87
140-
0.99553 4.3691 1817..82
1450-
0.99610- 4.5265 ; 825.76-
1500
0.99658 4.68371833.68
850
0-.920241.1.7017 r118.68.
900
0.94254 1.82281 730.36
950
0.95756 1 1.93891 740..79
1000
0.96787! 2.0;5171 750.41-
10-5.0-
0.97512 ; 2.1622 759.49
1100 0.90-0334 2.27121768.22
1650 0.95416! 2,379-0.; 776.7-1
1200 0.0870312.48601785-04
1-25-0 0.989211 2.5925.1 793.24
1300 0-.99091 2.6985 ; 8-01.36
1350
6:90224-; 2.8041 ; 809.42
1-40.0
0.99331 , 2-.90951847.43-
1450
0.99417. 3.014-7.! 825.42
1-500
0.99488 ; 3.11981 833.38
900 0.90932
1.0750.
724.56
950 0.53210
1.1482
730.34
1000 0.94800
1-.2187
746.94
10511; 0.95953
1 .2876
750.75;
11.00 0.96785
1.3541
766.03
.115.(. 0.97401
1.4901
774.92
1200 0.97865
1.48-?)3
783.56
1250 0.98221
1.5500
792.00
1300 0.9.8498
1.6143
800.32
1.350 0.98717 1.6752
808.52
1400 0.98593 1 /7419
846.66
1450 0.09035 1.8054
824.75
1500 0.99151
1.8687
832.79
P=0?2? bars
1
1.5762- 0-.22429! 0.14296
1.5883 0.20081! 0.12565
1.5988 0_18620.0.1149-6
1.6081 13.17695 0.10820
1.6166 0.17094 0.10386
1.62-44 ./.1.6694 0.10101
1.6318 0.1-612.1 0.00908
1.6337 0.16232 0.09776
1.065-3 0.1-6090 0.09.885
1.6516 0.I (0j03 0.06621
1-.6576 0,15933: 0.09576
1.6634 0.15887-0,09560
1.6690 . 0.15854: 0.09527 .
-1.6743 0.15833[ 0.09518
p=0. 30 bars
1.5467
1.5601
1.571:4
1.5812
1.5901
1.5982
1.605.8
1.61.28
1.6196
1.62;5-9
1.6320
1.6378
-1.6434-
1 1.6488
.5289
.56S4
.5976
.6181
.6323
.6420-
.6486
.6.531
.6563
.0584
.6591
.6605
.6608
.4606
0.25052 0.16135 1.4977
0.21932 0.13864 1.5405
0.19925 0.12402 1.5746
0.18625 0.11462: 1.6001
0..17767 0.10846 1.6485
0..17189 0.10435 1.6315
0.16792 0.10156 1.6407
6.16515 0.09962 1.6432
0.16318 0.09827 1.6516
0.18175-0.0973-I 1.6548
0.16072 0-09663 1-6569
0.15997 0-09615 1.6582
0.15944 0.09583 1.6589
0.45907 0.09563 1-6522
p = 0.50 bars
.5228
.5356
.5465
.5560
.5647
.5726
.5799
.5868
.5933
.5995
.6055
.6111
.6166
0..25053
0.22226
0.24316
0_19017
0.18124
0.17501
0.17059
0.16742
0.16511
0.16340
0.16214
0.16122
0.16054
0.16007
0_13961
0.12616
0.41692
0.11001
0.10025
0_10319
0.10102
0.09945
0.09832
0.09760
0.09692
0.09652
281.1
294.2
305.9
316.4
326.1
335-0
343.5
351.5
359-2
366.7-
373.9
380.9
387.7
394.4
276.5
290-2
302.6
313.6
324.0,
333.4
342'. 2
350:5
358.4.
368_0
333.3
380?.4
387.3
394.1
0.93222
0.95143.
0-96426
0.97301
0-.97914
0.98353
0.98675
0.98915
0.99098
0.99241
0.99352
6.99442
0.99514
0.99573
0.92548
0.94457
0.95783
0.96723
0.97403.
0.97904
0-98281
0.98569
0.98793
0.98970
0.99111
0.99225
0.99319
2.0548
2.1973
2.3347
2.4685
2.6000
2.7298.
2.8585
2.9864
.1137
.2406
.3671
3.4934
3.6195
3.7454
1.355t
t .4445
1.5309
1..6152
1,6980
1.7797
1..8606
1.9409
2.0208
2.1004
9.. 1 79:7
. 2589
2.3379
p---.0.25 bars
720.76 I 1.5601 10.23794 ! 0.152-57 ' 1.5118
? 731.92 1' 1.5729 10.21033 0_13234 1.55.34 -
741.90 1.5838 0.1028710.11959 1.5854
751.31 1.5934 i 0.18108 ' 0.1114.7 1,6887
760.20 , 1.6020 ;0.1/435 0..10019 1.6252
768.75 ' 1.6130 10.10064 0.10270- 1.6366
777.16 I 1.6173 ? 0.16006 ; 0.10033 1.947,6
785.41 I 1.6245 0.16374 . 0.00870! 1.6501
793.52 ? 1.6311 ; 0.10209 ? 0.09757 1.6539'
801.02 ! 1.6375 !- 0. (609010.0.9076 1.6506
809-05 11_6435 ;0.1600410.09620 1.6583
817.63 ' 1.6493 10.15947 0.-09581 1.6593
825.60 ? 1.6549 10.15899 ' 0.00555 1.6599
833.53 ; 1-6603 10.1567010.09540 1.0599
727.38
738.52
748_65
758..41
767,14
775.81
784.29
792.62
800_84
808.9-7
817.05
825.08
831.08
p=0 40 bars
1_5394
1:5514
1.5618
1.5710
1.5794
1.5871
1.5944
1.6042
1.6076
1.6137
1.6196
1.6253
1.6307
0.23580 0-15001
0.21124 0.13228
0.19497 0.12059
0.18407 0.11280
0.17666 0.10735
1.5195
1 :5561
1_5648
1.6063-
1.6221
0.17152 0.10394 1.6334
0.16791 0.10143 1,6415
0.16532 0.09966 r 1.6473,
0.16344 0.09839- 1.0513.
0.16207 0.09748
16107 0.0-9(18.3 I :6560
0.16033 0.09638 1.6572
0.15961 0.09008 1.6577
p=0.60 bars
278.7
292,1
304.2
315.1
325.0
334.2
342.8
351.0
358.8
366.3
373.6
380.7
387 .5
394.2
287.0
299.9
311.5
322 .2
331.9
341 .0
349.5
357.6
365.3
372.8
380.0-
38.7..0
393.7
1.5031 284.2
1.5409 297.4 0.92010 0.95091 734.24 .5224 0.23241 0.14689 ..5282 295.3
1.5717 309.5 0.93865 ..0106 765,28 .5337 0.210-84 0.1313-5 .5603 307.6
1.5955 320.4 0-.95201 .0685 755.44 .5436 0.19598; 0.12081 .5859. 318-.9
1.6134 330.5 0.96178 .1250 764.96 .5525 0.18565 0.11354 _6655 329.2
1.6266 339.8 0.96905 .1804 774.05 .5606. 0.17839 . -.6202 338.8
1_6361 348.6 0.97454- .2352 782.84 .5680 0.1/321 0.10489 .6311 347.7
1.6430 356.8 0.97876 .2896 791.40- .5750 0.16947 0.10234 .6390 356_1
1.6480 304.7 0.98206 .3432 799.80 .5816 0.10676 0.10049 .6448 364.1
1.6515 372.3 0.98467 .3967 808.044 .5879 0.16471 0.05914 .6489 371.7
1.6539 379.5 0.98676 .4500 816.27 .5938 0.16321 0.09816 .6518 379.1
1.6555. 386.6, 0.98845 .5031 824.41 .5996 0.16209 0.09746 .6538 386.2
1.6563 393.4 0.98984 .5560 832.49 ..60.50 0.16126 0.09696 .6549 393.1
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 2. (Continued)
dO
...x
.;;z-
E
_
6 ;...
OD
...,
'2
..7'
.
OW
...,
Z
-
.
bo
0
-ci
6
44
-. ,
P.
to
o
7 7
6
.x
...,
?.
U
R
-.?
..
,s
d
00
,t4.
-a-:
>:
to
44
.,
???:.
.
?
to
44
....,
ui
cr,
Id/kg ? deg
CD,
kJ/kg ? deg
ii
a, misec
p .. 0 . 80 bars
p.. 1-0 bars
950
0.89744
0.70476
730.27
1.5010
0.25042
0.15876
.5079
291.6
1000
0.92058
0.75091
742.12
1.5132
0.22486
0.14073
.5414
304.3
0.90351
0.59538
739.13
1.4968
0.23729
0.14895
1.5264
301.5
1050
0.93748
0.79539
752.89
1.5237
0.20678
0.12801
.5693
316.0
0.92360
0.63175
750.45
1.5079
0.21661
0.1.3450
1.5555
313 5
1100
0.94998
0.83864
762.88
1.5330
0.19397
0.11905
.5915
326.8
0.93861
0.66700
760.88
1.5176
0.20169
0.12412
1.5794
324.6
1150
0.95936
0.88098
772.35
1.5414
0.18483
0.11270
.6086
336.7
0.94995
0.70140
770.69
1.5263
0.19090
0.11656
1.5985
334.8
1200
0.06648
0.92262
781.42
1.5491
0.17825
0.10817
-5217
346.0
0.95862
0.73515
780.02
1.5343
0.18305
0.11126
1.6132
344.4
1250
0.97198
0.96375
790.20
1.5563
0.17345
0.10489
.6314
354.7
0.96534
0.75841
789.03
1.5416
0.17727
0.10733
1.6244
353.3
1300
0.97629
1.0045
798.78
1.5630
0.15991
0.10250
.6387
362.9
0.97062
0.80129
797.78
1.5485
0.17297
0.10444
1.6329
361.7
1350
0.97971
1.0449
807.20
1.5694
0.16727.0.1
0 5
.6439
370.7
0.97483
0.83388
806.34
1.5550
0.16975
0.10230
1.6392
369.7
1400
0.68246
1.0851
815.51
1.5754
0.16529
0.09946
.6478
378.2
0.97821
0,86625
814.75
1.5611
0.16732
0.10071
1.6439
377.4
1450
0.98469
1.12a2
823.75
1.5612
0.16380
0.09851
.6504
385.4
0.98097
0.89844
823.08
1.5669
0.16548
0.09953
1.6472
384.7
1500
0.98652
1.1650
831.90
1.5868
0.16269 0.09782
.6521
392.4
0.98323
0.93046
831.32
1.5725
0.16408
0.09866
1.6495
391.8
p==1.2 bars
fl p..1.6 bars
1000
0.88736
;0.49194 736.30
1.4832
0.24834
0.15622
1.5141
299.0
1050
0.91032
0.52283 748.12
1.4948
0.22557
0.14037
1.5439
311.2
0.88539
0.38700
743.74
1.4735
0.24122
0.15053
1.5251
307.3
1100
0.92763
0.559681758.96
1.5048
0.20885
0.12879
1.5690
322.6
0.90679
0.41003
755.29
1.4842
0.22171
0.13710
1.5515
319.0
1150
0.94081
0.58176 769.08
1.5138
0.19661
0.12035
1.5893
333.1
0.92329
0.43238
765.99
1.4938
0.20705
0.12708
1 5737
329.9
1900
0.95094
0.61022 778.68
1.5220
0.18760
0.11419
1.6054
342.9
0.93612
0.45419
776.06
1.5023
0.19607
0.11960
1.5918
340.1
1250
0.95883
0.63822,787.88
1.5295
0:18093
0.10965
1.6179
352.0
0.94619
0.47557
785.65
1.5102
0.18781
0.11402
1.6062
349.6
1300
0.96505
0.66585i795.80
1.5355
1.17593
0.10630
1.5275
360.6
0.95419
0.49663
794.88
1.5174
0.18154
0.10983
1.5176
358.5
1350
1.97002
0.09321 805.48
1.5431
0.17216
0.10380
1.6348
368.8
0.96061
0.51742
803.82
1.5242
0.17676
0.10656
1.6264
366.9
1400
0.97402 0.72035,814.02
1.5493
0.16930
0.10193
1.5402
376.5
0.96580
0.53801
812.56
1.5305
0.17310
0.10427
1.6332
374.9
1450
0-97729,0.747311 822.43
1.5552
0.16711
0.10053
1.5441
383.9
0.97005
0.-55843
821.15
1.5365
1.17028
0.10246
1.5382
382.6
1500
0.97998 '0.774131830.74
1.5608
0.16545
0:09949
1.6468
391.1
0.97357
0.57672
829.61
1.5423
0.16810
0.10108
1.6418
389.9
ii=2.0 bars
p..2.5 bars
050
0.86240 739.70
1.4566 ;0.25435 I0.15895
1:5105
I 304.0
100
,0.305831
0.88729
1.4679 23286
0.14424
1.5375
316.0
0.86460
0.25661
747.88
1.4512
0.24480
0.15182
115233
312.6
150
'0.324671751.86
0.90672 0.342921763.1,8
10
1.4779 0.21636
0.13301
1.5607
327.2
0.88721
0.27153
759.64
1.4615
0.22660
0.1.3948
1.5472
324.1
900
0.92198 10.360701773.57, 1.4868 0.20376
0.12448
1.5801
337.6
0.90516
0.28603
770.50
1.4710
0.21241
0.12392
1.5675
334.8
250 0.934050.378091783.51 14.4949 0.19415
0.11801
1.5960
347.4
0.91950
0.30019
780.94
1.4794
0.20140
0.12955
1.5848
344.9
300 094369 0.39517 793.021 1.5024 0.18678
0.11309
1.6087
356.6
9.93104
0.31408
790.78
1.4871
0.19284
0.11686
1.5989
354.3.
350 0.951400.4!201805.20p1.50930.18110,
0.10935
1.6188
365.2
0.94040
0.32774
800.25
1.4943
0.18618
0.11247
1.6102
363.2
400 0.9577910.428651811.1511.5158 10.17571
0.10648
1.6267
373.4
0:94804
0.34122
809.43
1.5010
0.18098
0.10908
1.5192
371.6
450 0.445141 819.90H5220 10.17330
0.10429
1.6327
381.3
0.95435
0.35455
818.37
1.5072
0.1.7690
0.10546
1.6262
379.7
10.95298
500 ,0.96728;0.46150,828.49 1.5278 .0 17065 0.10261 1.6371
388.7
0.95959
0..36776
827.13
1.5132
0.17370
0.10444
1.6315
387.
p == 3.0 bars
p=3.5 bars
100 10.8435710.21143,744.18
1.4372
0.25490
0.15818
.5117
309.7
150 i0.8;;8'..11 10 .224081 756.42
1.4481
0.23551
0.14507
.5359
321.3
0.85170
0.190301753.39
.4365
0.24329
0.14994
1.5262
318.8
200 10.88924,0.236371767.80
1.4578
0.22011
0.13473
.5570
332.3
0.87413
0.200981765.13
.4465
0.22698
0.13901
1.5478
329.9
250 10.90561 0.24835778.49 1.4665
0.20797
0.12663
.5750
342.6
0.89234
0.211391775.15
.4555
0.21394
0.13032
1.5654
340.4
300 01.0t689 0.2600s 788.64 1.4745
0.19842
0.12030
.5901
352.2
0.90719
0.22157,786.57
.4637
0.20356
0.12346
1.5822
350.3
350 ,0.92971 .0.27161 798.36,1.4818
0.19001
0.11537
.6024
351.3
0.91937
0.23156,796.53
.4712
0.19531
0.11805
1..5953
359.6
400 '0.93859 0.28297 807.7511.4887
0.18499
0.11152
.6123
369.9
0.92942
0.24140806.12
.4782
0.18875
0.11380
1.6059
368.4
450 0.94594 0.29418
816-8811.4951
0.18031
0.10852
.5292
378.1
0.93776
0.25110'815.43
.4847
0.18353
0.11045
1.5145
376.7
500 0.95208'10.305291825-8011.5011
0.17060
0.10617
.6262
385.9
0.94474-
0.26069
824.50
.4909
0.17937
0.10782
1.6213
384.6
----
Declassified and Approved For Release 2013/02/25 : CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 2. (Continued)
cs
b0
b0 ?
?or
COD
-o
^0
b 0
p =4,0 bars
1150
0.83547
0.16505
750.54
1.4263
0.25011
0.15418
1.5170
316.6
1200
0.85976
0.17451
762.61
1.4366
0.23314
0.14282
1.5396
327.8
1250
0.87963
0.18372
773.91
1.4458
0.21938
0.13367
1.5587
338.4
1300
0.89594
0.19273
784.58
1.4542
0.20829
0.12636
1.5750
348.4
1350
0.90937
0.20156
794.76
1.4619
0.19941
0.12055
1.5887
257.9
1400
0.92051
0.21025
804.55
1.4690
0.19229
0.11594
0.6000
366.8
1450
0.92979
0.21881
814.02
1.4757
0.18659
0.11228
1.6093
375.3
1500
0.93758
0.22726
823.23
1.4819
0.18201
0.10939
1.6166
383.3
P=5.0 bars
1200
0.83303
0.13760
757.90
1.4198
0.24361
0.14928
1.5258
324.0
1250
0.85576
0.14511
769.69
1.4294
0.22885
0.13948
1.5453
334.8
1300
0.87463
0.15245
780.82
1.4382
0.21672
0.13150
1.5624
345.1
1350
0.89032
0.15964
791.40
1.4461
0.20682
0.12504
1.5770
354.8
1400
0.90343
0.16670
801.53
1.4535
0.19877
0.11983
1.5894
364.0
1450
0.91443
0.17365
811.30
1.4604
0.19223
0.11565
1.5996
372.7
1500
0.92371
0.18051
820.77
1.4668
0.18693
0.11230
1.6079
381.0
,p=7 0 bars
1250
0.81332
0.10128
762.21
1.4041
0.24341
0.14839
1.5247
328.8
1300
0.83620
0.10666
774.04
1.4134
0.23014
0.13964
1.5424
339.4
1350
0.85555
0.11193
785.25
1.4219
0.21897
0.13237
1.5580
349.4
1400
0.87194
0.11710
795.95
1.4297
0.20966
0.12635
1.5716
358.9
1450
0.88587
0.12219
806.24
1.4369
0.20192
0.12141
1.5831
368.0
1500
0.89774
0.12719
816.17
1.4436
0.19551
0.11736
1.5927
376.6
p=9 .O bars
1300
0.80244
0.08143
768.07
1.3945
0.24012
0.14572
1.5268
334.5
1350
0.82456
0.08560
779.77
1.4033
0.22837
0.13803
1.5429
344.8
1400
0.84353
0.08970
790.93
1.4115
0.21834
0.13155
1.5571
354.5
1450
0.85982
0.09372
801.62
1.4190
0.20984
0.12611
1.5694
363.8
1500
0.87384
0.09768
811.93
1.4260
9.20269
0.12159
1.5799
372.7
1,12.110 bars
1350
0.78380
0.06277
772.56
1.3818 '0.23876
0.14435
1.5248
338.9
1400
0.80568
0.06589
784.23
1.3903 10.22830
0.13753
1.5394
348.9
4450
0.82474
0.06897
795.41
1.3981 10.21921
0.13169
1.5524
358.4
1500
0.84132
0.07199
806.16
1.4054 10.21138
0.12672
1.5637
367.5
1)=.16.0 bars
1450
0.78400 0.050571788.2011.3769 10.2282610.1371711.5342 352.3
1500
0.8031210.05287] 799.3911.3845 10.2200810.1319211.5460 361.6
j)=.20.0 bars
1500
0.76970
10.2264010.1357911.5315 356.6
1'0.041511793.4711.3684
1
b0
olE
00 0.0
0) (I)
"0 ^0
b0 b0 bl)
..?. ,.? .....,
0.84608i0.15398 760.19
0.867450.16225 771.76
0.88509 0.17033 782.67
0.89969 0.17826 793.06
0.91185 0.18604 803.02
0.92201 0.l93718I2.64
0.93057 0.201281821.98
0.83373
0.85477
0.87241
0.88726
0.89981
0.91045
0.81880
0.83962
0.85738
0.87255
0.88555
0.81027
0.83033
0.84763
0.86259
0.78311
0.80360
0.82156
p=4.5 bars
.4278
.4372
.4458
.4536
.4609
.4676
.4740
0.23865 0.1462211.5324
0.22433 0.1367111.5517
0.21267 0.1290311.5685
0.20324 0.12287 1.5827
0.19563 0.11794 1.5946
0.18948 0.11401 1.6043
0.1845310.11088 1.6121
p= 6,0 bars
0.11949
0.12570
0.13177
0.13774
0.14360
0.14939
765.80
777.32
788.23
798.67
808.70
818.42
1.4158
1.4248
1.4331
1.4407
1.4477
1.4543
0.23677
0.22393
0.21329
0.20453
0.19732
0.19141
0.14432
0.13588
0.12894
0.12328
0.11868
0.11495
p =8 0 bars
0.09244
770.96
1.4034
0.23549
0.14290
0.09710
782.43
1.4121
0.22397
0.13538
0.10167
793.38
1.4200
0.21424
0.12909
0.10616
803.88
1.4274
0.20607
0.12387
0.11058
814.00
1.4343
0.19926
0.11957
p= 10.0 bars
0,07644
777.24
1.3955
0.23226
0.14039
0:08015
788.59
1.4037
0.22202
0.13375
0.08380
799.47
1.4114 0.21327
0.12814
0.08739
809.93
1.4185 0.20583
0.12344
p= 14.O bars
0.05577
780.235
1.3787
0.23338
0.14063
0.05843
791.66
1.3868
0.2241410.13466
0.06104
802.66
1.3942
0.21608
0.12952
p=18.0 bars
1.5342
1.5517
1.5669
1.5800
1.5909
1.6000
1.5342
1.5501
1.5640
1 5760
1.5861
1.5364
1.5507
0.5633
1.5741
1.5296
1.5428
1.5544
325.9
336.6
346.7
356.3
365.4
374.0
382.1
331.7
342.1
352.0
361 3
370.2
378.7
336.3
347.0
356.7
365.8
374.6
342.7
352.5
361,9
370.9
345.6
355.2
364.5
?
0.76578 10.044491784.97 11:3681 10.2317010.1392911.5265 349.6
0.7858810.046551796.34 1 1.375810.21,r910.1339911.5384 359.0
p=21,0 1
0.7544710.037421790.77 11.3610 10.2288910.1373611.5251 354.3
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 3. Thermodynamic Velocity of Sound and Adiabatic Exponent k for Wet Cesium Vapor
P',IC
x.0.95
x=0,90
x=0,85
x.0.80
,
x=0.75 1 x=0.7
x...,0.65
a,
m/sec
k
r.0.6
a,
rn/sec
k
a, k
im/sec
a,
m/sec
11
-
a
'
m/sec
----
h
a ,
m/sec
h
a,
m/sec
I
I a,
k I
1m/sec
h
?
0. 0 C 0 0 0 0. 0 C 0 0 0 0 0 0 0 G
0 0 kr 0 nr: 0 0 0 0 0 LIC. 0' kr, 0 ICC 0 kr 0 Lr
LtZOCbXU Cr 0 -7: 0 0 CV CV CkC sck ks,
191.4
200.6
209.4
217.7
225.7
233.4
240.8
248.0
255.0
261.9
268.6
275.2
281.7
288,2
294.3
360.9
307.2
313.4
3I). 6
325.7
.128
.140
_152
.164
.176
.188
.200
.212
.224
.236
.248
.260
.273
.285
.295
.310
.322
.334
.346
.357
186.2
195.2
203.6
211.7
219 5
226.9
234.1
241.0
247.8
254,3
260.8
267.2
273.4
279.6
285.6
291.7
297.6
303.4
309.2
315.0
.126
.138
.150
.162
.173
.185
.196
'.208
.219
,231
.242
.254
.265
.277
.287
.299
310
.320
.330
.340
180.9
189.5
197.7
205 6
213.0
220.2
227.1
233.8
240.3
246.-6
252.8
258.8
264.8
270.6
276.4
262.1
287.7
293.2
298.6
304.0
1. 125
1.137
1.148
160
.17t
.182
.193
.204
.214
.295
.936
.246
.257
.267
.277
.287
.996
-.305
.314
.322
175.4
183.7
101.6
11,9.2
2084.
213:-3
220.0
296.4
232.6
238.6
944.5
250.3
255,9
261J
266.9
279.3
277.5
282.6
987.9
292.6
1.124
1.135
1.146
1.157
1.168
1.178
1.189
1.199
1.209
1.219
1.229
1.238
t.247
1.256
1.255
1.273
1-281
1.288
1.295
1.301
169.7
177.7
185.4
192.6
19?.).6
206.2
219..6
218.7
274.6
230.4
930.0
241.4
240.8
932.0
257.1
262.1
266.9
271 ? 7
276? 4
280.0
1.122
1.133
1.144
1 .154
. 2,174
-.174
.184
.193
.203
.912
.220
.299
.237
.244
.952
.259
.265
?270
.275
.279
163.8
171.5
!78.9
185.8
192.5
199.8
904.9
210.7
210.3
221:8
227.1
932.2
237.9
242.1
246.9
251.5
256.0
200.4
264.6
266.7
.121
.13t
.141
.151
.160
.170
.179
.187
.194
.-204
.211
.218
.225
.231
.237
.242
:246
.250
.253
.254
157.7
165.1
172.1
178.8
185.1
191.2
196.9
202.5
207.8
212.9
217.9
222.7
227.4
231.-9
230.4
240.6
244.7
246.6
252.5
256.1
.118
.128
.138
.147
.156
.165
.173
.180
.188
.194
.201
.206
.212
.216
.220
.224
.226
.227
.228
.227
151.4
158.4
165.1
171.5
177.5
183.2
168-7
103.9
198.9
203.8
208.3
212.8
217.1
221.2
-
--
-
-
-
.116
.126
.134
.143
.151
.159
.166
.172
.178
.184
.189
.193
.196
.199
--
_
The values for the saturation pressures of cesium vapor, found from the equations of [71, are based principally
on the data of [8], and lie above the values found in [9, 10].
We assume that the values for the saturation temperatures found in [8] may have been top low, and so the
values of the saturation pressure are too high, in view of the fact that the authors of this paper measured the tem-
perature of the thermostat while the cesium vapor was in a vessel along the axis of which ran A tungsten filament
heated to 1500?K. Ilie value of the heat of sublimation taken from [2, 3] is Al101=79699 t 1255 J/ 'g-atom.
The heat of dissociation D?0 is a very important parameter, the accuracy of measurement of which to a large
extent determines the accuracy when calculating the thermodynamic properties of the dissociating gas. The value
of LA forCs2 in the normal state is found in [11] (1-4= 0.45 eV), and [12] (14= 0.445 0.04 eV) from an analysis of
spectroscopic data [13, 14] by graphical extrapolation, using the Berdzh-Shponer method. The same value of DI) is
used in [15]. Recently, in [16], from similarity of the molecular constants, based, for the alkali metals, on the value
Do (Na2)= 0.76 eV, a value was obtained ofDo(Cs2)= 0.453 eV. In spite of the good agreement between the above
values of 00(Cs2), it should be kept in mind that the initial spectroscopic data are not good enough to make a re-
liable extrapolation. Noting this as well as the general nature of the accuracy Of determining the heats of dissocia-
tion of alkali metals, the value used is DP(Cs2)= 0.45 ? 0.04 eV=43,431 ? 6695 J/rnole, from which it follows that
0
Alo2= 26,1ot-
D = 115,967 f 6695 J./mole.
The thermodynamic functions of mon- and diatomic gases in the standard state needed for the calculations
were taken from [15], where they were found for atoms up to 2500?K (including the contribution from electron levels).
and for molecules up to 1500?K (including anharmonic vibrations, rotation-vibration interaction, etc.).
In accordance with the method used, the above initial data are satisfactory for the calculations. Further, an
attempt has been made to find the values of the specific volumes v' and the surface tension a for the liquid up to
800-900?K.
.The density of liquid cesium has been studied experimentally up to 396?K [17, 18]. The extrapolation of these
values to the boiling point was based on the following assumptions. It is known, first, that the densities of the liquid
alkali metals sodium [19], potassium [20], and rubidium [21] are satisfactorily described by equations of the type
P = pmp[1.- a(T -T rnp)] up to 1100?K (pmp is the density at the melting point Trnp). Second, these metals and
cesium have similar structures in the crystal and liquid states. Finally, the coefficient a in the above equation obeys
some sort of a law, as may be seen from the following data:
Element
Na
K
Rb
Cs
a?104, deg -4
2.58
2.7
3.55
3.5[17]
3.4 [16]
1014
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
It has been assumed, on the basis of an analysis of the data, that up to the boiling point the density of liquid
cesium (Table 1) may be calculated from the equation
(2' = (1840 ? 30)11 ? (3.9 ? 0.6)
10-4 (T ? I)] kg / m3,
The surface tension a of cesium has only been measured in the temperature range from 335 to 55001< [22]. It
was shown in [23] that the values of a, known up to 7230K for sodium, are satisfactorily described by the Bachinskii
formula (parachor equation)
c (Q' Q")4.
Using the theoretical value amp c---.6?10-2 J/m2 [24] at the melting point, and the values of Fr calculated above,
the parachor equation has been used to find the approximate values of the surface tension of cesium up to the boiling
point (see Table 1). The error in these data at 9000K is probably ?30%.
Results and Analysis of Calculations
The initial data as described above has been used to calculate the thermodynamic properties of cesium for
superheated, saturated, and wet vapor at temperatures from 400 to 1500?K in steps of 50?, and for pressures from 0.01
to 22 bars in varying steps, and the data has been used to compile tables and plot the appropriate diagrams.
Table 1, for the saturated state (by temperature),contains the following data: saturation pressure ps, degree of
dissociation of the vapor a" (ratio of the number of moles reacted Cs2 to the initial number), molecular mass of the
vapor if, , specific volume v' (up to 90001151 for
U238 photofission at 14 MeV gives a d log Y/dA value which is less (in absolute value) than for spontaneous fission
and fission by quanta with niaximum energy 8 MeV.
It is difficult to compare our data for yields of 145-151 asymmetric masses with those of other investigators
because we do not know of any directly measured yields in this mass range for U238 photofission at low or medium
excitation energies. We can only compare the yields of the mirror-image masses. However, it should be mentioned
that recent data on the relation between the number of prompt neutrons and the fragment mass [23-26] render such
a comparison qualitative rather than quantitative.
It may be seen from our data that we did not find a change in the 151/143 asymmetric mass yield ratio with
a change in maximum bremsstrahlung energy from 8 to 14 MeV. This justifies the conclusion that there is no change
in fragment yields in the 143-151 mass range, or that the change in yields in the excitation energy range 6.8-11.5
MeV is very small. This probably agrees with arguments that only the yields of markedly asymmetric masses at
A> 153 and A < 83 depend greatly on the excitation energy [27]. However, a comparison of mass distribution for
U238 spontaneous fission and photofission at 8 and 14 MeV with data in [1] on photofission at 5.5.-8 MeV shows a
marked change in yields for the mass range 140-147 as one.passes from spontaneous to induced fission.
In [22] the yields for U238 photofission by y -quanta with maximum energy MeV in the mass range 99-105 were
investigated in detail; it was found that at a mass number 105 there is a deviation in the smooth course of the curve.
This was interpreted as a "fine structure," additional to the heavy peak and due to the high probability of formation
of fission fragments with complete shells of 50 protons (Snl5r). Our data for this mass region appear to corroborate
this deviation at a mass of 105.
It should be mentioned that there is another viewpoint as regards the nature of local deviations from the smooth
mass yield distribution curve. The authors of [26], who investigated hot neutron-induced U238 fission, relate such
deviations to simple variation of the probability of emission from prompt fission fragments in relation to the mass,
and they consider that the hypothesis of greater probability of magic nuclei in a fission event does not correspond
with the facts.
We are very grateful to V. P. Shvedov and A. V. Stepanov for permission to use the continuous electrophoresis
apparatus and for their help in this work.
LITERATURE CITED
1. R. Duffield, R. Schmitt, and R. Sharp, Report No. 678, Presented by the American Delegation to the Second
International Conference on the Peaceful Uses of Atomic Energy, Geneva (1958).
2. A. K. Lavrukhina, et al., In thesymp.: Physics of the Fission of Atomic Nuclei [in Russian]. Moscow, Gosatom-
izdat, p. 210 (1962).
3. V. P. Shvedov, et al., Radiokhimiya, 6, 711 (1960).
4. A. Pappas and S. Alstad, J. Inorg. Nucl. Chem., 17, 195 (1960); 15, 222 (1960).
5. R. V. Sedletskii and K. A. Petrzhak, Radiokhimiya, 4, 99 (1962).
6. D. Hume, National Nuclear Energy Series. Plutonium Project Record, Vol. 9, book 3. Radiochemical Studiesof
the Fission Products, p. 261 (1951).
7. R. Schmitt and R. Duffield, Phys. Rev., 105, 1277 (1957).
8. I. A. Vasil'ev and K. A. Petrzhak, Z. eksperim. i teor. fiz., 35, 1135 (1958).
9. H. Richter and C. Coryell, Phys. Rev., 95, 1550 (1954).
10. 0. Hahn, Applied Radiochemistry, Ithaca, N.Y., Cornell University Press (1936).
11. 0. Hahn, Z. Phys. Chem., 103, 461 (1923).
12. K. A. Petrzhak and R. V. Sedletskii, Pribory i tekhnika eksperimenta, 2, 32 (1960).
13. K. A. Petrzhak and R. V. Sedletskii, Pribory i tekhnika eksperimenta, 5. 177 (1961).
14. B. D. Kuz'minov, et al., Zh. eksperim. i teor. fiz., 37, 406 (1959).
15. R. Sher and I. Leroy, Nucl. Energy. A., 12, 101 (1960).
16. Yu. S. Zamyattiin, In the symp.: Physics of the Fission of Atomic Nuclei [in Russian], Moscow, Gosatomizdat,
p. 103 (1962).
17. L. Glendenin, C. COryell, and R. Edwards, National Nuclear Energy Series. Plutonium Project Record, Vol. 9,
book 3. Radiochemical Studies of the Fission products, p. 489 (1951).
18. A. Pannas, Proceedings of the First International Conference on the Peaceful Uses of Atomic Energy,
Geneva (1958),
1029
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
19. P. Kuroda and M. Menon, Nucl. Sci. Engng., 10, 70 (1961).
20. B. Young and H. Thode, Canad. J. Phys., 38, 1 (1960).
21. G. Wetherill, Phys. Rev., 92, 907 (1953).
22. D. Wiles and C. Coryell, Phys. Rev., 96, 696 (1954).
23. V. F. Apalin, et al., Atomnaya energiya, 8, 15 (1960).
24. J. Freser and I. Milton, Phys. Rev., 93, 818 (1954).
25. S. Whetstone, Phys. Rev., 114, 581.(1959)..
26. H. Farrar and R. Tomlinson, Canad. J. Phys., 40, 943 (1962).
27. T. Sugihara, et al., Phys. Rev., 108, 1264 (1957).
1030
All abbreviations of periodicals in the above bibliography are letter-by-letter transliter-
ations of the abbreviations as given in the original Russian journal. Some or all Of this peri-
odical literature may Well be available in English translation. A complete list of the cover-to-
cover English translations appears at the back of this issue.
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
THE EFFECT OF THE IRON MINERALS IN ORES ON OXIDATION
OF URANIUM IN ACID
G. M. Alkhazashvili, G. M. Nesmeyanova, and L. N. Kuz'mina
Translated from Atomnaya nergiya, Vol. 15, No. 4,
pp. 313-31'7, October, 1963
Original article submitted December 17, 1962
This paper gives the results of an investigation into the effect of iron minerals on extraction of uran-
ium from pitchblende in dilute sulfuric acid containing oxidizing agents. From these results a more
efficient method may be selected for extraction of uranium according to the composition of the ore
material.
This work confirms the opinion that Fe(II) ions have an unfavorable effect on oxidation of
uranium by a mixture of nitric and sulfuric acids; this shows that relatively dilute solutions of mixed
acids (40
1301
1.2 1.3 1.4 mi/m2
Relation between the over-all kinetic energy and mass ratio of fragments
during fission of U233 (a, curve 1) and Th232 (b) by 14.5-MeV neutrons, and
U233 (a, curve 2) by hot neutrons.
In [1] a single-humped curve was obtained from measurements of the Unilateral spectra of the kinetic energy
of symmetrical fission fragments (with resolution in an analyzer). This indicates recording of symmetrical fission,
but the data were obtained only during fission by 14.5-MeV neutrons when the symmetrical fission intensity was high.
The maximum error occurs during the investigation of hot neutron-induced syrnmetrical fissiOn,because in this case
there may be a considerable contribution from more intense (asymmetric) fission due to boundary effects in the tar-
get. It has been shown experimentally that for U233 fission the ratio of aSymmetric fission intensity to symmetrical
fission intensity, i.e., the ratio of the peak to the valley, is 180. Single-humped Curves were also obtained for the
Unilateral spectra of symmetrical fragments. With fission by 14.5-MeV neutrons the ratio of the peak to the valley
is 5, which agrees with radiochemical data. In the case of recording of Unilateral spectra for mass ratios slightly dif-
ferent from symmetrical fission, the curves are double-humped,with a peak ratio corresponding to the selected mass
ratio.
With use of 14.5-MeV neutrons a large number of a-particles is formed in the chamber as a result of an (n, a)
reaction in the gas. ?The a-particle energy >15 MeV because the reaction threshold is close to zero. It was there-
fore necessary to determine the effect of random coincidences of a-particle pulses and those of the fragments on the
Measured over-all kinetic energy spectra. The over-all kinetic energy of the fragments was measured during a ten-
fold variation in the bombarding neutron flux. Thevariation in the over-all value was not more than 1.5 MeV; there-
fore the effect of random coincidences is within the limits of experimental error.
The results Of measurements of the over-all kinetic energy are given in the figure. The kinetic energy of sym-
metrical fragments was measured to an accuracy of +5 MeV; the error for the other types of fission was +2 MeV.
Like the case of U235[2], the kinetic energy of symmetrical U233 fission fragments with fission by 14.5 MeV neutrons
1039
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
is 20 ? 5 MeV higher than for hot-neutron fission. A characteristic feature is that the dip in kinetic energy in the
case of symmetrical fission of U233 and Th232 by 14.5-MeV neutrons is far smaller than that in [1, 2] for U233 and U239
by such neutrons. This may be due to the appearance of a third symmetrical peak on the mass distribution curve for
U233 and Th232. The data show that there is a similarity in the behavior of the symmetrical fragment yields and their
kinetic energy during a change in the bombarding particle energy. The table gives data on the symmetrical frag-
ment yields, measured to an accuracy of 10% [3, 4] and the kinetic energies for several nuclei. The symmetrical
fragment kinetic energy for L1233 and U235 is taken from our data and [1, 2], and for Pu, from [5]. The error in the
kinetic energy determination for our investigations and [1, 2] is t5 MeV; [5] does not give the error. The difference
in the symmetrical fragment yields cannot be due to the difference in the excitation energies because the bond en-
ergies of the youngest neutron for these nuclei are very similar (see the table). Although the observed effect is prac-
tically within the limits of experimental error, an examination of the data together with those for different excita-
tion energies of the nucleus undergoing fission shows that there is some correlation between the symmetrical frag-
ment yield and their kinetic energy. It is worth noting that the behavior of the maximum kinetic energy differs from
that of the kinetic energy of symmetrical fragments and (see the table) its value increases steadily with increasing
atomic weight.
Yields and Kinetic Energies of Symmetrical Fission Fragments
Indices
Nucleus
U233
U235
Pl1293
Kinetic energy of symmetrical frag-
ments, MeV
140
135
147
Yield of symmetrical fragments, %
0.018
0.01
0.04
Maximum kinetic energy of the frag-
ments(?ml =1.25) MeV
m2
175
177
182
Bond energy of the youngest neutron,
MeV
6.74
6.39
6.38
The results of a radiochemical investigation of the products of Ra 226 fission by particles of different energy show
that there is a slight change in the symmetrical fragment yield and a considerable change in the yields of fragments
corresponding to asymmetric peaks and valleys [6]. The authors of [7] investigated the behavior of the over-all kin-
etic energy in relation to the mass ratio of the fragments during splitting of RaPsby deuterons of different energy. A
comparison of the results with those of radiochemical investigations shows that the kinetic energy changes most
markedly in the mass ratio region in which the change in fragment yield is greatest. The results in [6, 7] are in-
sufficiently accurate for any quantitative assessment. The most interesting fact in the case of Ra226 is that the kinetic
energy of the fragments increases with increasing yield and decreases when the latter decreases. This is further evi-
dence that a very general correlation exists between the fragment yields and their kinetic energy.
It may now be assumed that the kinetic energy of the fragments is determined by Coulomb repulsion during
fission, and its value depends on the effective distance between the centers of the fragment charges. As regards the
numbers of protons, symmetrical fragments from fission of nuclei heavier than thorium, and fragments corresponding
to the "heavy" valley in Ra 226 fission are included in the region of markedly deformed nuclei. Asymmetric frag-
ments belong to the region of slightly deformed nuclei. Maximum kinetic energy corresponds to fragments with a
complex neutron shell of 82 neutrons. To know the behavior characteristics of the kinetic energy of fragments, it is
evidently necessary to take into account the different deformabilities of the nuclear material during fission. In [8]
it was shown that with increasing nuclear deformation the shell effects disappear at a deformation parameter a2=0.05,
but reappear at a2= 0.2-0.3. At low excitation energies fission is adiabatic; therefore it may be assumed that in the
presence of a degree of nuclear deformation at which shell effects occur in the fragments a system which is favorable
from the energy viewpoint is produced. Fragments corresponding to spherical or slightly deformed nuclei may be
formed at lower deformations of the nucleus undergoing fission. The probability of symmetrical fission in such a case
will be defined by the ratio of the number of nuclei reaching the required deformation to the number of nuclei split
in the earlier deformation stages.
1040
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Therefore, the extent to which symmetrical fission takes place adiabatically is greater, and shell effects play
a more important role in the former than in asymmetric fission. With increasing excitation the degree of adiabatic-
ity decreases and likewise the role of the shell effects. In this case symmetrical fission may occur at lower deforma-
tions of the nucleus, which leads to an increase in its probability and an increase in the kinetic energy of the
fragments.
LITERATURE CITED
1. V. M. Adamov, S. S. Kovalenko, and K. A. Petrzhak, Zh. eksperim. i teor. fiz., 42, 1475 (1962).
2. S. S. Kovalenko, K. A. Petrzhak, and V. M. Adamov, Atornnaya energiya, 13, 474 (1962).
3. S. Katcoff, Nucleonics, 16, 78 (1958).
4. G. I. Marchuk and V. V. Srnelov, Neutron Physics [in Russian], Moscow, Gosatomizdat, p. 157 (1961).
5. I. Milton and K. Frasser, Phys. Rev. Letters, 7, 67 (1961).
6. A, Fairhall, K. Zensen, and E. Neuzil, Proceedingsof the Second United Nations International Conference
on the Peaceful Uses of Atomic Energy, Vol. 15, Geneva, UNO, p. 452 (1958).
7. H. Britt, H. Wegner, and S. Gursky, Phys. Rev. Letters, 8, 98 (1962).
8. B. T. Geilikman, Physics of the Fission of Atomic Nuclei [in Russian], Moscow, Gosatomizdat, p. 5 (1962).
All abbreviations of periodioals in the above bibliography are letter-by-letter transliter-
ations of the abbreviations as given in the original Russian journal. Some or all of this peri.
odical literature May well be available in English translation. A complete list of the cover- to-
Cover English translations appears at the back of this issue.
1041
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
DELAYED NEUTRONS FROM FISSION OF U233 BY 1 5-MeV NEUTRONS
B. P. Maksyutenko
Translated from Atomnaya gnergiya, Vol. 15, No. 4,
pp. 321-322, October, 1963
Original article submitted April 18,1963
1133
A U sample of weight 3.63 g and diameter 30 mm was bombarded by a 15-MeV neutron flux and then en-
closed in a polyethylene block containing 10 BF3-filled counters connected in parallel. A high voltage was switched
into the system simultaneously in the cascade generator and- the neutron flux fell to zero for a fraction of a second.
Two series of bombardments were carried out (300 and 30 sec). The neutron counting efficiency was 10%.
Relative Yield of Delayed Neutrons
Group No.
Half-life, sec
Relative units
1
. 55
1.00?0.01
2
24
0.78?0.04
3
15.5
1.89?0.30
4
5.2
1.20?0.37
5
9,9
8.04?1.04
The relative yields of all groups at preset half-lives (see the table) were determined from the over-all decay
curve corresponding to bombardment for 300 sec. The value of the yield ratio of the first two groups was introduced
into a system of equations describing the decay curve corresponding to 30-sec bombardment, and the relative yields
of all groups except the second one were found. The error of the result for the 3-5 groups was determined from the
scatter of the results of these two series of measurements, using Student's criterion. The relative yield error of the
first two groups was determined from the integral count and the duration of the measurement interval. The system
of equations was solved by electronic computer. The results of the calculations are given in the table.
The total yield of delayed neutrons accompanying fission of U233 by 15-MeV neutrons is 1.6 times greater than
for fission by hot neutrons and 3.8-MeV neutrons, and is 0.780 0.066 of the total yield of delayed neutrons accom-
panying hot-neutron fission of U"5.
I would like to thank N. V. Golodova for programming the calculations.
1042
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
DETERMINATION OF THE PARTIAL ALPHA-DECAY PERIOD OF P
R. B. Ivanov, A. S. Krivokhatskii, L. M. Krizhanskii,
V. G. Nedovesov, and M. I. Yakunin
Translated from Atomnaya gnergiya, Vol. 15, No. 4,
pp. 322-323, October, 1963
Original article submitted January 23, 1963
241
The isotope Punt undergoes 5- and a-decay. The partial a-decay periodT, of this isotope has been fre-
quently determined, but the results have a wide scatter. According to recent data, the partial a-decay period of
Punt has the following values: Ta = (5.62 + 0.2)? 105 years [1] and (5.72+ 0.1)? 105 years [2], as against 1 ? 106-2.5
.105 in [3-5]. The results in [1, 2] were obtained by the same method and agree closely, but differ considerably
from the values in [4, 51.
Values Used in Calculating Ta For Punt
Mass
o. of
Ni.
Sii
Ti, years
Ta for Punt,
years(cal-
culated)
238
!). 55G
2.078.10-3
86.4 [7]
3.97.105
240
0.441
6.712.10-2
6600181
4.34.105
942
0.423
0.473
3.88.10510]
3.47-105
We determined Ta by a different methodthanthat in[1, 2]. The relative Punt content of the mixture of plu-
tonium isotopes was determined by mass-spectrometric analysis, together with use of ionization a-spectroscopy. By
using a magnetic a-spectrometer [6] one may determine the intensity of a-transitions for each isotope and thereby
find the relative number of Punt a-decays. From the data obtained the partial period of Punt a-decay may be cal-
culated by means of the equation
Ni
Ti?Si '
where Tis the half-life of the isotope; Ni is the ratio of the number of Pu241 atoms to the number of atoms of the
isotope; Si is the ratio of the number of Pu241 a-decays to the number of a-decays of the given isotope.
The table gives the values of Ni, Si and T, and the Tavalues found from these. The mean value of Ta is
(3.9 ? 0.4)? 105 years, which is nearly one-and-a-half times less than in [1, 2], but agrees with [3, 4]. The authors
of [2] state that the reason for the discrepancy between their results and [3] is that the number of Punt a-decays in
[3] is too high due to Pu. In our work this error 80 MeV).
No. of neutrons/MeV ? le
4
3
2
1
2
7
3
2
r
100
200
MeV
Fig. 3. Energy spectrum of neutrons beyond a heavy-
concrete shield (p = 3.85 g/cm2) 460 cm thick: 1)
data of the present study; 2) data of [11].
where nu
do
=110dE
energy greater than El at a depth x may be written as
E0
q)(x)= N (E , x) dE e-111 I(2 Vrvtx (E0-6),
Ej
where I0 istheBessel functionof zero order for an imaginary argument. The value of n was found from the condition
of optimum agreement between the experimental data [1] and the data calculated by formula (3) for the neutron
flux at various depths; the neutron spectra in the experiments [1] were replaced by a set of monochromatic lines with
the corresponding fluxes [14-161 When (3) was compared with the experimental data, the second part of the neutron
? flux (energies of 20-80 MeV) was ignored, since as was seen above (Fig. 2), the rate of attenuation of this part
? The lower limit, 20 MeV, for,the energy range considered is found from the threshold energy of the C12(n, 2n)C11
reaction, which was used in the experiments to determine the attenuation of a neutron flux in concrete [1].
E when a neutron with an energy E' interacts with a nu-
cleus. We shall assume that u(E)=0a(E)no. The quantity
aa(E)the cross section for inelastic interaction?depends
to a considerable extent on the neutron energy when
E < 80 MeV and is constant in the range from 80 MeV
to several BeV [3-11]. This fact makes it possible to sub-
divide the integral under consideration, from Emin= 20
MeV* to 700 MeV, into two sections. We first consider
neutrons with energies greater than El= 80 MeV, for which
u, the linear coefficient of attenuation is independent
of energy. Figure 1 shows (black circles) the values of
dp (E) obtained on the basis of [12] for the secondary
dE
charged particles (mainly protons) produced by (p. C),
collisions for an initial energy of Ep= 660 MeV, emitted
at angles 0 < 30? from the direction of the primary proton.
If we consider the contribution made by the protons emit-
ted at angles 0> 30?, the values of do/dE increase some-
what in the 100-400 MeV energy range. Figure 1 also
shows the values of the differential cross section for the
emission of cascade protons at an energy of E = 460 MeV,
obtained by means of the formula
(da'= -a
dE c dE )A1 craAl ?
The values of the differential cross section of the emis-
sion of cascade protons from (p. Al) collisions are taken
from [13]. The data given in Fig. 1 permit us to assume
that the differential cross section of neutron emission
do
E) is independent of both E' and E, the energies
dE
of the primary and secondary neutrons. In this case we
obtain a simple solution of Eq. (1) for a monochromatic
neutron flux 6(E0?E) hitting the shielding:
N (E, [ti (E0?E)
1 I
x I (2 iirnix (Eo?E) , ( 2)
?
and II is the Bessel function of first order for an imaginary argument. The flux of neutrons with an
(3)
1050
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
of the flux at considerable depths is completely determined by the rate of attenuation of the flux of neutrons with
energies of more than 80 MeV.
Let us determine the distribution function for the second part of the neutron flux iP(E, x). We shall assume
that 0(E, x) satisfies the following equation:
En
? (E) (E,\ no ..?,Tdc r N (E', x) dE.
d se P-
(4)
Here Pp is the linear coefficient of attenuationof the neutron flux P(E, x)dE under conditions of poor geometry.
In other words, in accordance with the data of [171 we assume that when there are no neutrons of the first group.
0(E, x)dE depends on x exponentially. The differential cross section ? do(E) for the emission of neutrons with energies
dE
of 20-80 MeV for different nuclei is found from the data of [13] for the interaction of protons with aluminum nuclei
(it is assumed that the cross section is independentof E'). It should be taken into account that the values of pp [18]
are determined for the neutron flux hitting perpendicularly to the shielding, while the secondary neutrons have a
specified angular distribution [13]. Consequently, we must select the component of the secondary-neutron flux in
the direction of the primary flux. If we use the angular diStribution of protons with energies of 30-90 MeV, produced
when 460 MeV protons interact with aluminum, we can show that this component is equal to 0.6 times the secondary
neutron flux. With these assumptions, the solution of (4) Will be
(E, x)=-r--"P ("x "P (E)v
(x) d.v.
The neutron flux is found by integrating (5) with respect to energy from Emin to El:
E
(x)-= ill (V x) dE
min
The total flux of neutrons with energies higher than Em inwill evidently be the sum of (3) and (6):
F (x) =p (x)-1-/ (x).
(5)
(6)
(7)
Figure 2 shows how the flux of neutrons produced by bombarding a beryllium target with 660-MeV protons
varies as a function of the thickness of steel and cast-iron shielding. The data of Fig. 2 indicate good agreement be-
tween the experimental and calculated values of the fluxes for a shielding thickness of more than 20 cm (fix P11).
For individual intervals of shielding thickness the law governing the attenuation may be written in exponential form
and we may introduce such a widely used parameter as A-1_, the thickness for 50% attenuation. From the slope of
the curves of Fig. 2 for a thickness of more than 20 cm, we obtain the following values: i (exp.)= 15.9 f 0.6 cm:
(calculated)=16.5? 1.3 cm.
The table gives the calculated and measured values [1] of the 50% attenuation layers for ordinary concrete
(p 2.35 gicm3) for different energies of the neutrons hitting the shielding.
The calculation requires the values of the cross section of inelastic interaction between neutrons and the nu-
clei of the elements of which the shielding is made; these are taken from [3-11]. For heavy concrete with a spe-
cific weight of 3.85 g/cms, the Values of at a shielding depth of 3-4.5 m, calculated by the Monte Carlo method
:[11] and Eq. (3), are equal to 25.3 ? 2.5 and 24.5? 0.07 cm, respectively. The experimental and calculated results,
shown in Fig. 2, indicate that for a shielding thickness greater than the relaxation length (?x=1) the flux of neu-
trons with energies above 20 MeV may be described by the following formula:
F (x)-.= I..3e7L" I (2 (Eu-- 1)).
(8)
For the condition of optimum agreement between the measured and calculated values of Al for ordinary concrete
arid an energy of 660 MeV, the value of the coefficient ti was found to be 1.3.10-3 MeV-1. It is difficult to say
whether the value of the coefficient n remains strictly constant for the various elements of which the shielding is
made.
1051
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25 : CIA-RDP10-02196R000600110002-5
Figure 3 shows the energy spectrUm of the neutrons' at a depth of 460 cm, obtained by means of Eqs.(2)and(5)
for the case when a monochromatic flux of 300-MeV neutrons impinges perpendicular to the shielding. It also
shows the spectrum of particles (chiefly neutrons) calculated by the Monte Carlo method [11]. The flux of neutrons
that did not interact is shown in spectrum 1 by the column. Energy spectrum 2 was normalized by using the con-
dition that the areas under curves 1 and 2 from 100 MeV to 200 MeV were equal. The considerable difference be-
tween the spectra in the 250-300 MeV range is apparently due to the fact that the value of the differential cross
section for the emission of secondary neutrons in this range is somewhat high in the present study, while it is some-
what low in the study referred to by Lindenbaum [11].
The authors thank V. P. Dzhelepok, for his valuable comments and N. A. Chernikov for his evaluation of the
methods for solving the kinetic equation.
LITERATURE CITE))
1. L. N. Zaitsev, M. M. Komochkov, and B. S. Sychev, Atomnaya Energiya, 12, 525 (1962).
2. 0. I. Leipunskii, B. V. Novozhilov, and V. N. Sakharov, Distribution of Gamma Quanta in Matter [in Russian].
Moscow, Fizmatgiz (1960).
3. B. V. Gavrilovskii and V. I. Moskalev, Dokl. AN SSSR, 110, 972 (1956)..
4. H. de Carvalho, Phys. Rev., 96, 398 (1954).
5. T. Coor et al., Phys. Rev., 98, 1969 (1955).
6. I. Cassels and I. Lawson, Proc. Phys. Soc., 67A, 125 (1954).
7. G. Millburn et al., Phys. Rev., 95, 1268 (1954).
8. F. Chen, C. Leavitt, and A. Shapiro, Phys. Rev., 99, 857 (1955).
9. V. Nedzel, Phys. Rev., 94, 174 (1954).
10. V. S. Pantuev and M. N7Khachaturyan, Zh. eksperim. i teor. fiz., 42, 909 (1962).
11. S. Lindenbaum, Ann. Rev. Nucl. Sci.,-11, 213 (1961).
12. L. S. Azhgirei et al., Zh. eksperim. i teor. fiz., 36, 1632 (1959).
13. N. Metropolis et al., Phys. Rev., 110, 185 (1958).
14. V. P. Dzhelepov et al., Izv. AN SSSR, Ser. fiz., 19, 573 (1955).
15. V. S. Kiselev et al.. Zh. gksperim. i teor. fiz., 35, 812 (1958).
16. W. Goodell, H. Loar, R. Durbin, and W. Havens, Phys. Rev., 89, 724 (1953).
17. B. Moyer et al., AECD-2149 (1947).
18. M. Livingston and J. Blewett, Particle Accelerators (1962).
1052
All abbreviations of periodicals in the above bibliography are letter-by-letter transliter-
ations of the abbreviations as given in the. original Russian journal.. Some or all of this periodical literature may well be available in English translation. A complete list of the cover-to-
cover English translations appears at the back of this issue.
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
THE EFFECT OF REFLECTORS MADE OF VARIOUS MATERIALS
ON THE INCREASE IN THE NUMBER OF NEUTRON CAPTURES
IN THE URANIUM BLANKET OF A FAST REACTOR
V. I. Golubev. A. V. Zvonarev, M. N. Nikolaev,
and M. Yu. Orlov
Translated from Atomnaya E.nergiya, Vol. 15, No. 4,
pp. 327-328, October, 1963
Original article submitted March 13, 1963
As was shown in [1], the use of additional reflectors considerably increases the number of neutron captures in a
blanket zone consisting of metallic uranium. The purpose of the present study is to investigate the effect of addi-
tional reflectors on the increase in the number of captures in a blanket zone made of uranium carbide.
Increase in the Number of Neutron Captures in a Reactor
Blanket
raterial of addi-
ional reflector
Beryllium
Graphite-
Nickel
Iron
Copper
1Kh18N9T steel
Water
Uraniurn carbide
Uranium
Reflector
thickness
Ill
135
Uranium
carbide
Metallic
uranium
140
600
192
184
184
160
144
co
co
0.64?0.08
0.50?0.08
0.47?0.07
0.42?0.07
0.24?0.06
0.33?0.06
0.23?0.06
1.00
0.86?0.10
0.51+0.10
0.28?0.09
0.41?0.09
0.40?0.09
0.49?0.10
? ?
1.00
In the present study, as in [1], we investigated the effect of additional reflectors on the asymptotic region of
the neutron spectrum [2].
The measurements were made on the BR-1 reactor [2]. The blanket of the reactor was built up from slugs of
enriched uranium and graphite 47 mm in diameter and 10 mm high. The slugs were built up in columns (one graph-
ite slug for each two slugs of uranium).
The resulting grid had a uranium-to-carbon nucleus ratid of 1 to 0.884, which is approximately the same as
the value found in uranium carbide. The assembled reactor blanket had the shape of a regular hexagon 1100 mm on
a side and 700 mm high. Additional reflectors made of beryllium, water, iron, copper, nickel, graphite, orlKhl8N9T
steel were placed against one face of the blanket. The thickness of most of the additional reflectors was selected
on the basis of the results found in [1]. We used thicknesses for which it had been found that any further increase in
the reflector thickness did not add to the number of neutron captures in the uranium reactor blanket. A number of
thicknesses were tried for the iron and graphite reflectors. It was found that for the graphite reflector an increase in
thickness beyond 600 mm did not appreciably increase the number of captures in the blanket, while for the iron re-
flector the value was 184 mm.
In order to verify that the asymptotic spectrum had been established and to determine the number of captures
in an infinite uranium carbide blanket, we increased the thickness of the reactor blanket in one direction by 350 mm.
It was found that for a blanket of the chosen dimensions, an asymptotic spectrum is established in the region of low
energy neutrons, which play the chief role in the U238 (n, U239 reaction.
We measured experimentally the distribution of U238 neutron capture density in the reactor blanket both with
and without additional reflectors made of the above-mentioned materials. In addition, we plotted a curve of the
1053
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25 : CIA-RDP10-02196R000600110002-5
neutron capture density distribution in the thickened uranium carbide blanket. The radiative capture of neutrons
in the uranium was determined from the Li activity of irradiated specimens of powdered uranous-uranic oxide, from
which the fission fragments had been chemically removed. Weighed amounts of the powder were placed in flat al-
uminum containers 47 mmin diameter and 3 mm high (the U308 layer was about 1 mm thick) and then put be-
tween the blanket slugs at the level of the center of the reactor active zone. Inorder to take account of the in-
homogeneity produced in the neutron flux by the slight heterogeneity of the uranium-carbon mixture in the reactor
blanket, the specimens were placed both between uranium slugs and between adjacent slugs of uranium and graphite.
To determine the efficiency of the additional reflectors we used the ratio of Bi= Ai/Auc, where Ai is the dif-
ference between the total number of neutron captures in uranium with and without the i-th additional reflector, and
Auc is the same difference for an infinite uranium carbide reflector. The results of the measurements for blankets
made of uranium carbide and metallic uranium [1] with various additional reflectors are shown in the table.
It can be seen from the table that the efficiency of the materials that produced considerable softening in the
neutron spectrum (water, beryllium) became substantially lower when the uranium blanket was replaced by a uranium
carbide blanket, while the efficiency of the heavy materials was only slightly reduced and was even increased in the
case of iron, since the effects of the deep interference minima [1] which had been found in the cross section of iron
at energies above 25 keV were not noticeable the case of a uranium carbide blanket, owing to the high degree of
softening of the neutron spectrum.
In conclusion, the authors thank I. I. Bondarenko for his valuable comments and advice, as well as N. D.
Golyaev, P. V. Kindinov, Yu. F. Koleganov, K. I. Nesterov, and E. A. Osipov for their help with the measurements.
LITERATURE CITED
1. V. I. Golubev, A. V. Zvonarev, M. N. Nikolaev, and M. Yu. Orlov, Atomnaya Energiya, 15, 258 (1963).
2. A. I. Leipunskii et al., Atomnaya Energiya, 5, 277 (1958).
1054
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
CALCULATION OF THE .1)ECTRAL AND ANGULAR DISTRIBUTION
OF SCATTERED y -QUANTA FROM A POINT MONODIRECTIONAL
Cs137 SOURCE IN IRON
L. R. Kimel', A. M. Panchenko, and V. P. Terent'ev
Translated from Atomnaya gnergiya, Vol. 15, No. 4,
Pp. 328-331, October, 1963
Original article submitted February 28, 1963
The problem of the spectral and angular distribution of scattered y -quanta from a point monodirectional
source was solved by the Monte Carlo method. The source, located in an infinite iron medium at the point 0 (Fig.
1), emitted y-quanta with
an initial energy E0= 0.661 MeV in the positive direction of the h axis. The spectral and
angular distribution were determined for the scattered energy which
passed through rings Arj located in planes normal to the beam at
distances hi from the point 0. The spectral and angular distribu-
tion of the scattered energy per unit area at distances rj from the
beam were obtained by averaging the results for the distribution
within the rings Arj.
The following values of hi were selected:
Fig. 1. Geometry used in the computation.
i
?3-2.-1
0
1
2
3
6.
5
h, cm
?4
?2
?0.5
0
2.4
4.8
7.2
9.6
12
Negative values of h Corresponded to the reverse half-
space, which was beneath the plane passing through the point 0
normal to the beam.
Each plane was subdivided into rings with radii rj:
i
0
1
2
3 4
5
6
r, cm
0--0.50.5-1
1-1.7
1.7-2.7
2.7-4
4-5.5
5.5-8
A study was made of 5420 y-quanta histories involving the following sequence of events [1]: the y-quantum
path to the first interaction and the type of interaction were determined: in the case of Compton effect, the energy
of the scattered quantum and its direction of flight after scattering were calculated. Such a sequence of calcula-
tions was repeated until the quantum disappeared as the result of photo-effect or until the quantum fell into the en-
ergy region below 10 keV. Upon penetration of a ring by a scattered quantum, the energy of the quantum was re-
corded along with the angle 0 between the quantum velocity vector and the normal to the ring at the point of pene-
tration and also the angle y between the projection of the quantum velocity vector on the plane normal to the beam
and the radius drawn in this plane through the point of penetration (see Fig. 1). The calculations were done on the
"Strela-3" electronic data processing machine in the Computing Center of the USSR Academy of Science.
1055
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
In order to obtain the random numbers needed for the calculations, a special program previously suggested [2, 3],
was used in the machine.
i=1;
1.0
0.8
30?< y< 90?
0.6
0.4
0.2
or.
-
tOr02...A
1.0
0.8
0.6
0.4
0.2
7.0
0.8
0.6
0.4
0.2
r&ez
? 0.8
2 0.6'
5, 0.4
.5 0.2
7.0
0.8
0.6'
0
0.2
1.0
0.8
0.6
0.4
0.2
? 0
Oh
02 0-6 0.6' 0
0 02 Oh
j=1.1=1; j=2
90?4 y 3UCI3. 2ZnC1-! - Zn2'.
of the zinc electrode potential in a sodium chlor-
ide-potassium chloride melt with 4 wt.a/oU4+ in rela-
The monovalent state of zinc in the compound was
tion to temperature.
confirmed qualitatively. A zinc compound was not formed
when zinc chloride was added to a melt containing us,
ions (with reduction of U4+ ions by uranium metal); one was formed when zinc metal was added to a melt containing
Us+ and Zn2+ ions. It must be admitted that a certain amount of alkali metal chlorides might also form part of the
compound. Its composition would then be more complex:
3UCI3. 2ZriCl? n (Na, K) Cl.
When the electrolyte and the compound were dissolved in water, the latter was decomposed and hydrolysis took place.
Zn2U3(.:I11-} 01120 --> 4-2U(0104 --1-2ZnC12+ 4I1C1+ 2 -2- H2.
As a result of instability in aqueous solutions, uranium-zinc chloride of lower valences could not be separated for
analysis and further investigation.
We determined the time necessary for displacement of uranium from fused sodium and potassium chlorides by
zinc. Figure 1 shows the relation between the reaction of zinc metal with an equimolecular sodium chloride-po-
tassium chloride mixture to which uranium tetrachloride was added, and time. Stabilization of the zinc potential
corresponds to the end of the reaction. It may be assumed that in the investigated concentration range, stabilization
of the zinc potential is directly proportional to the uranium content of the melt (for the same area of the zinc sur-
face and at constant temperature, e.g., 800?C). Reduction of uranium to the trivalent state and formation of a com-
pound take place on the zinc metal surface in contact with the electrolyte. It may be assumed that the rate of com-
pound formation will be determined by the rate of transfer of e ions to the zinc surface via the diffusion layer of
the electrolyte. Thereforeothe reaction rate will depend on the diffusion coefficient D of the U4+ ions in the sodium
chloride-potassium chloride melt.
D = Do exp(_ -1) therefore there must be a linear relation between the log of the amount of uranium displaced
RT
during the reaction and the reciprocal of the absolute temperature. Figure 2 gives the relation on a semilog scale
1067
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
between reaction time and temperature under constant experimental conditions. The above linear relation shows
that the limiting stage in the reaction is transfer of U4+ ions to the surface via the diffusion.
LITERATURE CITED
1. J. Katz and E. Rabinovich, Chemistry of Uranium [Russian translation], Vol. 1, Moscow, Izd-vo inostr. lit.,
p. 362 (1954).
2. I. F. Nichkov, S. P. Raspopin, And Yu. V. Bazhkov, Zh. prikl. khim., 33, 9, 2136 (1960).
3. I. F. Nichkov, S. P. Raspopin, and A. F. Tsarenko, lzy. vyssh. Uchebn. zavedenii, Tsvemaya metallurgiya, 5
(1962).
All abbreviations of periodicals in the above bibliography are letter-by-letter transliter-
ations of the abbreviations as given in the original Russian journal. Some or all of this peri-
odical literature may well be available in English translation. A complete list of the cover- to-
cover English translations appears at the back of this issue.
1068
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
A NEW TYPE OF POROUS BED MODEL FOR NEUTRON LOGGING
N. K. Kukharenko, Ya. N. Basin, Yu. P. Bal'vas, and Yu. V. Tyukaev
Translated from Atomnaya gnergiya, Vol. 15, No. 4,
pp. 338-339, October, 1963
Original article submitted October 4, 1962
The successful resolution of research problems in neutron logging through the study of geological borehole
sections would have been unthinkable without an extensive modeling of porous beds [1]. We shall briefly describe
foreign practice in the fabrication of porous-bed models [2]. Blocks of natural rock of a certain lithology and
porosity are fashioned in quarries and given a specified shape and size. The rocks are partially dried due to exposure
on outcrops, so that they have to be saturated with water or some other fluid prior to fabrication. This technique
is highly laborious and even so the resulting models suffer from some important defects: it is difficult, fOr instance,
to find suitably large blocks of rockhaving adequately preserved porosity throughout their bulk; firm monolithic blocks
of rock generally feature low permeability and this hampers fluid saturation; replacement of the fluid filling the pore
void of the model (e.g., replacement of water by petroleum) is virtually impossible, and this acts as a severe limit-
ing factor in experimental practice.
TABLE 1. Hydrogen- and Chlorine-Containing Models
Bed material
Water content, in water
equivalents, ak
Cl,
g/liter
(for total
bed volume)
uniform
distribu-
tion
in hori-
zontal
layers
in verti-
tical
rods
total
Sand
Sand with horizontal celluloid
layers
Sand with finely divided celluloid
evenly distributed throughout the
volume
Sand with lattice
Sand with finely divided lattice
material
4
4
6.5
4
9.5
?
2.5
?
2.5
?
?
?
?
3.0
?
4
6.5
6.5
9,5
9.5
?
?
?
10
10
A model simulation technique based on the principle of similitude has been proposed in recent years [3]. How-
ever, this method likewise suffers from some flaws. First, each new model having a different similitude ratio re-
quires a far-reaching transformation of the borehole instrument; secondly, the design of such models is rendered more
difficult by the problem of choosing some substance identical to the fluid filling the borehole and the bed, and re-
placing that fluid for other measurement conditions.
The authors have developed a new type of model for porous beds, one free from the flaws mentioned.* The
outstanding feature of this new line of models is the presence of an artificial pore void. This is brought about by a
system of horizontal cavities sandwiched between sheets of dense rock and vertical holes in the sheets. The volume
is the same for both. The sheet thickness and the distance between holes (channels) is less than the mean free path
length Of fast neutrons. The pore void and the borehole model can be filled with ease with any fluid required for
the purpose.
This work was performed at the All-Union Geophysics Research Institute and at the All-Union Research Institute
for Nuclear Geophysics and Geochemistry (VNIIG and VNIIYaGG).
1069
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
-e- -e-
-e- -0--
-Cr
Arrangement of hydrogen-containing rods in experimental ?
heterogeneous "sand-lattice" model.
TABLE 2. Results of Neutron-Gamma Core Sampling Measurements for Different
Hydrogen Distributions in Models (Arbitrary Units)
50-cm probe
24-cm probe
Bed
borehole
borehole
wall
center
wall
Sand
4.47
3.32
1.51
Sand with horizontal celluloid layers
3.38
2.64
1.61
Sand with finely divided celluloid
3.62
2.96
1.45
Sand with lattice
3.26
2.91
1.38
Sand with finely divided lattice
material
3.30
2.97
1.41
? An artificial pore void differs substantially from natural bed porosity in size, shape, and distribution through-
out the bulk of the rock. This necessitates that the interchangeability of natural and artificial void be justified either
theoretically or empirically.
Monte Carlo methods may be used to arrive at results of sufficient accuracy, but no general solution is ob-
tained thereby and,moreover,this approach requires running a program for each variant of the model on a high-speed
electronic computer. Beginning steps in this direction have already been taken for a simplified pore-space geometry.
At the same time, experiments were conducted on a sand bed model of 40% porosity and 4% moisture content. Sand
of this moisture content is roughly equivalent to limestone of 1% moisture content in its moderating properties.
Additional water content in the bed (see Table 1) is brought about by a system of horizontal layers of celluloid sheet
(2 mm thick in every 50 mm sand), a lattice formed of the same layers and of vertical rods (vinyl chloride tubes of
of 14/11 mm diameter, paraffin-impregnated, see the figure), pulverized material, evenly mixed with the sand, of the
type Composing the horizontal layers and the lattice. The celluloid, paraffin, and vinyl chloride material contained,
in addition to hydrogen and chlorine, a few other elements. Their effect might be safely ignored on account of their
scarcity and, their closeness in their neutron properties to oxygen, which is one of the principal components of sand.
In-model experiments were carried out by neutron gamma-logging using-probes 50 and 24 cm long in a bore-
hole 15 cm in diameter and filled with fresh water. A VS-14 counter with 0.5-mm thick cadmium lining was used.
The results (Table 2) appear in arbitrary units (readings of the appropriate neutron-gamma core sampling probe in
fresh water).
We learn from Table 2 that:
1. In the presence of horizontal hydrogen-containing layers, the neutron-gamma log readings were lower for
the large probe (50 cm) and higher for the small probe (24 cm) than the readings taken for a homogeneous porous
medium of the same hydrogen content. The tabulated hydrogen content in a bed is consequently equivalent to some
1070
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
hydrogen content larger than the real one (some fictitious water saturation). The differences (derived from com-
parison to readings for a homogeneous medium) are 7% for the large probe and 11% for the small probe. It is pos-
sible to make an approximate estimate of the additional fictitious water saturation from measurements with the 50-
cm probe, if we assume the probe readings to be a linear function of the logarithm of water saturation for the range
in question. The additional fictitious water saturation will come to roughly 1 abs.
2. The neutron-gamma probe readings for both large-probe and small-probe measurements in beds made of
sand-with-lattice and the same sand with finely divided lattice material uniformly distributed throughout are al7
most identical (differing by 1 to 2%). In particular, we see that anisotropy of the bed with respect to hydrogen con-
tent brought about by the vertical rods affects the probe readings in just about the same way as anisotropy due to
horizontal layers, but with sign reversed. In arriving at this conclusion, we neglected a slight effect exerted by chlor?
me anisotropy of the sand-with-lattice bed on the probe readings. Tentativecalculations demonstrate that this con-
tribution is negligible, however.
The above account confirms the possibility of fabricating artificialporous beds, which we here term hetero-
geneous porous beds. The new type of model holds great promise and greatly facilitates the solution of research prob-
lems in nuclear geophysics. Experimental models of carbonate beds of 11% and 15% porosity for use in neutron core
sampling research are now being designed.
1.
0. A. Barsukov
izdat (1958).
2. I. T. Devan. Symposium on Industrial GeophysimNo. 2 [in Russian], Moscow, Gostoptekhizdat (1960), p. 40.
3. Sh. A. Guberman, Similitude theory and borehole radiometry [in Russian], Moscow, Gostoptekhizdat (1962).
LITERATURE CITED
et al., Radioactive methods in studies of oil and gas boreholes [in Russian], Moscow, Gostoptekh-
1071
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
SECONDARY DUST COMPONENT OF RADIOACTIVE CONTAMINATION
IN THE SURFACE LAYER OF THE ATMOSPHERE
B. I. Styro, Ch. A. Garbalyauskas, V. I. Luyanas, V. P. Matulyavichus,
T. N. Nedvetskaite, and I. S. Tomkus
. Translated from Atomnaya inergiya, VOL 15, No. 4,
pp. 339-341, October, 1963
Original article submitted December 8, 1962
A suggestion dating back Several years [1] held that a component raised from the ground by the wind in as-
sociation with finely dispersed dust must be included in the composition of radioactive impurities present in atmos-
pheric air. Subsequently, Reiter [2] discovered, on measuring the concentration of radioactive impurities in both
mountain and valley air [2] and taking the ratio of the quantities of-long-lived and short-lived components at both
such points, that the first ratio was consistently greater than unity, the second consistently less. The explanation
offered [11 is as follows. Aerosols settling down from the upper-lying layers of the atmosphere become mixed with
radioactive substances accumulated over a long period on the earth's surface and raised by turbulent currents and
by the surface air layer. This surface dust contains fallout in which long-lived isotopes predominate.
TABLE 1. Radioactive Fallout in Lithuania, July-August, 1961
Sampling
site
Nature of underlying surface
Weight
of ashed
sample
residue,
mg
Count of rate
sample
Average
half-life
of sample
activity,
days
cpm
cpm ? g
Vir nius
Shilute
Pile station
Nida
Sandy ground, overgrown
Meadowland, thick overgrowth
Water surface
Running sand covered with sparse flora
1992
1553
1823
4667
235
271
195
522
118
174
107
112
36.5
57.8
57.8
31.5
TABLE 2. Amount of Sr" Present in Radioactive Fallout (July-August, 1961)
Sampling
site
Amount of
Sr" pre-
cipitated,
PC/km2
Amount of
90
Sr precipi-
tated with
fallout,
? C /km2
Amount 'of
precipitate,
mm
Amount of
90
Sr per mm
precipitate,
uCikm2. mm
Primary
component,
? C /km2
Secondary
component,
? C/km2
Fraction of
secondary
component,
16
Vin'nius
Shilute
Pile station
Nida
85.3
127.5
67.8
61.6
76,8
114.7
61.0
55.4
116.0
276.3
226.8
101.6
0.66
0.42
0.27
0.27
31.3
74.6
61.0
55.4
45.5
40.1
0.0
0.0
59
35
0.0
0.0
Samplings were made in July and August; 1961 to reveal the secondary component in radioactive fallout and
to estimate its quantity. Four sampling points were chosen: the region of the village Nida on. the Kursk sand bar
(at bar width -2 km),separated nom. the mainland by a 12-km bay; at a pile station in the Kursk Bay,5 km from the
sand bar and 7 km from the mainland; in the district of the village Shilute, situated 15 km from the seashore, and
in the region of Virnius (the Eruzale post at a distance of -6 km from the city), some 270 km from the shoreline.
1072
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
'
Radioactive fallout samples were collected on the surface of distilled water in vessels presenting 3200 cm2
surface area, positioned at a height of 0.8 meter above sea level (at a height of ?5 meters above the water level
in the case of the pile station). The water was changed once every ten days in the period from July 6 to August 29,
1961, evaporated, and the solid residue was ashed at 500?C.
The activity of the samples collected was measured with an end-window counter, (1.1 mg/cm2 thick mica
window), following the conventional practice with self-absorption in the sample taken into account. The findings
appear in Table 1. Radiochemical isolation of the Sr90 from the samples was the next step. In this we were kindly
assisted by Prof. V. P. Shvedov, with the analytical work entrusted to N. A. Susorova, to both of whom the authors
are deeply indebted.
The relatively large amount of solid residues collected at Nida is accounted for by the existence at that point
of fine quartz sand piled up by the strong wind and collected in a cuvette, despite the fact that the terrain is cov-
ered by sparse grass. Fine sand grains were carried and deposited by the strong westerly wind even onto the pile
station lying 5 km out from the sand bar, and the amount of precipitate collected out there was also comparatively
large.
The short effective half-life of the activity of samples collected at Nida and Virnius are apparently due to
the presence to some components of the naturally radioactive series in the sandy ground.
The minimum of the total activity of the fallout material was discovered at the pile station 7 km off from
the mainland, where the possibility of radioactive material and mainland dust impinging is apparently restricted.
These data bear evidence of the prominent role played by the dust component blown into the cuvette when turbulent
mixing occurs in the ground layer of the atmosphere. The nature of the underlying surface of the restricted region
immediately adjacent to the observation point exerts a substantial effect on the activity of the samples collected
(see Table 1).
Table 2 lists information on the amount of Sr90precipitated duringJulyand August, 1961. Since the activity
of the dry fallout was 10 to 40% of the total activity [3-5], and possibly includes to some extent the secondary dust
component, we assume the fraction of the total activity due to dry fallout to be 10%. Assuming this quantity to be
40%, say, the fraction of the secondary component appearing in the last column of Table 2 will agree with the values
given to within 1%. After subtracting these 10% from the entries in the second column, we obtain the amount of
Sr90 precipitated with the fallout. Again, assuming the secondary dust effects above the pile station in the bay to be
insignificant, we take 0.27 fiC Sr90 per km2' mm as the activity contributed by fallout reaching the ground, with no
perceptible secondary effects added. This assertion is apparently close to the truth since westerly rains and winds
were observed during that period sweeping shoreward air masses into the neighborhood of Nida and the pile station
immediately after these air masses passed over the Baltic Sea. The sampling point at Shilute was 15 km away from
the shore of the Kursk bay and 20-22 km from the pile station. We may, therefore, assume that the synoptic proc-
esses developed above these sampling points were the same during the period of observation, and that the activity
swept out of the troposphere by the fallout precipitates was in consequence the same as well. This permits us to as-
sume that 1 mm of fallout precipitate at Shilute also accounts for 0.27pC Sr" per km2. mm. A similar inference
with respect to Virnius is less reliable, however.
Making use of the values and fallout data listed, we may calculate the amount of Sr90 falling out at Shilute
and Virnius in rainfall, and the contribution of secondary effects. The data indicate 35% and 59%, and are highly
significant. Even though the data for the Vii' nius region may meet with some objection, considering the distance
of the pile station sampling post from that city, the data referable to the Shilute area appear to be close to the real
values.
If the fraction of the secondary component is about 35%, then this contribution must be taken into account
in an estimate of the build-up of fallout activity on the earth's surface. It should be borne in mind that the investi-
gations were conducted during the summer, in a lull in nuclear weapons testing. Values at variance with the ones
reported could be obtained at some other time. The numerical values for the fractions of secondary precipitates
might be different for other isotopes, and might be different again if this process were studied in areas featuring a
different underlying surface and flora.
The authors make no pretension to a high order of accuracy in the values cited for the contribution of the
secondary effect. The purpose of this communication is to demonstrate that this effect may be a significant one,
and at the same time to draw the attention of the scientific community to the problem of setting up and performing
similar investigations, with attendant experimental difficulties.
1073
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
The authors express their acknowledgements to students R. Minkyavichus and R. Kozhenyauskas of the Virnius
State University for their invaluable assistance in the work of the sampling expedition.
LITERATURE CITED
1. B. I. Styro, Problems of nuclear meteorology [in Russian], vile nius (1959), p, 1.
2. R. Reiter, Naturwissenschaften, 47, 300 (1960).
3. E. Wilkins, Trans. Amer. Geophys. Union, 39, 30 (1958).
4. W. Gerlach and K. Stirstadt, Atomkem Energie, 4, 143 (1959).
5. W. Marquardt, Z. Meteorol.,15, 221 (1961).
1074
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
NEWS OF SCIENCE AND TECHNOLOGY
CONFERENCE ON ELECTROSTATIC GENERATORS
AND DIRECT-VOLTAGE ACCELERATORS
G. M. Osetinskii
Translated from Atomnaya griergiya, Vol. 15, No. 4,
pp. 342-343. October, 1963
A workshop attended by Member nations of the Dubna Joint Institute for Nticleat Research was held in late
March, 1963 at Dubna to disciiss the physiCs and engineering of electrostatic generators and direct-voltage acceler-
ators.
The conference was attended by over 70 specialists from member nations of the Joint Institute, including vari-
ous institutional representatives from the Soviet Union. Interest in the Conference was high, for a vast amount of ex-
perimental material has been accumulated in recent years, both on the operation of electrostatic generators and on
the design of individual components.
Thirty-three papers were presented to the conference on the design of electrostatic generators, techniques for
focusingparticle beams, design of ion sources for various electrostatic generators, and various sets of operating con-
ditions. A special session was devoted entirely to the design of polarized sources and direct-voltage accelerators.
A paper presented by V. I. Chetvertkov (NTIEFA?the D. V. Efremov Research Institute for Electrophysical Equip-
ment) took Up various aspects of the development of high-precision systems for stabilizing accelerating voltages (sta-
bilization to about +0.01%) in proton-accelerating electrostatic generators. The formulas submitted by the author
make it possible to estimate the energy variation of accelerated particles When due to instability in the angle of in-
flection and in the position of the beam as it enters the analyzer magnet, as well as instability of the position of the
slit terminal device. This paper also examined for the first time an ion-optics technique for measuring energy fluc-
tuations of charged particles, using beam deflection prior to entry into the magnetic analyzer. This method is dis-
tinguished by its high speed and makes it possible to measure the conductor-potential instability even in the presence
of a liner. The time-of-flight of negative corOna ions in the high-voltage gap of an eledirostatic generator was cal-
culated, and an expression was offered for the transient, frequency, and phase response characteristics of the corona
spray triode.
A repott by M. Cihak (Nuclear Research Institute of the Academy of Sciences of the Czech SSR) was devoted
to designs of high-voitage stabilization circuits in electrostatic generators, to an accuracy not inferior to 10-4, and
based on the general theory of automatic control.
V. I. Chetvertkov and A. L. Fedulov (NIIgPA) rendered an accOunt of the performance of an accelerating volt-
age stabilization network at ?150-200 keV for a neutron generator at currents to 3 mA, designed with transistor and
magnetic components. The network stabilizes to within 1-2%, is inexpensive, and is in practice ready for operation
immediately after plugging in.
Stabilization of the magnetic field of electromagnetic analyzers by nuclear magnetic resonance was the sub-
ject of a paper presented by V. G. Kunstman (NIIEFA). The author showed that high accuracy in the reproduction
of a field distribution, and consequently high accuracy in measuring beam energy of an electrostatic generator re-
quires that the analyzer field follow a specified cycle consistently, otherwise the error in energy Measurements will
run to 0.5%. If the field is programmed to consistently follow a specified hysteresis loop, at a rate not exceeding 20
0e/sec, the analyzer may provide an accuracy of about 10-4 of relative energy measurements. The error
will increase as the rate of change, and the error increase will be less on the downward branch of the hysteresis loop
than on the ascendant branch.
P. E. Vorotnikov (I. V. Kurchatov Institute of Atomic Energy) calculated the phase focusing (bunching) of ions
emerging from an ion source by a variable longitudinal electric field, to obtain current pulses lasting ?10-9 sec at a
pulse repetition rate 106 to 101 sec-1 from an electrostatic generator. It was shown that a conventional low-current
1075
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
ion source yields pulses lasting 3. 10-9 sec at a pulse current of "4-1.5 mA at the accelerator exit when a buncher
electrode is added to the ion-optical system. This current is 10 to 30 times larger than currents now achieved. This
mode of operating an electrostatic generator has some important practical applications (time-of-flight spectrometry,
study of short-lived nuclides, work under high background-level conditions, etc.).
The paper "Remarks on focusing of ion beams in electrostatic generators" submitted by D. Paris (Academy of
Sciences of the Hungarian People's Republic) was received with rapt attention. The author presented the operating
details of the ion evacuation system using a high-frequency source, and pointed out the intriguing possibility of focus-
ing a beam with a resultant reduction in the amount of gas used up in the source. Attention was directed to the sali-
ent features of focusing multicomponent accelerator tubes.
T. Saidl (Institute of Nuclear Research of the Academy of Sciences of the Czech SSR) reported calculations of
the principal optical parameters of accelerator tubes (focal length, transverse magnification, ratio of inner and outer
beam diameters, etc.).
Papers submitted by G. Ya. Roshar (NIIiFA), V. A. Romanov (Power Physics Institute), E. Gurski (Academy of
Sciences of the Polish People'sRepublic), J. Cirak (Academy of Sciences of the Czech SSR), G. Winger (East Germany)
presented the results of experience in the design and operation of 2 to 5 MeV electrostatic generators.
Much attention was given to ion sources for dc electrostatic generators.
A report by S. G. Tsepakin et al. (NIIEFA) told of the development of high-frequency ion sources at currents
300 ?A, 2 mA, 10 mA. A series of duaplasmatron type sources at 20 mA current in the steady state and 0.05, 0.5,
and 1.5 A in pulsed operation has been developed. Data on sources using a Penning type discharge and operated in
pulsed mode with 15 mA current were presented. Electron sources with currents of 1 and 10 mA in the steady state
were also reported on.
A paper submitted by N. F. Ivanov, V. S. Kuznetsov, A. I. Solnyshkov (NIIEFA) entitled "Shaping of pulsed
ion beams with current of the order of hundreds of milliamperes in dc accelerators" presented a procedure for design-
ing the optical system of high-current beams with volume charge taken into account. This method is used for design-
ing the optics of a hydrogen ion injector at 400 mA and 700 keV energy. The results of the measurements, which
were in agreement with theoretical prediction, were reported. A beam 15 mm in diameter with 400 mA current and
700 keV beam energy was obtained.
A. N. Serbinov and V. I. Moroko (Power Physics Institute) reported on a pulsed high-frequency source with a
honeycomb extraction system. Tests were run on two variants of the extraction system, differing in the size of the
cathode?anode space (1.8-2.2 mm). In the first variant an ion current of 21 mA in a pulse lasting 1 ?sec was ob-
tained in acceleration to 270 keV energy. The second variant yielded a current of 220 mA. The gas flowrate of
the hydrogen source was 15 cm3/h.
A paper by P. S. Markin (Academy of Sciences of the Ukrainian SSR) cited data on an inexpensive ion source.
This ion source is based on an arc discharge in an axial magnetic field with a heated cathode, hollow anode, and in-
sulated anticathode (modeled after the Abel?Meckbach source). The source was studied in steady state and in pulsed
operation. Doubly-charged carbon, nitrogen, and oxygen ions are found in the spectrum of the ion source.
A paper by V. I. Man' ko (Institute of Atomic Energy) dealt with parallel feed of ion sources into a double-tube
electrostatic generator.
B. P. Ad' yasevich (Institute of Atomic Energy) reported on the fabrication, design, and testing of a source of
polarized ions (protons and deuterons) in which polarization of nuclei in an atomic beam is achieved by adiabatic
extraction of hydrogen atoms found in the state mj=+1/2 from a strong-field region to a weak-field region,followed
by electron collisional ionization. The polarized ion source built by the authors provides a current of ?0.1 ?A. Pro-
ton polarization reaches 50%, deuteron polarization reaches 33%.
A source designed on the same principle was discussed in a paper by R. P. Slabospitskii et al. (Physics and
Technical Institute of the USSR Academy of Sciences).
"Injection system of negative ions for the tandem electrostatic generator PG-5," a paper submitted by A. Ya.
Taranov and Yu. Z. L,evchenko (Physic's and Technical Institute), dealt with the design of a source of negative ions
for this electrostatic generator based on the transformation of positive ions to negative ions through a mercury jet
target.
1076
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
The authors obtained intense beams of negative hydrogen and oxygen ions. They studied the injection con-
ditions for a beam of negative ions shot into the tandem accelerator, the conditions for passage of the beam down
the accelerator ion duct at various voltages across the duct, etc.
The design of standardized NG-200-Sh neutron generators with neutron flux higher than 1010 neutrons/sec was
the subject of a paper by V. D. MikhailOv (NIIgFA). ?
A report by 0. B. Ovchinnikov (NIIgFA) provided information on the building of a 2.5-MeV accelerator with a
balanced multiplication circuit as high-voltage source. The accelerator was designed to produce 25 kW electron or
ion beams. The high-voltage part of ihe accelerator is placed in a compressed-gas tank.
B. I. Ale bertinskii presented a report on the work of a NIIgFA team developing techniques for calculating the
output characteristics of capacitance type voltage-multiplication circuits. The comparison between calculations
and results of measurements made on various models of symmetrical cascade generators, presented by G. M. Osetinskii,
showed that the method proposed is totally satisfactory for taking into account internal resistance effects in the switch-
ing components (transistor components included), internal resistance of the power supplies distributed over protective
stages, stray capacitances distributed over compensating inductance stages. Expressions were derived for calculating
the simulating factors of various voltage circuits.
Upon the conclusion of the conference, the delegates visited the Nuclear Problems Laboratory, the Nuclear
Reactions Laboratory, and the Neutron Physics Laboratory.
1077
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
INTERNATIONAL CONFERENCE ON SECTOR-FOCUSED CYCLOTRONS
AND MESON FACTORIES*
P. Lapostol
CERN, Geneva
Translated nom Atomnaya Energiya, Vol. 15, No. 4,
pp. 343-346, October, 1963
Sector-focused cyclotrons have been stirring up increasing interest among workers in many laboratories through-
out the world during the past few years. In some laboratories, sector-focused cyclotrons are already in operation or
are under construction, and many other laboratories have plans for installing such machines. Scientists in univer-
sities and laboratories (particularly European ones) engaged in work or studies on sector-focused machines have,
therefore, naturally displayed keen interest in any opportunity to exchange their ideas and experiences. At the April
1963 conference sponsored by CERN, 150 scientists from 60 laboratories in Europe (including the Soviet Union) and
America were in attendance; a total of 66 papers were read. Since the preceding Los Angeles conference took place
rather recently, this conference was devoted either to new advances or new topics which did not find place on the
agenda of the preceding conferences covering related matters (e.g., physical experiments which might be carried
out with the aid of sector-focused machines, acceleration of polarized particles, etc.).
Experience in the operation of sector-focused cyclotrons. R. Livingston (Oak Ridge), on opening the session,
presented a review of the sector-focused machines already in operation, which are listed in the accompanying
table. He noted that the difficulties in the way of achieving isochronism have been overcome, the quality of the
beam extracted is not inferior to that of other accelerator types, the duty cycle is 4-5, and negative ions have been
successfully accelerated, with new vistas opened up for physical experimentation. One serious difficulty, though, is
induced radioactivity, but the use of graphite at the low temperatures involved pretty much solves this problem too.
One strong positive feature of sector-focused cyclotrons is their flexibility and reliability; slight energy ad-
justments can be carried out in a few seconds, the energy may be varied substantially or the type of particle ac-
celerated may be completely changed in a matter of hours, and the machines are capable of stable operation for
hours and days on end at the specified operating conditions.
Reports followed on the machines installed at Oak Ridge, Berkely, and elsewhere. The delegates were very
much interested in a description of experimental procedure for optimizing the parameters of the r-f voltage and mag-
netic field in order to attain the optimum isochronism conditions.
In the Karlsruhe cyclotron, the orbits may be run up to the maximum energy (200 turns). Field perturbations
with a harmonic of the order of 0.1% were found to result in betatron oscillations of 9-mm amplitude.
The delegates heard a report on the Ann Arbor (Michigan State University) sector-focused machine which was
just commissioned. The most sophisticated machine of this type discussed was the Philips firm 130-cm cyclotron.
The final assembly of the machine was completed on April 4, 1963, and two days later 400 turns on a radius out to
53 cm (at 14 MeV) were achieved. After some final readjustments, particles of 20 MeV energy were produced on
April 12. The deflector was mounted on April 17, and 30% of the particles orbiting were extracted on the following
day.
Particle extraction is one of the problems where current progress is most spectacular. Both of the methods used?
the now conventional peeler-regenerator method and the resonance method (employing both natural and forced res-
onance) presented strikingly encouraging results. In the electron analog (Oak Ridge machine), 850/0 of the particles
were extracted when the vr = 2 resonance was used. The dependability of this type of extractor is determined not
solely by the exact channel design, but also by the careful and thorough examination of the problems connected with
high voltage.
? The term "meson factories" in this context means 400-800 MeV accelerators with a proton beam intensity 100 times
greater than in present-day synchrocyclotrons.
1078
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
The Birmingham cyclotron uses an electrostatic peeler and regenerator system to achieve an extracted current
of up to 40 ?A at 35-40% efficiency.
Isochronous Cyclotrons Presently Commissioned (as of April 15, 1963)
Location of
machine
Year
commi s-
sioned
Number
of sectors
Pole
diameterergiof
cm
Maximum
internal-
beam en-
orbits, MeV
Energy of other
beams, MeV
Extracted-
beam
energy,MeV
Number
of orbits
Delft
1958 4
85
12(p)
>300
Urbana
1958
4
111
15 (p)
4-15(p)
15(p)
>100
Dubna
1959
6
120
13(d)
>1000
Harwell
1959
3
56
3(p)
Moscow
1959
3
150
32(d)
6 (p), 17, 29(H2), 35 (He3)
32(d), 20(112)
>160
Los Angeles
1960
4
125
50(p)
48(H-)
48(H)
>1000
Birmingham (UK)
1961
3
102
12(d)
11 (D-)
>400
Berkeley (Cal.)
1961
3
224
130(a)
25, 50 (p), 16, 33, 40,
65 (d), 25(He3), 33, 65,
50(p), 16?
38 (d), 33-
>600
75, 80 (a)
75 (a)
>500
Oak Ridge
1962
3
193
90(a)
8, 12, 32(p), 40(d)
80 (a)
Boulder
1962
4
132
24(p)
16, 19 (p), 8(H-), 17(D-),
8(H-), 16,
>200
30 (a)
19 (P)
Davis
1962
3
56
10(p)
>100
Ann Arbor
1962
3
229
50(d)
50(H2)
>210
Karlsruhe
1962
3
211
40(d)
7, 12(p), 15(d)
12(p), 26(d)
>150
Eindhoven
1963
3
142
12(p)
>400
Oak Ridge
(electron analog)
1961
8
79
530keV
430 keV
>2600
The Philips firm has developed a new accessory which they call a regenerator-compressor. The compressor
functions to displace a perturbation caused by the regenerator to greater radii, thereby setting the radial focus at
the channel entrance and maintaining a wide separation of orbits. This device has been successfully used to extract
15% of the particles from a synchrocyclotron.
Physical experiments using sector-focused cyclotrons and meson factories. On opening this session, A.Zucker
(Oak Ridge) made an analysis of the physical problems awaiting investigation on high beam-intensity accelerators in
the 20-100 MeV energy range. He stressed the point that one particularly vital feature of sector-focused
machines is the possibility of varying the energy and varying the type of particles, combined with the high beam
quality and the excellent energy resolution (of the order of 10 keV).
H. Bernadini (Rome, CERN) took note of the value accelerators designed for -500 MeV have for pion physics.
High-intensity proton beams of 800 to 1000 MeV energy are required in some high-precision experiments and studies
on rare events. Still higher energy ranges would be interesting in research on higher-lying resonances and even for
prying open the K-meson shell, but in the 1 to 12 BeV range there is at present no most preferred energy.
The conference proceeded from these introductory lectures to discuss several special topics:
-acceleration of negative hydrogen ions, now apparently within reach, and promising a most intriguing solu-
tion to the extraction problem;
-production and acceleration of polarized particles, which will be a great help in carrying out many novel
experiments.
At the present time, satisfactory results have been reported, and it appears to be entirely within the realm of
possibility to increase the energy of negative and polarized particles accelerated in sector-focused cyclotrons to 100
MeV by an appropriate engineering of the magnetic field and accelerating system.
Shielding and activation problems which crop up in the design of targets and beam catchers are very serious
in the case of high beam-intensity accelerators. These problems are the most serious limitations on meson and pion
factories. Many different materials have been studied as potential beam-stop materials, but aside from carbon and
1079
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
silicon none of them furnish any appreciable decrease in activation. The solution might possibly be found in the
choice of geometry for the parts on which the beam impinges, and in the use of heavy materials to shield against
induced activity.
One of the reports took up the problem of duty factor, particularly with respect to meson factories. The re-
quired low-frequency and high-frequency duty factors may be evaluated in accordance with the requirements of the
experiment, the speed of light, and the time required to carry out the experiment.
Advances in the theory and design of sector-focused machines. Many new and interesting developments came
to the attention of the conference. Among these we may note a quantitative study of the effect of the spiral angle
on the stability region; a program for mapping the magnetic field for an accelerator of up to 800-900 MeV with a
specified energy dependence of vz; a new method for calculating the distribution of magnetic field index with vari-
able permeability of the field taken into account.
A report produced by Michigan University showed that the use of a narrow slit at the center in a preaccelera-
tion process reduced betatron oscillations and narrowed down the duty cycle. The possibility of employing a double-
dee accelerating system operating at various harmonics is under study. More detailed calculations have been per-
formed for various extraction systems. The status of construction and assembly work on various sector-focused cyclo-
trons (at Milano, Orsay, Grenoble, Michigan State University) was reported. An ingenious technique for studying a
cyclotron magnetic field was proposed: direct determination of vz with a "floating wire" ("CSF"). A design of the
magnetic channel and deflector as a coaxial transmission line with a slit where it would be a comparatively easy
matter to shape the field as desired deserves mention here.
A Berkeley team is engaged in the study of problems involving very high deflector voltages: improving the
mechanical rigidity of electrodes (to avoid vibrations in response to electrical forces), choice of material (inconel
or stainless steel, and tungsten for the anode), and the effect of the beam. For a successful design with a generous
safety margin, we may use VE=1500 kV2/mm.
There was a report on a magnetic beam locator devloped at Argonne National Laboratory; the probe is capable
of measuring the position of a 0.09 ?A beam, without introducing distortions, to within ?0.1 mm.
Meson factories. R. Richardson (University of California) made a survey of various types of meson factories.
The comparison was based on such parameters as duty cycle, practicability of the beam desired, beam quality with
respect to precise energy information, possibility of varying the output energy, possibility of producing several beams
simultaneously, induced radioactivity, complexity of design, reliability, and costs. The usual type of sector-focused
-cyclotron was shown to have acceptable parameters in all respects. A cyclotron built to accelerate negative ions
would not be exorbitantly expensive if it were to be doubled in size, and still would feature such advantages as
variable energy, good duty factor (if isochronism losses occur immediately prior to stripping), and the possibility of
producing several beams simultaneously with different energies. A synchrocylotron with spiral-ridge focusing may
yield appreciably greater intensity than a conventional synchrocyclotron because of the higher repetition rate; the
particle extraction efficiency will be enhanced and an added bonus is the possibility of accelerating a variety of par-
ticles. A spiral-sectored ring synchrocyclotron differing slightly in design from its earlier counterpart had similar
beam parameters: intensity to 100 ?A, extraction efficiency of ?30-40%.
A strong-focusing proton synchrotron is much cheaper, but it is impossible to obtain a high intensity with that
machine. A separated-orbit cyclotron may feature most of the advantages pointed out, but the cost and complexity
of a machine of this type seem too high a price at present.
In linear accelerators, the extraction efficiency is 100%, the beam intensity and energy may be regulated with
great ease, and there is no problem in accelerating polarized particles. The disadvantages in this case are the large
duty cycle and, possibly, the high cost. Improved duty factors might be attained in the cryogenic linear accelerator.
Studies on experimental models have shown that r-f losses may be reduced by a factor of 104 when lead and niobium
are used. However, the fabrication of full-scale resonators is still an exceedingly difficult engineering feat, and it
might take several years before engineering plans for a full-scale accelerator of this type become definitive.
The Zlirich group suggested an annular isochronous cyclotron in which the central region would be absent. Par-
ticles are to be injected into the racetrack at 70 MeV from a conventional sector-focused machine, and the terminal
energy of 500 MeV will be limited by the vr =1.5 resonance. The advantage seen in this annular facility is the po-
tential usage of several extraction systems and greater ease in positioning targets, improvements over the presently
1080
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
available counterparts. When particles are transferred from the injector cyclotron to the annular one, crossing of
resonant lines may be avoided and improved focusing may be attained in the annulus by choosing uz close to Unity.
The extraction and injection efficiencies will be less than 100%, of course.
The separated-orbit cyclotron suggested by F. Russell (Oak Ridge) is something of an ingeniously conceived
hybrid between linear and cyclic accelerators. It is a cyclic machine, but each revolution (in a total Of about 100
revolutions) will have its own independent guide field, and this will make it possible te obviate resonance effectS,
just as in a linear accelerator. Acceleration will take place in from 5,000 to 10,000 acceleration intervals formed
by some 50 to 100 resonators distributed in the meridian planes. Phase stability is the same as in linear accelerators,
but the grouping of accelerating gaps in the resonators loosens the r-f field specifications. Enetgy variation at A
given point is impossible, but extraction may be accomplished at 100% efficiency, in theory, from any point On the
orbit. The principal defect in this type of accelerator, very similar in construction to a wasps' nest, istheordinately
high cost and the vast number of engineering problems to be overcome in building suitable magnets, the Vacuum'
system, and the resonators.
The principal limitations imposed on intensity in FM sector-focused cyclotrons were discussed, And it was
shown that frequency-modulated sector-focused machines could produce measurably higher intensity than preSently
existing FM cyclotrons.
Finally, a design of a muon microtron capable of producing high-intensity pure muon beatns Was described.
The conference clearly revealed that the time when accelerators could be built on the basis of rough Cut-
and-try calculations or approximations belongs to the past. At present, computer techniques enable designers to be-
gin with a detailed study of not only linear, but also nonlinear, problems.
The experience accumulated in operating machines now in service demonstrates that all of the theoretical
work carried but has been exceptionally useful. The machines are operating in accord with theoretical predictions,
and are put into operation without mishap, thanks to the accuracy of the engineering calculations, and their per-
formance is dependable, flexible, and versatile. These achievements serve as a stimulus to Machine designers, and
the development of theory leads to a better understanding Of the conventional cyclotrons, synchrocyclotrons, And of
extraction problems concerning the successful operation of all existing cyclic accelerators.
Sector-focused cyclotrons pose a host of difficult and fascinating engineering problems before design engin-
eers in connection with the magnetic field, r-f system, and high-voltage techniques. It is quite possible that these
machines will excite somewhat lesser interest than accelerators designed for extremely high energies;.-bilt They
far more accessible and it is most significant that new advances and new inventions are constantly coming to the
fore despite the fact that cyclotron engineering has a rather long history behind it. One might even Conjecture that
the lack of enthusiasm for acceleration of 11- ions is partially to be accounted for by the relative routineness Of this
problem, and the fact that it falls short of promising a sufficiently broad field of activity to engage the intense inter-
est of theoreticians and engineers.
Independently of what type of accelerator will be accepted for the task of constructing meson factories, they
will all come in handy for a detailed probing into pion and muon physics. It is to be anticipated that 500-800 MeV
cyclotrons yielding excellent beams will be built. The energy range up to 12 BeV, where K-rnesons and antiprotons
come in for intensive study, would obviously be brought within range by machines of other types. .
1081
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
IAEA SYMPOSIUM ON THERMODYNAMICS OF NUCLEAR MATERIALS
V. V. Akhachinkii
Translated from Atomna)a fnergiya, Vol. 15, No. 4,
pp. 346-351, October, 1963
In May, 1962, an international symposium of the thermodynamics of nuclear materials was sponsored by the
International Atomic Energy Agency at Vienna. The proceedings appeared subsequently under the title Thermo-
dynamics of Nuclear Materials, IAEA, Vienna, 1962. Forty-six papers delivered at the symposium may be found
in this publication. In consideration of the importance of the information contained in those papers, we presenthere
a brief account of the topics covered in them.
The classification as to subtopic was not particularly strict, and there will accordingly be some overlap be-
tween the subjects dealt with in different papers mentioned.
General problems of the thermodynamics of the actinides, and applications to theory. E. Westrum and F.
Gronfold (USA) presented an information-packed paper on the thermodynamics of oxides, sulfides, selenides, and
tellurides of the actinide elements. The reference ran to 135 titles. The major portion of their attention was
centered on the thermodynamics and phase relations of the uranium?oxygen system. A method was proposed for
estimating the entropies of chalcogenide compounds and values of the standard entropies of oxides of all the actin-
ides and lanthanides were listed, as well as the entropies of the sulfides, selenides, and tellurides of uranium and
thorium. For the first time, experimental thermodynamical data were presented (see Table 1) referable to uranium
sulfides (at 298?K).
A report by R. Ackerman and R. Thom (USA) used a comparison of the properties of gaseous monoxides and
dioxides of the actinide elements to the properties of the counterpart compounds of other elements to explain the
duality of the chemical nature of the actinides. The author's view is that this method for shedding light on the na-
ture of the transactinide elements is better than the method used by Cunningham and Haissinsky, who considered
ions in aqueous solutions and in solids.
B. Cunningham (USA) reported a wealth of new information on americium and curium: types and parameters
of crystal lattices, thermal expansion coefficients, magnetic susceptibilities. The melting point of americium was
reported to be 995 ? 7?C, that of curium 1340 ? 40?C.
M. Rand (Great Britain) cited some thermodynamical data for uranium compounds where conflicting reports
exist, and suggested several thermodynamics problems for solution.
A report by I. Prigogine and R. Balescu (Belgium) was devoted to the thermodynamics of nonequilibrium states.
G. Reiss (USA) outlined the basic principles of the statistical thermodynamics of fused salts. Some of the char-
acteristics of fused halides of the alkali metals were computed (e.g., heat of mixing, surface tension, compressibility).
S. Takeuchi and X. Suzuki (Japan) reported a statistical-thermodynamical calculation of the pressure of hy-
drogen in equilibrium with the PuH2 phase containing a region of homogeneity. The relationship between the num-
ber of hydrogen atoms occupying octahedral and tetra-
TABLE 1. Experimental Thermodynamical Data for hedral vacancies in the plutonium was also computed
as a function of composition and temperature.
Uranium Sulfides at 298?K
Compound
in
C,/mole
cal/mole ' deg
S?, entropy
units
LIF?,
kcal/mole
US
US2
U2Ss
12.08
17.84
22.85
18.63
26. 42
33.08
?87
_120
?127
1082
A.Searcy and D. Meschi (USA) computed the
integrated and the partial thermodynamical functions
for the U?H and Zr?H systems from data on dissocia-
tion pressure.
A paper submitted by 0. Kubashevsky (Britain)
contained material on phase diagrams based on thermo-
eTh
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 2. Thermodynamical Characteristics of Inter-
metallic Compounds of Uranium
Compound
11?, kcal/mole
UrZit12 ?54. 2
I.A.:(111 ?27.2
l'Ga3 ?41.4
1.J1113 ?20.3
0'113 --13. 2
US'n3 ?40.8
UPL3 ?20.9
dynamical data, as well as a discussion of the solution
of the converse problem. Concrete examples were cited
of the construction of phase diagrams and prediction
AS?, entropy of data for binary systems of interest in nuclear power
?units applications (Zr?Hf, U?Zr, Bi?Cd, Bi?Zn, U?W,
U?Fe). The author's feeling is that an exact phase dia-
. 4 gram might be plotted in some cases exclusively on the
?14.5 . basis of thermodynamical data.
?13 0
?11.7 E. Rudi (Austria) devoted his report to the thermo-
dynamics of refractory uranium and thorium compounds.
Cross sections of ternary phase diagrams of uranium and
thorium with carbon and Zr, Hf, Nb, Ta, Mo, W, and
and other refractory materials with boron, carbon, and nitrogen were
also ternary diagrams of uranium, thorium,
produced.
Experimental procedure and techniques. G. Skinner (Britain) reported on the most recent improvements in
methods for determining the heat of formation, the most important of which were, in his view, the rotating calori-
metric bomb, combustion in a calorimetric bomb in a fluorine atmosphere, calorimetry of high-temperature reac-
tions, and calorimetry for research on very slow reactions (Tian-Calvet calorimeter).
H. Feder et al. (USA) reported on the application of an oxygen and a fluorine calorimetric bomb, a glassbomb
for observing the nature of combustion, a bomb for pyrophoric substances, and several other devices. Experimental
procedure and technique was also touched on in most of the other papers.
Alloys. G. Smith (USA) studied the thermodynamics of the formation of binary magnesium compounds with
calcium, copper, nickel, and yttrium by measuring vapor pressure by the Knudsen method. Vapor pressure values
were reported for magnesium (626-818?K). calcium (844-965?K), and also above certain two-phase systems, as for
example, Ca+ Mg2Ca, I+ MgI, etc.
G. B. Fedorov and E. A. Smirnov (USSR) used the Knudsen method to measure the vapor pressure of pure zircon-
ium and the partial pressure of zirconium above its alloys with tin.
On the basis of the data obtained, the thermodynamical characteristics of 6 -zirconium were plotted, as well
as thermodynamical activity and changes in partial thermodynamical functions of zirconium and its alloys with tin.
V. V. Akhachinskii, L. M. Kopytin, M. I. Ivanov, and N. S. Podaskaya (USSR) determined the heats of forma-
tion of intermetallic compounds of plutonium with aluminum and iron, and of uranium with iron,from the heats of
solution of these compounds and of their constituents, and obtained the following values:
Compound ATP, 298 kcal/mole
PuAl2 34.0 + 0.8
PuAl3 43. 2 + 0..8
PuAl.,. 43.2 + 0.8
PuFe2 6.5?0.4
UFe2 7.7?0.3
In addition, the heats of formation of the compounds PuAl, Pu3A1, Pu6Fe, and U6Fe were estimated at, res-
pectively: ?17; ?17; ?3.3; and ?3.9 kcal/mole, with an error not exceeding +30%. I. Johnson and H. Feder (USA)
used the electromotive force method to study the thermodynamical properties of binary systems of uranium with Zu,
Cd, Ga, In, Ti, Sn, and Pb. Equations for the free energy, heat and entropy of formation of seven compounds were
reported over the range from 300 to 950?C. Some of the data referable to the temperature 430?C are reproduced in
Table 2.
The optical absorption method was used by P. Rice, G. Balzhiser, and D. Ragone (USA) to determine the thermo-
dynamical activity of bismuth in the uranium?bismuth system over the 1018-1115?K temperature range. The authors
calculated the free energy of formation of UBi, U3Bi4, and UBi2 from liquid bismuth and y-uranium, and obtained
the following equations:
for
for
for
UBi At" =
u31314AF? =
U13i2 AF? =
? 12
?12
?11
320+4.40 T + 370 cal/ g -atom ,
980-1-5.10 T ? 360 cal/ g-atom,
440? 4.90 7' ? 280 cal/ g-atom.
1083
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 3. Basic Thermodynamical Characteristics of Thorium, Uranium, Plutonium, and Their Oxides
Substance
cal/mole"7T
, kcal/mole
subl
u.
A'9subl' e'
Temp. range,
?K
Th(g)
131700-27.47'
131.7 ?2.8
27.4 +1.5
1757-1956
Th (g)
? 10300-14.4T
173..5 12.2*
38.4 ?1.0*
2200-3000
Th02(g)
?137300+11.17'
158.7 +2.5
35.3 +1.0
2200-3000
Th02 (s)
?296000+46.4.T
- ?
?
2000-3000
U(g)
106760-26.09T
106.76+0.01
20.09+0.07
1630-1970
U0(0
UO2 (g)
(-16800-10.0T)
?121.522+ 4..24T
(151,5)*
137.1 +1.7
? (33,4)*
36.4 ?0.9
1900-2500
1600-2100
C303 (g)
UO2 (g)
?198500+19.07'
=258650+40.64T
92.0 ?2.0 f
- ?
41.0 ?2.0 f
?
1230-1700
300-1500
Pu (g)
80500-22.947'
80.50+0.04
22.91+0,6
1392=1793
PHO (g)
? 20600-18.4T
- (146)*
(37)*
1700-2000
pu02(0
? (-122000+ 5.0T)
(1.31)
(35)
1800
Pu203( s)
(-393000+63.0T)
?
? ?
_
PuO2ls)
?251600+40.25T
10000-1500
*Corresponds to removal of one mole Me0 (g) from Me02 (s).
1-Corresponds to the hypothetical process UO3 (s) UO3(g).
_
The activity coefficient of uranium in a dilute solution with bismuth is log y?= 2.670-5625/T (?K).
The free energy of formation of uranium carbide, ?22,000 f 1800 cal at 1075?K, and ?19,500 cal at 1275?K
per gram-atom of U, was found by determining the concentration of uranium in liquid bismuth existing in equilibrium
with uranium carbide UCx.
D. Wiswall and J. Egan (USA) feel that bismuth has potentialities in reactor engineering. They investigated all
the papers published on the thermochemistry of liquid alloys of bismuth with Th, Pa, U, Pu, and fission products, and
compared these with their own data.
A. Thorley and K. Teajack (Britain) studied the embrittlement of niobium attacked by the hydrogen-containing
alloy Na?K.
Volatilization processes. Processes involving volatilization of refractories play a great role in high-tempera-
ture reactors. A discussion of the mechanism underlying volatilization processes shared attention in a paper sub-
mitted by P. Gilles (USA) with the techniques of vapor pressure measurement.
D. White, P. Walsh, and L. Ames (USA) presented a review of the thermodynamics of the volatilization of ox-
ides of the rare earths and of yttrium over the 1900-2700?K range. It was found that, aside from a rare exception,
stable vapor in equilibrium with oxides consists of gaseous Me0, Me, and monatomic oxygen.
K. Gingerlich and J. Efimenko (USA) carried out a thermodynamical study of thorium phosphides by evaporating
them and measuring the activity of the ions in the gaseous phase by means of a mass spectrometer.
E. Keiter, E. Rauh, and R. Thorn (USA) used the effusion technique and mass spectroscopy to find the thermo-
dynamical characteristics of uranium sulfide and uranium oxysulfide.
A. N. Nesmeyanov, Yu. A. Priselkov, and V. V. Karelin (USSR) measured by the Knudsen method the pressure
of saturated vapor Of 99.5% pure yttrium metal and found that
1578,03
log P (n o un, H .-_-7.813u? (1361-1761? K).
Volatilization and thermodynamics of oxides. N. Voronov, A. Danilin, and I. Kovalev (USSR) determined the
rate of evaporation of uranium dioxide in a vacuum over the 1450-2300*C range. The oxide was heated by passing
current directly through the specimen under study. The finding was that
1084
30 709
log P_ uoa (mm Hg) = ---,----+ 10.915.
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 4. Vapor Pressure of UO2 and UO3
Puo3 (g), mm Hg
-
r*, K
PU02 (g),
at
at
mm Hg
P02=to-o atmo
Po2=I 0-8 atmo
1750
5.1.10-7
1.60.10-3
1.60i0
2000
6. 9 ? 10-5
1.39.10-2
1.39.10-3
2250
3.0.10-2
7.70?10-2
7. 70. 10-3
2500
1.4.10-2
0.309
3.09.10-2
and of uranium:
and of plutonium:
log P (atmos
The rate of evaporation of Zr02 and Th02 in
air was also determined over the 1500-2000?C range.
At 1900?C, the rates of evaporation of these two com-
pounds was the same, viz., -7'10-8 g/crn2. sec.
R. Ackerman and R. Thorn (USA) devoted their
report to a discussion of their own data and data pub-
lished by others on the volatilization of thorium, uran-
ium, plutonium, and their oxides. The basic thermo-
dynamic characteristics appear in Table 3.
They also derived equations for the vapor pres-
sure of thorium:
=(5.091 + 0.333) (28 780 + ( 20)
(1757? 1956 K).
1'
(23 330 21)
log P (winos) = ().701 * . ? (1600 -- 2000' K),
log P *rims
and of thorium dioxide:
and of plutonium dioxide (in vacuo):
and of plutonium dioxide (in oxygen):
k 17 587 1- 7. ,
(5.014 0.041)? - - (1.100 ? 1800' K),
800
log P(atrilos) 7.98-
27910
Jog I(atmos)=8.l29--; T ,
20 500
log P (atmos)=8,61--_ (1500 - 1700' C),
and finally,of plutonium oxide PuOx (1 < x< 2):
log P(atmos 8.072 29 7,240 (2000-2400? K).
E. Cordfunke (Netherlands) gave a brief description of the principal techniques used to determine the char-
acteristics of a volatilization process, and discussed the available data on the volatility of oxides of several metals
important in nuclear technology, placing special attention on uranium and plutonium oxides. Table 4 cites some
data on vapor pressures of UO2 calculated from the equation
33115
log Pu02 (mm Hg) T 4.028 log T +25.686,
reported by Ackerman et al., from experimentally obtained data, and the vapor pressure of UO3,calculated by the
author on the basis of known thermodynamical data.
T. Markin, L. Roberts, and A. Walter (Britain) used the emf method to study the thermodynamics of uranium
oxides of the compositions from UO2 to UO2,6 over the 500-1060?C range. The results were discussed with a view
to the available published data and the results of investigations carried out by the authors using the tensimetric
method over the 1000-1450?C range. Phase relationships were also surveyed in the uranium-oxygen system and a
portion of the phase diagram for compositions from UO2.00 to UO2.25 was reproduced for the 300-1400?C range.
1085
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 5. Thermodynamical Characteristics of Yttrium and Zirconium Hydrides and Deuterides at 298?K
Compound
CP, cal/mole ? deg
So, entropy units
(Ho?HZ) cal/mole
FO I{
( 0) cal/mole ? deg
T
ZrH2
ZrD2
YH2
YD2
7.396+0,015
9.631+0.019
8.243+0.016
10.773+0.022
8.374+0,02
9.168+0.02
9.175?0.018
10.294+0.021
1284.1+2
1474.4+3
1402.7+2.8
1659.1+3,3
4.067+0,01
4.223+0.01
4.470+0.009
4.729+0.010
E. Aukrust, T. Forland, and K. Hagemark (Norway) measured the equilibrium pressure of oxygen above non-
stoichiometric uranium dioxide UO2+ x at 1100?, 1200?, 1300?, and 1400?C in the range of compositions from UO2
to U308. It was shown that the nonstoichiometric phase of UO2.. x exists up to the ratio 0/U=2.245 at 1300?C and
0/U= 2.255 at 1400?C. A model was suggested for the defect structure.
T. Mukaibo et al. (Japan) determined the heat of formation of U301?an intermediate metastable compound
formed in the oxidation of UO2 to U308 in air. They used two independent methods: differential thermal analysis
and measurement of specific heat. Two values were obtained for AH?288U307,-815.7 ? 2.4 kcal/mole, and ?821.1
2.1 kcal/mole. Results were also reported for the measurement of the specific heat of U307 over the 100-400?C
range.
A paper by C. Comareck and M. Silver (USA) presented some experimental data on the determination of ther-
modynamical characteristics (partial free energies, enthalpy, and entropy) of oxygen dissolved in titanium, zircon-
ium, hafnium in amounts upto 30 at.% and over the 800-1000?C temperature range.
Volatilization and thermodynamics of carbides. E. Huber and C. Holley (USA) systematized existing data on
the thermodynamics of the carbides of the actinide elements, and brought forth new data on the heats of formation
of ThC, U2C3, UC1.88, PuC8.77, and Pu2C3, obtained by combustion calorimetry, and found to be ?7 ? 6; ? 49 ? 4;
?18 ? 4; 3.7 + 3.1; and ?1.7 kcal/mole, respectively.
R. Mulford, G. Ford, and J. Hoffman (USA) employed the Knudsen method to measure the vapor pressure above
PuC2 in equilibrium with graphite over the 2000-2400?K temperature range. The pressure of plutonium above PuC2
is found from the equation
17 920 (? 250)
log P(atmos + 2.779 (? 0.11).
The heat of evaporation of Pu from PuC2 is 95,100 cal/mole. The heat of formation of PuC2 (H?), entertaining
various pertinent assumptions, is found to range from ?7 to ?8 kcal/mole. It was shown that probably all plutonium
carbides volatilize with some plutonium loss and that there does not exist a solid compound volatilizing congruently.
D. Jackson et al. (USA) applied mass- spectrometric techniques to an investigation of the process and thermo-
dynamics of volatilization of gadolinium and thorium dicarbides. It was found that gadolinium is predominantly
present in the gaseous phase above the solid GdC2. The amount of gaseous GdC2 at 2000?K is 1% and at 2422?K it
amounts to 5.8% of the amount of Gd present. Above solid ThC2, gaseous Th and ThC2 are found in commensurate
quantities, and their pressure is expressed by the equations
for
for
ThC2 log P
Th log P
(atmos)
(atmos)
39
364 (?
163)
(+
(?
0.65)
0.57)
(2400-2600? K),
(2400-2600? K).
36
025 (+
+7.20
144)+5.74
7'
The enthalpy of sublimation of ThC2(solid) from ThC2 to Th (gas) comes to 213 and 185 kcal/mole, respec-
tively. The calculated heat of formation of ThC2(al?288) is ?48.6 ? 2.5 kcal/mole.
H. Eick, E. Rauh, and R. Thorn (USA) measured the vapor pressure of uranium above uranium carbide of com-
position UC1,78 f 0.05 by the effusion method over the 2060-2820?K temperature range. The amount of U235- and U23-
containing uranium volatilized in the process was determined from the a-activity. A mass-spectral analysis revealed
that the effusate contained gaseous uranium, monatomic and triatomic carbon, and UC2. The ratio of LP- to UC ii- was
4 at 2800?K. The vapor pressure of uranium overlying UCI,88 is given by the formula
1086
Declassified and Approved For Release 2013/02/25 : CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
TABLE 6. Thermodynamical Data on Borides
Compound
C (298?K),
P'
cal/mole ? deg
S?, 298?, e.u.
BN (cub)
CrB
MoB
TaB
WB
Mo2B
W B
Cri32
HfB2
MoB2
NbB2
TaB2
TiB2
ZrB2
W2B5
9.95
8.57
9.49
11.80
8.01
.18.70
15.36
.12.80
14.23
14.45
11.81
13.98
13.62
13.12 -
21. oi)
8.4+1
10.51
13.1+1
13.2+1
22.8+2
28.2+2
6.6+1
11.2+1
8.7+1
8.0+1
11.3+1
6. 2?1
8.5*
21+2
*E. Westrum found the empirical value 8.58.
34 568
log P(atmos ? 1 7.01 (2060-2460? K),
7'
33 593
log P(atmos ? 4 7.0 (2540-2820' K).
7'
The calculated free energy of formation of UC1.80 was
?51,400+ 6.02 T cal/mole (at 2060-2460?K).
S. Alcock and P. Greaveson (Britain) used three
techniques, all variants of the Knudsen method, to
measure the equilibrium vapor pressure above solid
systems U?C and U?B, determined uranium activity
in these systems, and calculated their thermodynamical
characteristics:
for
for
for
for
for
UC AF?
--25200 1- 3.6 T
UC2 AF?
= ?32600+3.6T
U132 AF`'
= ?39 300+3,0 7'
U B4 AF?
=-- ?60 400+4.4 7'
U1312AF?
= ?106 000+10.5
kcal/ mole(1450 ? 1550? C).
kcal/ mole (1700 ? 1800? (),
kcal/ mole (!450 1550? C),
kcal/ mole(1730-1850? C).
T kcal/ mole (1720 .1850?.C).
The free energies were calculated for the formation of compounds of liquid uranium and solid boron and carbon.
Diagrams of the integrated free energy of formation vs. composition were plotted for the systems U ?C and U?B
at 1450?C. The equation for the pressure of dissociation of uranium above UC2 was derived as
31 170
log P(atmos)=6.81? (1700-18(10? C).
7'
H. Lonsdale and J. Graves (USA) reported on the results of vapor pressure measurements of the dicarbides of
uranium, thorium, and protactinium by the Knudsen method. Protactinium carbide was isolated as a very dilute
solid solution in thorium dicarbide by bombarding the latter with neutrons. The vapor pressure of uranium and
thorium above their dicarbides in equilibrium with graphite was found to satisfy the equations
log Pu(atmos)
28 400 (+ 1100)
4.76 (? 0.47) (2000-29000 K),
7' m
log P.r,\.,atmos)
37 600 (? 1000)_1._7.39 (? 0.39) (2300-2900? K).
'1'
The vapor pressure of protactinium above dilute solid solutions of PaC2 and ThC2 may be expressed by the
formula
39 200 (+ 1900)
log P(atmos)=
+6.99 (? 0.74)? log Xpa (2300-2900? K),
where xpa is the molar fraction of protactinium.
In the temperature region studied, the computed heats of formation of UC2 and ThC2 were ?25 and ?46
kcal/mole, respectively.
W. Deiss, H. Michaud, and G. Pelissier (France) attempted to isolate uranium, UC, and UC2 of maximum pur-
ity by in-vacuum volatilization with electron-bombardment heating of the material. It was found that the con-
densate arrived at is oxidized when pure uranium is volatilized, while volatilization of carbidized uranium yields
an oxide-free condensate. The author demonstrated by means of thermodynamical calculations that the formation
of carbon monoxide is responsible for the partial pressure of oxygen becoming lowered to such an extent that liquid
1087
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
and gaseous uranium no longer react with the oxygen, and the probability of any reaction involving the condensate
is very slight. UC and UC2 films are obtained in the process. The authors hold the view that these carbides are stable
in the vapor phase.
V. E. Ivanov, A. A. Kruglykh, V. S. Pavlov, G. P. Kovtun, and V. M. Amonenko (USSR) determined the vapor
pressure of UC in the 1675-1860?C range, that of UO2 over the 1650-1930?C range, and that of USns over the 1025-
1295?C range from the rate of evaporation from an open crucible. The following equations were derived for the
vapor pressure:
for UC log P (mm Hg) =21.306 49 200
T '
for UO2 log P (mm Hg) =12.098_32 150
?p?,
for USns log P (mm Hg) =9.067 17 223
T
T. Mukaibo et al. (Japan) measured the specific heats of UC and UC2 in an adiabatic calorimeter over the
100-400?C range:
Cp (UC) =5.01+ 2.63.10-2 T-1,92.10-5 T2 cal/ mole,
Cp (UC2) =2.93+ 4.33.10-2 T-3.17.10-5 T2 cal/ mole,
The probable error was estimated at 3.0% by the authors.
Other thermodynamical data. I. Skidmore and E. Morris (Britain) determined experimentally the equation of
state for uranium under a pressure of several kilobars and the specific internal energy at several kilojoules per gram.
A knowledge of the properties of uranium under these conditions is required to calculate reactor safety margin. The
required states were arrived at by compressing and heating uranium by a shock wave with subsequent adiabatic ex-
pansion.
J. Egan, W. McCoy, and J. Bracker (USA) employed the emf method to determine the standard free energies
of formation of several chlorides of Mg, Ce, U, and Th over the 400-600?C temperature range. Here are some of
the results they reported:
Compound AF? kcal/g ? atom at (400? C)
MgC12 ?127.80
CeCl3 ?211.26
ThC14 ?232.4
UC13 ?168.2
J. Berkowitz (USA) used the nitrogen-graphite reaction in the 2200-2500?K range. The gas effused from a
Knudsen cell was ionized by an electron beam, and the positive ions were analyzed in a mass spectrometer. Ng-,
CN+, Cit, and CiF ions were found to predominate. The author reported the thermodynamical characteristics of the
reaction
C (g) +1/2 N2 (g) CN (g).
R. Gross, S. Hayman, and H. Clayton (Britain) determined the heats of formation of UN, U3Si2,USi, USi2 and USis
by synthesizing them directly from their constituent elements in a calorimeter. The heats of formation of USi, USi2,
and USis were also determined from the difference in the heats of reaction of these silicides and of their constituent
elements and tellurium. The heat of formation of U2N3 was determined by measuring the heat of the reaction in-
volving UN and nitrogen. All of the synthesis reactions were carried out at a temperature of the order of 1000?C. The
results were reported as
Compound ATP, kcal/g ? atom
USis
7.9 ? 0.03
7.7? 0.2
USi2
10.4 ? 0.1
10.2 ? 0.3
USi
9.6 ? 0.2
10.4 ? 0.4
U2Si3
8.1 + 0.1
UN
39.8 ? 0.2
U N
2 3
33.7 + 0.2
1088
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
The second set of figures was obtained by measuring the heat of the reaction between the suicides and tellurium.
H. Flotow and D. Osborn (USA) measured the specific heats of ZrH2, ZrD2, YH2, and YD2 in an adiabatic calori-
meter over the temperature range 5-350?K, and, on the basis of their results, they compiled a table of several func-
Fr ?fro
tions: S?, He?H1 T
, and Some of the data referable to the temperature 298?K are reproduced in
Table 5. Other thermodynamical data are reported including the heats of formation of ZrH2 and ZrD2, which are
?39.3t 0.3 and-40.5t 0.3 kcal/mole, respectively.
E. Mesaki et al. (USA) studied by the mixing method the enthalpy HT2?HT1 (T1= 298?K, T2 = 400 to 1200?K)
of fifteen high-melting borides, computed their specific heats, and estimated the standard entropies. A separate list
of data is found in Table 6.
In conclusion, we should like to point out that, in line with the intensified interest in uranium carbide and
plutonium carbide, IAEA called a special conference to meet in Vienna in October, 1962 to give experts on the ther-
modynamics of those carbides an opportunity to discuss their specific field. The conference carried out important
work in evaluating and coordinating the available data on the carbides, and passed in recommendations on the most
reliable values reported in the literature. A report of the conference will be published along with some new data, "
particularly the data reported by E. Westrum on the specific heat and entropy of UC and UC2.
1089
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
THE USE OF y-RAY SOURCES IN NONDESTRUCTIVE TESTING
AT THE CSEPEL METALLURGICAL COMBINE (HUNGARY)
E. Fenyvesy, K. Scserbak, and K. Vara
Translated from Atomnaya fnergiya, Vol. 15, No. 4,
pp. 351-353, October, 1963
Research work on applications of y -ray sources in flaw detection was begun in Hungary in 1953. A radioiso-
topes laboratory was set up in 1955 at the Csepel metallurgical combine in the central materials testing division.
At the present time, y-ray sources are in systematic use in Hungary in y-radiographic monitoring of weldments and
castings. This work is mainly concentrated at the Csepel metallurgical combine, plants for maintenance work on
electric power station equipment, the Lenin metallurgical combine, and the April 4 machine tool factory. Every
year, about 40,000-42,000 y -radiographic plates are taken throughout the country. Coe?. Cs127, 1r122 are the most
commonly used y -ray sources, and are obtained mostly from Great Britain and the USSR. The training of engineers
and technicians specializing in y -radiographic monitoring work is under the supervision of the Educational Section
of the Ministry of Metallurgy and Machinery. Only trained personnel are authorized to perform radiographic work
in the plants.
Fig. 1. Radiomonitoring of large parts.
Fig. 2. Apparatus for routine radiography of small castings.
About one-half of all the radiographic work is carried out by the radioisotopes laboratory at the Csepel metal-
lurgical combine. Castings are flaw-monitored in a special room of 100 m2 floor area, which has two entrances for
admitting parts to be radiographed and a special tunnel for servicing personnel. The doors leading to the monitoring
room are interlocked to ensure the automatic withdrawal of the y-emitting sources into a storage well should any
of the doors be accidently opened during the radiographic work. Large castings are moved about with the aid of an
overhead crane. A well 10 meters depp and consisting of three steel tubes nested into one another and filled with
concrete is situated in the middle of the asphalt-covered floor. Three different y-ray sources (60-curie Co62, 26-
curie Co127, and 150-curie Ir122) are positioned in that well.
1090
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Fig. 3. Portable container weighing ?1.0 kg.
Large castings to be monitored are positioned around
the well and one of the three y-ray sources is used, the
choice being based on the thickness of the specimen (Fig.
1). The radiation sources are moved into the work position
by special battery-powered devices. Positioning of the
sources is by remote control from a panel mounted in a sep-
arate room shielded by 50 cm thick heavy concrete. The
height to which the source is raised is monitored by a peri-
scope. Photographic laboratory rooms for developing film
and charging plate holders are situated around the control
room. The x -radiographic films used most often of the
y-plates are of the brands Agfa, Gevert, Kodak, and
Ferramia, as well as 0.15 and 0.45 mm thick intensifying
lead foil. DIN-54110 standards are used in interpreting the
plates obtained. Depending on film quality, the thickness
of the material, and the isotope used, the sensitivity in flaw
detection varies from 0.8 to 2.0% of the thickness of the
part examined. Small castings (for example, parts of ma-
chine tools and sewing machines) are monitored with a spe-
cial facility consisting of a spherical lead container and a
y-ray source mounted on a tubular framework 2 m high.
25000 14249 The container has a collimator shaping the beam in such a
way that the semidiameter of the radiation field will be
m. A hand cart presenting an area of 1.2 m2, on which
the parts to be monitored and film holders are wheeled into
position) is placed underneath the tubular framework, i.e.,
in the exposure field. During the exposure, a second hand
cart is prepared, and replaces the first after the first exposure
is completed. This method of monitoring makes it possible
4040 to check out a large number of small castings (Fig. 2). The
,2550 ,27754120
point of this work is not only to detect existing flaws in the
casting, but also to develop, in collaboration with casting
technologists, a casting technology which will minimize
the amount of scrap produced in routine casting work. The
correctness of the method may be evaluated in terms of the
eventual savings.
Approximately 75910 of the total volume of y-radiography work consists of monitoring weldments, most of which
were fabricated not in the laboratory but in plants throughout the combine or in plants outside the Csepel combine.
To meet this need, we designed and built special containers consisting of metallic spheres filled with lead and
mounted on rubber-wheeled carts. A special opening in the center of the conveyance .accommodates, in an exact fit,
a matched tube with a capsule-sealed y-ray source attached to it. When the plates are being prepared, an aluminum
tubular rod ?2 m long is attached to the tube and is used to remove the y -radiation source from its holder. For moni-
toring weldments for high-elevation construction cranes, it is a good practice to use a spherical container weighing
-40 kg, moved about by hand and containing an Ir122 source of 32-curie activity (Fig. 3).
Welded seams of air pressure tanks, cranes, crane rail tracks, railroad cars for transporting butane gas, and other
metal structures are monitored systematically in the laboratory. The most useful and interestingof theworkiprojects
carried out in the laboratory has been the investigation of illuminating stanchions for the People's Stadium built in
19b3, and quality control of weldments for a section of the Druzhba oil pipeline and on the bridge of an intake struc-
ture. Monitoring the state and quality of cranes of outmoded design is a routine job at the Csepel metallurgical works.
In several instances in the history of the laboratory, old reinforced-concrete structures were monitored, and
this has enabled technicians to successfully determine the spatial arrangement of the iron framework inside the con-
crete, and thus to check its dimensions against the originalblueprints. Useful work was also done in reconditioning
?..) 20000
15000
10000
?000
17139
8393
1955 1956 1957 1958 1.959 1,950 (961 1962
Years
Fig. 4. Number of y -radiography plates taken by
the radioisotope laboratory, year by year.
1091
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
the old Budapest fortress. In answer to the request of a building plant contracted for this work, brick walls ranging
from 60 to 120 cm in thicluiess were radiographed in order to determine the location and nature of voids in the brick-
work, and the effect these might have on the load-carrying capacity of the walls. The y-plates taken allowed for a
successful determination and pinpointing of several ventilation holes, and this was an immense aid to the building
workers. The number of radiography shots taken in the laboratory's history may be seen in Fig. 4. The largest num-
ber is registered for 1960, after which a significant decline may be noted. The reason for this is the fact that an
unusually large amount of casting was done at the Csepel works in 1960, and studies were carried out there to deter-
mine the location and frequency of appearance of defects, and in order to incorporate into production technology
those changes which might eliminate flawed castings.
The use of y -emitter isotopes in Hungary has advanced far past the initial difficulties encountered, and the
technical and cost results have been eminently satisfactory. The use of y -emitting sources has vastly expanded the
arena for monitoring materials. Hungarian specialists reached the conclusion that x-ray facilities and y -emitter
sources, as well as accelerators, are necessary tools in monitoring the quality of commodities and parts produced in
today's technology.
1092
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
BIBLIOGRAPHY
NEW LITERATURE
Translated from Atomnaya fnergiya, V.ol. 15, No. 4,
pp. 354-358, October, 1963
State Atom Press (Gosatomizdat) Releases
V. F. Turchin. Medlennye neitrony [Slow neutrons]. 1963, 372 pages. 1 ruble, 38 kopeks.
This book takes up interactions between slow neutrons and matter. The first portion deals with the theory
of slow neutron scattering on crystals, in gases and liquids, and the theory of magnetic scattering of neutrons, and
presents some experiments in scattering research. Sources for producing slow neutrons and means of detecting them
are described. Neutron scattering on a single isolated nucleus and on a system of chemically bound atoms are con-
trasted; the principles of slow-neutron spectrometry are outlined;over-all aspects of the theory of slow-neutron scat-
tering in matter are handled in the spirit of the Van Hove, Placzek, and Wick treatment.
The second portion of the book is devoted to the thermalization and diffusion of neutrons. Here we find
questions relating to the spectrum and spatial distribution of slow neutrons in various media.
The appendices list relations between various neutron characteristics, amplitudes and cross sections for scat-
tering on bound atoms, the parameters KAv, CAN, for the Debye crystal, diffusion characteristics of various sub-
stances as measured by pulsed techniques.
The bibliography includes 158 pertinent titles.
Voprosy teorii fiziki plazmy [Advances in the theory of plasma physics]. Edited by M. A. Leontovich. No.1,
1963, 288 pages. 1 ruble.
This item is the first to appear in a series of symposia devoted to various aspects of plasma theory. This first
contribution takes up some over-all problemsin the description of a plasma. An article by D. V. Sivukhin outlines
the drift theory of motion of a charged particle in electromagnetic fields; a paper by B. A. Trubnikov investigates
the simplest kinetic effects brought about by interparticle collisions in a fully ionized homogeneous gas; an article-
by S. I. Braginskii addresses itself to transport phenomena in a simple and in a multicomponent plasma; an article
by A. A. Vedenov discusses plasma statistical thermodynamics as a system of particles undergoing Coulomb inter-
action.
Teoriya yadernyldi reaktorov [Nuclear reactor theory]. Translated from the English, symposium edited by
G. Birkhoff and E. Wigner. 1963, 364 pages. 1 ruble, 78 kopeks.
This book, first published by the American Mathematical Society, is the eleventh volume on the proceedings
of a symposium on applied mathematics, and deals mostly with mathematical problems encountered in the theory
of nuclear reactors. Nineteen papers appear in this volume, and cover the topics: neutron thermalization, resonince ab -
sorption, passage of radiation through biological shielding, various aspects of kinetic reactor theory, the concepts of
positivity and criticality, diffusion theory, and diffusion models.
M. L. Gol'din. Avtomaticheskii kontra urovnya gamma-luchami [Automatic gamma-ray level monitoring].
1963, 68 pages. 19 kopeks.
This brochure deals with radiation detectors used in a gamma relay switch; a concise exposition of techniques
for designing gamma switch shielding with two types of emitters appears; a procedure is cited for designing gamma-
emitters and the design of radiation source units is described; examples of technical problems on monitoring and con-
trol of levels of free-flowing and liquid media are given; the reader may also find recommendations on the storage,
assembly, and servicing of gamma-relay level switches.
1093
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Releases by Other Publishers
R. V. Dzhagatspanyan, R. F. Romm, and L. K. Tatochenko. Primenenieradioaktivnykhizotopov dlya kon-
trolya khimicheskikhprotsessov[Radioisotopes in chemical process monitoring]. Moscow, Goskhimizdat (State Chem-
ical Press), 1963, 344 pages. 1 ruble, 25 kopeks.
This book outlines the basic theory underlying radioisotope sensors and gives some standard layouts of in-
dustrial instruments in that line; the over-all concept of the origin and properties of nuclear radiations is presented;
methods for recording nuclear radiations are described and a discussion appears of the operating principles and char-
acteristics of gas-filled, crystal, and scintillation detectors. A special section is devoted to the application of in-
dustrial instruments using radioisotope sensors and to the major problems confronted in safe handling of such instru-
ments; here we find a discussion of automatic process control procedures and level control, density and concentra-
tion monitoring and control, automatic production of chlorine and chlorine-derived products, and analysis of the
composition of liquid and gases, and some of the rules and regulations mandatory in any work with sources of ion-
izing radiation.
Literature references are appended to each chapter; the book has a subject index.
M. F. Yudin. Metody i apparatura dlya graduirovki dozimetricheskikh priborov [Techniques and equipment
for calibrating dosimetric instrumentation]. Moscow, Standartgiz (Standards Press), 1962, 120 pages. 38 kopeks.
This brochure deals with uniformization of measurements of x-ray and gamma-ray dosage and contains some
useful recommendations on the use of various techniques and equipment for calibrating and testing roentgen meters
and gamma-emitters. Information presented in a form accessible to a wide readership may be found here on the
basic processes involved in the interaction of electromagnetic radiation with matter. The conditions required for
uniformity in measurements in the field of dosimetry of ionizing radiations are explained. Techniques and equip-
ment for transmitting the measured roentgen values from standardizing instruments to regularly used devices are
described.
The appendices provide tables of linear attenuation coefficients and the albedos of gamma-radiation energy
in various media (e.g., air, water, iron, lead), ex function values, and recommended forms for recording evidence
bearing on standard emitters and dosimeters.
Articles from the Periodical Literature
I. Nuclear Physics
(Nuclear reactions, neutrons, fission of nuclei).
Zhur. dltsptl. i teoret. fiz., 44, No. 6 (1963).
24. A. Perfilov et al., 1832-36. Ternary plutonium fission.
L. N. Usachev etal., 1950-52. Determination of fission threshold in experiments on the (d, phand (y, f)
reactions.
Pribory Itekhn. ksper., No. 3 (1963).
S. S. Moskalev et al., 58-61. A multifilament neutron detector with nonoverloading preamplifier.
M. P. Sokolov, 66-71. Automatic facility measures radioactivity of wire.
A. B. Ekatov. etal., 72-78. A multidimensional analyzer.
Trudy akad. nauk I,itov. SSR. Seriya B, 1(1963).
V. Yu. Potsyus and I. S. Tomkus, 20-32. The background of nuclear emulsions used in the study of atmospheric
Industries atomiques, 7, Nos. 5-6 (1963).
A. Biette, 123-98 Ultrahigh-vacuum pumps for nuclear research.
Nucl. Physics, 43, No. 2 (1963).
M. Anderson and W. Bond, 330-38. Neutron spectrum of a elutonium-beryllium source.
1094
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
D. Winterhalter, 339-43. Angular distribution of fast neutrons scattered in aluminum.
Reactor Sci. and Teclinol., 17, No. 3 (1963).
G. Gierts, 121-24. Fast neutron spectrometry based on the Lie (n, t)He4reaction.
F. Brown et al., 137-41. Cross section of the Li7 (n, t) reaction for 3.5 to 15 MeV neutrons.
II. Plasma Physics
Doklady akad. nauk SSSR, 149, No. 5 (1963).
A. E. Bazhanova and V. D. Shfranov, 1049-51. On radiation from a charge moving in a plasma near cyclo-
tron resonance.
L. M. Kovrizhnykh et al., 1052-55. Hydrodynamic oscillations of a low-pressure homogeneous plasma in a
magnetic field.
V. K. Mer nikov, 1056-59. On the lines of force of a magnetic field established by helical currents flowing
on the surface of a torus.
Zhur. tekhn. fiz., 33, No. 6 (1963).
E. E. Lovetskii and A. A. Rukhadze, 652-59. Oscillations of a cold inhomogeneous plasma in a gravitational
field.
E. E. Lovetskki and A.A. Rukhadze, 660-66. On the convective instability of an inhomogeneous plasma in a
gravitational field.
M. V. Samokhin, 667-74. Heat currents and flows in a dual-temperature plasma.
M. V. Samokhin, 675-85. Particle and heat flows in a multicomponent plasma.
Yu. G. Zubov, 686-92. Study of the energy spectrum of electrons and ions escaping through the ends of a
magnetic mirror machine.
F. G. Baksht, 693-702. Flight oscillations in an electron-ion stream.
V. P. Demidov and D. A. Frank-Kamenetskii, 703-709. Collisional dissipation on cyclotron overtones in a
plasma.
V. V. Matveev et al., 710-14. Investigation of hard plasma radiation in a strong magnetic field.
K. V. Suladze and A. A. Plyutto, 716-18. Some aspects of converging plasma jets in an induction discharge.
Zhur. eksptl. i teoret. fiz., 44, No. 6 (1963).
A. A. Galeev, 1920-34. Stability theory of an inhomogeneous rarefied plasma in a strong magnetic field.
L. M. Kovrizhnykh et al., 1953-63. On the oscillations of an inhomogeneous low-pressure plasma.
V.I. Petviashvili,1993-2000. On anomalous diffusion of a plasma in the presence of oscillations.
L. E. Pargamanik and G. M. Pyatigorskii, 2029-38. Shift and broadening of energy levels of one-electron
atoms and ions in a high-temperature plasma.
M. S. Khaikin et al., 2190-93. Standing magnetoplasma waves in bismuth single crystals.
Phys. Fluids, 6, No. 4(1963).
H. Furth, et al., 459-83. Instability of a planar pinch caused by finite conductivity.
H. Weitzner, 484-89. Green's function for the linearized one-dimensional Crooke's equation.
H. Liemohn and F. Scarf, 490-500. First-order and second-order perturbation of a plasma having a Cauchy
equilibrium distribution.
H. Karr et al., 501-507. Resonance interaction of a plasma with a spatially rotating stationary magnetic
field.
1095
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
G. Fejer, 508-12. Reflection and refraction of MHD waves at discontinuities.
L. Talbot et al., 559-65. Comparison between a Langmuir probe and microwave electron density measure-
ments in an arc-heated low-density wind tunnel.
N. Geffen, 566-71. Magnetogas-dynamic flows with shock waves.
L. Taylor, 591-92. Electron temperature in gases situated in radio-frequency fields.
N. D' Angelo, 592-93. Ion waves in an inhomogeneous plasma.
G. Bethke and A. Ruess, 593-94. Dynamical relationship between low-power microwaves and a shock-wave
plasma.
G. Bethke et al., 594-96. Dynamical relationship between high-power microwaves and a shock-wave
plasma.
K. Uo, 596-97. Adiabatic compression of plasma by a magnetic field of multipole axial cusped geometry.
III. Nuclear Engineering. Nuclear Power
(Neutron Physics. Nuclear reactor theory and calculations. Reactor design. Operation of nuclear reactors and re-
actor power stations. Nuclear radiation shielding. Disposal of radioactive wastes.)
Izvestiya akad. nauk Lat. SSR, No. 2 (1963).
D. Dobryakov et al., 68-74. Electromagnetic shuttle network at a reactor installation.
Nauka i tekhnika, No. 4 (1963).
K. Shvarts, 7-9. The Salaspils (Latvia) nuclear reactor ready for research work.
Teploenergetika, No. 5 (1963).
L. S. Sterman et al., 35-38. Reactor power station layout with steam superheat in a separate reactor.
Teploenergetika, No. 6 (1963).
V. I. Subbotin et al., 70-74. Measuring temperature fields in turbulent mercury flow through tubes.
Tekhnika kino i televideniya, No. 5 (1963).
N. V. Lapteva and V. S. Polonik, 69-77. Closed-circuit TV in nucleonic and nuclear power applications.
Energia Nucleare, 10, No. 5 (1963).
P. Basso et al., 237-46. Variational technique for computing extrapolation length of some fuel elements,
for application in thermal utilization determinations.
gnergie nucleaire, 5, No. 2 (1963).
P. Delame, 154-67. High-flux-density nuclear reactors.
Industries atomiques, 7, Nos. 5-6 (1963).
M. Barbier, 55-65. Radioactivity induced in materials by high-energy protons, neutron, and photons.
J. Juillard, 73-84. Nuclear power in Japan.
J. Nucl. Materials, 8, No. 1 (1963),
R. Sowden, 81-101. Radiolytic problems in water reactors.
Kemenergie, 6, No. 4 (1963).
H. Heinrich, 146-51. Boundary conditions at the surface of hollow control rods slowing down neutrons in ac-
cordance with the three-group method.
Kernenergie, 6, No. 5 (1963).
P. Wenzel, 193-202. Investigations of uranium-plutonium cycles applicable to water-moderated reactors.
1096
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
F. Krtiger and A. Willer, 207-209. Determination of gamma flux inside an extended source.
Nucl. Energy (June, 1963):
A. Thorne, 145-56. Shielding equipment for nuclear deactivation systems.
J. Pearson, 156-64, Internal heat transfer in fuel elements.
Nucl. Engng., 8, No. 86 (1963).
---, 231-36. Glove boxes.
D. Robertson, 236-37. Multiple-purpose shielded cave.
---, 237-38. Design of glove boxes at Aldermaston.
---, 239-41. Brief data on glove boxes available from American, British, and West German manufacturers.
---, 242-44. Shielded cells for handling high-level materials at Windscale.
- -, 245-47, Tables of data on shielded caves for handling radioactive high-level materials, country by
country.
W. Burton and A. Mills, 248-52. Computer calculations of fuel reprocessing schemes.
Nucl. Sci. and Engng., 15, No. 3 (1963).
C. Wilkins, 229-32. Note on collisional density at epithermal energies.
P. Nichols et al., 233-44. Measurement of lattice constants in gas-cooled reactor.
R. Osborn, 245-58. Discussion of theroretical investigations of probe-induced flux perturbations.
W. Lanning, 259-67. Application of spherical harmonics to gamma flux transport.
P. Tunnicliffe et al., 268-83. Exact determination of relative initial conversion ratio.
E. Bryant et al., 288-95. Loss rates and loss mechanisms of fission products from uranium-graphite fuel.
E. Garelis, 296-304. Time-dependent neutron thermalization for an unreflected multiplying medium.
J. Walker et al., 309-313. Thermal flux perturbations caused by indium foil in water.
G. Hanna, 325-37. Neutron flux perturbations due to absorber foil. Theory compared to experiment.
H. Albers et al., 342-44. Xenon poisoning in ,a shutdown reactor.
J. Randall and J. Walker, 344-45. Foils which do not cause flux perturbations. Experimental verification.
Nucleonics, 21, No. 6 (1963).
H. Davis, 60-63. How big will power plants get?
R. Creagan and A. Jones, 64-67. How far can we go with PWRs?
W. Oberly and G. Roy, 68-71. How far can we go with BWRs?
L. Koch, 72-75. The future of fast breeders.
M. Edlung and P. Schutt, 76-78. The future of thermal breeders.
D. Stoker et al., 79-84. Wanted: a balanced nuclear economy.
L. Nelson, 88-89. Gamma-ray absorptiometry determines total uranium in flat fuel elements.
A. Humm and S. Protter, 96, 98. Reconditioning the Brookhaven graphite reactor fuel-storage canal.
Nukleonik, 5, No. 4(1963).
K. Becker, 137-47. Measuring burnup conditions for a flow of boiling water in round vertical channels.
W. Kehler and J. Romanos, 159-63. Neutron flux measurements by fast-neutron fissioning of U238 and Th".
1097
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
W. Dio et al., 163-70. Experimental determination of the 2. coefficient for reactor lattices for the
ARGONAUT reactor.
T. Stribel, 170-73. Neutron lifetime measurements and thermal reactor reactivity measurements by the
Rossi a-method.
H. Hejtmanek, 173-78. Elementary solution of the transport equation by means of anisotropic scattering.
A. Belleni-Morante, 183-84. Reactor kinetic equations.
Reactor Sci. and Technol., 17, No. 3 (1963).
H. Meister, 97-114. Subcritical uranium-heavy water lattice experiments using a pulsed neutron source.
Y. Fukai, 115-20. Neutron collision probability in first flight, in a cylindrically shaped moderated fuel
system.
E. Axton, 125-35. Absolute in-pile flux density measurement in the GLEEP reactor.
B. Fastrup, 143-44. In-pile epithermal spectrum measured experimentally.
IV. Materials for Atomic Industry
(Geology. Chemistry. Chemical process technology. Metallurgy).
Geokhimiya, No. 4 (1963).
M. M. Botova et al., 361-69. Experience in applying biogeochemical techniques to uranium prospecting
In desert areas.
S. M. Manskaya and L. A. Kodina, 370-82. Aromatic monomers of lignin in lignites, and their possible role
in the concentration of uranium, germanium, and vanadium.
Doklady akad. nauk SSSR, 149, No. 5 (1963).
A. D. Gel' man et al., 1071-73. Isolation of oxalato-sulfite and sulfite complexes of thorium IV and uran-
ium IV.
Zhur. anal. khim., 18, No. 4(1963).
A. A. Nemodruk and P. N. Palei, 480-85. Photometric study of the interaction between tetravalent uranium
and arsenazo-III.
T. S. Dobrolyubskaya, 486-91. Investigation of the fluorescence of uranylsulfite and uranylfluoride solutions,
with the aim of enhancing the sensitivity of uranium determinations.
Zhur. struktur. khim., 4, No. 2 (1963).
V. K. Trunov et al., 277-79. On the binary oxides of uranium, tantalum, and tin.
Atompraxis, 9, No. 5 (1963).
H. Getoff and W. Parker, 175-77. Isolation of high-purity I131 from Te131 by column chromatography.
Energia Nucleare, 10, No. 5 (1963).
Z. Hainski and G. Rossi, 247-58. Application of intensity ratio calculations to impurity determinations in
aluminum and SAP alloy.
A. Bassi and G. Camon, 277-79. Chemical polishing of uranium dioxide.
Energie nucleaire., 5, No. 2 (1963).
R. Taylor, 168-76. Recovery of krypton formed in fissioning of nuclear fuel.
P. Renault and X. Talmont, 177-90. Pulse extraction columns for uranyl nitrate extraction.
Y. Sausselier, 191-94. Evolution of the concept of nuclear grade purity.
1098
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
J. Inorg. and Nucl. Chem., 25, No. 4(1963).
T. Sato, 441-46. Solvent extraction of uranium (VI) from sulfuric acid solutions by tri-n-octylamine.
S. Adar et al., 447-52. Ion exchange behavior of transuranium elements in LiNO3 solution.
W. Jenkins, 463-64. Sulfaminic acid as a plutonium solvent.
J. Inorg. and Nucl. Chem., 25, No. 5 (1963).
R. Iyer et al., 465-72. Fission of Thm by pile neutrons. Yield curve as a function of mass.
E. Cordfunke and A. Van der Giessen, 553-55. Pseudomorphological decomposition of U04 to UO3.
M. Zangen, 581-94. Note on the synergic effect in solvent extraction. 1. Uranium (VI).
J. Nucl. Materials, 8, No. 1 (1963).
R. Caillat et al., 1-2. Justification of the choice of the Mg-Zr alloy for fuel-element cladding.
J. Bernard and B. Bondouresques, 3-11. Mg-Zr alloy as a fuel-cladding material.
J. Herenquel, 12-22. Fabrication technology and metallurgical properties of Mg-Zr alloys.
R. Darras et al., 23-28. Compatibility of Mg-Zr alloys and carbon dioxide under high pressure and at high
temperatures.
M. Salesse, 39-40. A new material for nuclear engineering: sintered magnesium oxide.
D. Leclercq et al., 41-48. Compatibility of sintered magnesium with carbon dioxide at high pressures and
high temperatures.
J. Herenquel, 49-59. Processing, transformation, and metallurgical properties of Mg-MgO type compounds.
L. Popple, 60-76. Oxidation of magnesium alloys under atmospheric conditions in a reactor.
R. Squires and R. Weiner, 77-80. Grain-boundary denuded zones in magnesium alloy with 0.5 wt. 07o zirconium.
J. Berry et al., 102-115. Leakage of gaseous fission products from irradiated sintered uranium oxide.
A. Lemogne and P. Lacombe, 116-25. Plastic flow and fracture of uranium single crystals under tensile load
at 196?C.
R. Akeret, 126-37, Welding of SAP (sintered aluminum powder).
P. Poeydomenge et al., 138-42. Uranium decontamination by progressive solidification.
G. Clottes, 143-47. Uranium recrystallization temperature in zone melting.
J. Nucl. Materials, 8, No. 2 (1963).
G. Higgins, 153-59. Secondary recrystallization in magnox Al 80 alloy.
G. Higgins and B. Pickles, 160-68. Hydrogen capture by Zr-55 alloy and its effect on the alloy's mechanical
properties.
R. Doldon, 169-78. Fatigue testing of magnesium-zirconium and magnesium-aluminum cladding materials.
E. Walker and P. Fisher, 179-86. Design of metallurgically stable magnesium-zirconium alloys.
S. MarvincoviC, 187-97. Formation of a solid solution in the U308--0UO2 transformation.
R. Kent and T. Wells, 198-206. Creep flow characteristics of the magnesium-zirconium alloy ZA at 400 and
450?C in carbon dioxide.
D. De Halas and G.Horn, 207-220. Development of changes in the structure of uranium dioxide upon irradia-
tion of fuel rods.
P. Thrower and W. Reynolds, 221-26. Changes in the microstructure of graphite brought about by neutron
irradiation.
1099
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25 : CIA-RDP10-02196R000600110002-5
J. Kelly, 227-31. Textured of hot-pressed Be0.
I. Barwood and B. Butcher, 232-40. a-8 -phase transformations in uranium.
A. Brailsford and K. Major, 241-47. Effects of irradiation on the resistivity and thermal conductivity of
a -uranium.
A. Brailsford, 248-58. Resistivity due to interstices and vacancies in a-uranium.
N. J. Bailey, 259-62. Oxidation of zirconium thin films.
K. Mackay and N. Hill, 263-64. Lattice parameter and hardness measurements in high-grade beryllium.
B. Raz and H. Schmidt, 265-67. Note on the electrical resistivity anomaly of sintered UO2.
M. Salesse et al., 268-70. Accumulation of helium in sintered specimens of neutron-irradiation beryllium
oxide.
I. Amato et al., 271-72. Comment on a case of density loss during sintering of a pair of UO2 beads.
A. Carrea 275-77. Sintering of uranium dioxide in an atmosphere of controlled hydrogen content.
Kemenergie, 6, No. 5 (1963).
H. Rabold and W. Schimmel, 187-92. Water chemistry problems in water-cooled power reactors.
R. Manze and 0. Hladik, 225-28. Radiochemical investigations of multiple splitting of uranium.
Kemtechnik, 5, No. 5 (1963).
W. Ochsetifeld and S. Krawczynski, 218-21. Mixer-settler for experimental research on extraction.
Nucl. Sci. and Engng., 15, No. 2 (1963).
M. Silverman et al., 217-18. Radiation damage to Freon-11 (Ce12F).
L. Baker et al., 218-20. Determination of total emissivity of polished and oxidized surfaces.
Nukleonik, 5, No. 4(1963).
P. Bettzieche_ et al., 148-53. Changes in the properties of steel irradiated by small doses, depending on ir-
radiation temperature.
V. Dosimetry and Radiometry. Nuclear Meteorology
Nauchn. trudy vyssh. ucheb. zaved. Litov. SSR. Geografiya i geologiya, 2 (1962).
V. Matulyavichene and V. Matulyavichus, 119-26. Some aspects of applications of A-2 type nuclear emul-
sion in research on atmospheric radioactivity.
Atompraxis, 9, No. 5 (1963).
E. Piesch, 179-88. Nuclear emulsions in fast-neutron dosimetry.
Nucleonics, 21, No. 6 (1963).
M. Tamers and R. Bibron, 90-94. Benzene method measures tritium in rain without isotope enrichment.
Nukleonik, 5, No. 4(1963).
K. Becker, 154-59. Phosphate film badge for nuclear plant personnel.
VI. Radioactive and Stable Isotopes
(Separation, production, applications).
Vestnik sko-Idioz. nauki, No. 4(1963).
S. V. Andreev et al., 135-38. Radioisotopes check effectiveness of pesticide spraying of crops.
1100
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Izvestiya ?vyssh. ucheb. zaved. Stroitel' stvo i arkhitektura, No. 3 (1963).
Yu. V. Dezhin and I. I. Borisov, 154-57. How gamma-emitters map boundaries of active zone under an ir-
radiation assembly.
Stroit. i dor. mashiny, No. 4 (1963).
V. I. Postnikov, 22-24. Radioisotopes in the building and building materials industries,
Trudy Volgograd. nauchno-issled. inst. neft. i gaz. prom., No. 2 (1963).
L. A. Karol' kov, 101-102. A radioactive level gage.
Energie nucleaire, 5, No. 3 (1963).
P. Bovard and A. Grauby, 149-53. Soil irradiation experiments in the TRITON pool reactor.
Kerntechnik, 5, No. 5 (1963).
H. J. Marcinowski, 201-204. Accidents in handling radioactive materials.
H. Ramdohr, 204-206. Activation analysis aids in grading copper ore.
W. Ktihn, 207-212. Continuous measurement of moisture content in sintered iron by neutron scattering.
Nucleonics, 21, No. 6 (1963).
---, 100-107. Advancing radioisotope applications in engineering and the physical sciences (Gatlinburg,
Tenn. April, 1963 conf.).
JADERN; ENERGIE, No. 9 (1963)
E. Karnikova, M. Holinka, and V. Masaryk. Uranium and beryllium compatibility.
J. Truhly and F. 'Silandar. Metallographic identification of inclusions in uranium metal.
J. Simorda. A 2000-curie .cobalt gamma facility.
M. Marchol. Ion exchange resins containing phosphor, arsenic, or antimony in their functional groups.
w,
J. Krtil, V. Kourim, and Z. Kolarik. Use of ammonium salts of heteropolyacids in isolation of Csi".
0. Caletka and M. Kirs. Comment on the mechanism underlying sorption of zirconium on silica gel from
nitrate solutions.
J. Staroba. Radioactive air ionizers for use in plastics manufacturing.
A. Uncovsky. Thickness measurement of hot-rolled strip in the 1-10 mm range.
L. Simon. The Alpha RAL-1 scintillation radiometer.
T. Fukatko. New facility measures intensity of beam of accelerated ions.
1101
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Soviet Journals Available in Cover-to-Cover Translation
ABBREVIATION
AE
Akust. zh.
Astr(on). zh(urn).
Avto(mat). svarka
Byull. eksp(erim).
biol. (i med.)
DAN (SSSR)
Dokl(ady) AN SSSR
Entom(o1). oboz(r).
FMM
FTT, Fiz. tv(erd). tela
Fiziol. Zh(um). SSSR
Fiziol(ogiya) rast.
Geol. nefti i gaza
lzmerit. tekhn(ika)
RUSSIAN TITLE
Atomnaya energiya
Akusticheskii zhumal
Astronomicheskii
Avtomaticheskaya
Avtomatika i Telemekhanika
Biofizika
Biokhimiya
Byulleten' eksperimentarnoi
biologii i meditsiny
Doklady Akademii
Nauk SSSR
Elektrosvyaz'
Entomologicheskoe
Fizika metallov i
Fizika tverdogo tela
Fiziologicheskii zhurnal
I.M. Sechenov
Fiziologiya rastenii
Geodeziya i aerofotosyemka
Geokhimiya
Geologiya nefti i
Geomagnetizm i
lskusstvennye sputniki
lzmeritel'naya tekhnika
TITLE OF TRANSLATION
Soviet Journal of Atomic Energy
Soviet Physics ?.Acoustics
zhurnal Soviet Astronomy ? AJ
svarka Automatic Welding
Automation and Remote Control
Biophysics
Biochemistry
Bulletin of Experimental
Biology and Medicine
Doklady Biological Sciences Sections
(includes: Anatomy, biochemistry, biophysics,
cytology, ecology, embryology,
endocrinology, evolutionary morphology,
genetics, histology, hydrobiology,
Life microbiology, morphology, parasitology,
Sciences physiology, zoology)
Doklady Botanical Sciences Sections
(includes: Botany, phytopathology,
plant anatomy, plant ecology,
plant embryology, plant physiology,
plant morphology)
Proceedings of the Academy of Sciences
E of the USSR, Section: Chemical Technology
Chemical Proceedings of the Academy of Sciences
oa Sciences of the USSR, Section: Chemistry
Proceedings of the Academy of Sciences -
Cc of the USSR, Section: Physical Chemistry
Doklady Earth Sciences Sections
.175 (includes: Geochemistry, geology,
17) geophysics, hydrogeology, lithology,
C .*2
Le_ 7/3 Earth mineralogy, oceanology, paleontology,
?-? Sciences .. permafrost, petrography)
a a /Proceedings of the Academy of Sciences
.12 of the USSR, Section: Geochemistry
Proceedings of the Academy of Sciences
of the USSR, Section: Geology
Mathematics Soviet Mathematics ? Doklady
Soviet Physics ? Doklady
(includes: Aerodynamics, astronomy,
crystallography, cybernetics and control
theory, electrical engineering, energetics,
Physics fluid mechanics, heat engineering,
hydraulics, mathematical physics,
mechanics, physics, technical physics,
theory of elasticity sections)
Telecommunications
obozrenie Entomological Review
metallovedenie Physics of Metals ano Meta Ilography
Soviet Physics ? Solid State
imeni Sechenov Physiological Journal USSR
Plant Physiology
Geodesy and Aerophotography
Geochemistry
gaza Petroleum Geology
aeronomiya Geomagnetism and Aeronomy
zemli Artificial Earth Satellites
Measurement Techniques
PUBLISHER
Consultants Bureau
American Institute of Physics
American Institute of Physics
Br. Welding Research Assn. (London)
Instrument Society of America
National Institutes of Health**
Consultants Bureau
Consultants Bureau
National Science Foundations-
National Science Foundation*
Consultants Bureau
Consultants Bureau
Consultants Bureau
American Geological Institute
Consultants Bureau
Consultants Bureau
American Mathematical Society
American Institute of Physics
Am. Inst. of Electrical Engineers
National Science Foundation**
Acta Metallurgica
American Institute of Physics
National Institutes of Health**
National Science Foundation*
American Geophysical Union
The Geochemical Society
Petroleum Geology
American Geophysical Union
Consultants Bureau
Instrument Society of America
TRANSLATION
Vol. Issue
1 1
1 1
34 1
12 1
27 1
6 1
21 1
41 1
112 1
112 1
106 1
106 1
112 1
124 1
106- 1
123 6
112- 1
123 6
130 1
106 1
1
37 t
5 1
1 1
47 1
4 1
1 1
2 1
1 1
1 1
7 1
BEGAN
Year
1956
1955
1957
1959
1956
1961
1956
1959
1957
1957
1956
1956
1957
1959
1956-
1958
1957-
1958
1960
1956
1957
1958
1957
1959
1961
1957
1962
1956
1958
1961
1958
1958
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
lzv. AN SSSR
0(td). Kh(im). N(auk)
lzv. AN SSSR
C(td). T(ekhn). N(auk):
Metall). i top.
fzv. AN SSSR Ser. fiz(ich).
lzv. AN SSSR Ser. geofiz.
lzv. AN SSSR Ser. geol.
lz. Vyssh. Uch. Zav.,
Tekh. Teks. Prom.
Kauch. i rez.
Kolloidn. zh(urn).
Metallov. i term.
Met. i top.(gorn.)
Mikrobiol.
OS, Opt. i spektr.
Paleontol. Zh(urn)
Pribory i tekhn.
eks(perimenta)
Prikl. matem. i mekh(an).
PTE
Radiotekh.
Radiotekhn. i elektron(ika)
Stek. i keram.
Svaroch. proiz-vo
Teor. veroyat. i prim.
Tsvet. metally
UFN
UKh, Usp. khimi
UMN
Vest. mashinostroeniya
Vop. onk(o1).
Zav(odsk). lab(oratonya)
ZhAKh, Zh. anal(it). Khim(ii`
ZhETF
Zh. eksperim. i teor. fiz.
.ZhFKh
Zh. fiz. khimii
ZhNKh
Zh. neorg(an). khim.
ZhOKh
Zh. obshch. khim.
ZhPKh
Zh. prikl. khim.
ZhSKh
Zh. strukt(urnoi) khim.
ZhTF
Zh. tekhn. fiz.
Zh. vyssh. nervn. deyat.
(im. Pavlova)
lzvestiya Akademii Nauk SSSR:
Otdelenie khimicheskikh nauk
(see Met. i top)
lzvestiya Akademii Nauk SSSR:
Seriya fizicheskaya
lzvestiya Akademii Nauk SSSR:
Seriya geofizicheskaya
lzvestiya Akademii Nauk SSSR:
Seriya geologicheskaya
lzvestiya Vysshikh Uchebnykh Zavedenii
Tekhnologiya Tekstil'noi
Promyshlennosti
Kauchuk i rezina
Kinetika i kataliz
Koks i khimiya
Kolloidnyi zhurnal
Kristallografiya
Metallovedenie i termicheskaYa
obrabotka metallov
Metal lurg
Metallurgiya i toplivo (gornoye delo)
Mikrobiologiya
Ogneupory
Optika i spektroskopiya
Paleontologicheskii Zhurnal
Pochvovedenie
Poroshkovaya Metallurgiya
Priborostroenie
Pribory i tekhnika eksperimenta
Prikladnaya matematika i mekhanika
(see Pribory i tekhn. eks.)
Problemy Severe
Radiokhimiya
Radioteknika
Radiotekhnika i electronika
Stal'
Stanki i instrument
Steklo i keramika
Svarochnoe proizvodstvo
Teoriya veroyatnostei i ee primenenie
Tsvetnye metally
Uspekhi fizicheskikh nauk
Uspekhi khimii
Uspekhi matematicheskaya nauk
Vestnik mashinostroeniya
Voprosy onkologii
Zavodskaya laboratoriya
Zhurnal analiticheskoi khimii
Zhurnal eksperimental'noi i
teoreticheskoi fiziki
Zhurnal fizicheskoi khimii
Zhurnal neorganicheskoi khimii
Zhurnal obshchei khimii
Zhurnal prikladnoi khimii
Zhurnal strukturnoi khimii
Zhurnal tekhnicheskoi fiziki
Zhurnal vychislitel'noi matematika i
matematicheskoi fiziki
Zhurnal vysshei nervnoi
deyatel'nosti (im I. P. Pavlova)
Bulletin of the Academy of Sciences of
the USSR: Division of Chemical Science
Bulletin of the Academy of Sciences
of the USSR: Physical Series
Bulletin of the Academy of Sciences
of the USSR: Geophysics Series
Bulletin of the Academy of Sciences
of the USSR: Geologic Series
Technology of the Textile Industry, USSR
Soviet Rubber Technology
Kinetics and Catalysis
Coke and Chemistry, USSR
Colloid Journal
Soviet Physics ? Crystallography
Metals Science and Heat Treatment of
Metals
Metallurgist
Russian Metallurgy and Fuels(mining)
Microbiology
Refractories
Optics and Spectroscopy
Journal of Paleontology
Soviet Soil Science
Soviet Powder Metallury and Metal Ceramics
Instrument Construction
Instruments and Experimental Techniques
Applied Mathematics and Mechanics
Problems of the North
Radiochemistry
Radio Engineering
Radio Engineering and Electronic Physics
Stal (in English)
Machines and Tooling
Glass and Ceramics
Welding Production
Theory of Probability and Its Application
The Soviet Journal of Nonferrous Metals
Soviet Physics ? Uspekhi (partial translation)
Russian Chemical Reviews
Russian Mathematical Surveys
Russian Engineering Journal
Problems of Oncology
Industrial Laboratory
Journal of Analytical Chemistry
Soviet Physics ? JETP
Russian Journal of Physical Chemistry
Journal of Inorganic Chemistry
Journal of General Chemistry USSR
Journal of Applied Chemistry USSR
Journal of Structural Chemistry
Soviet Physics ? Technical Physics
U.S.S.R. Computational Mathematics and
Mathematical Physics
Pavlov Journal of Higher Nervous Activity
Consultants Bureau
Columbia Technical Translations
American Geophysical Union
American Geological Institute
The Textile Institute (Manchester)
Palmerton Publishing Company, Inc.
Consultants Bureau
Coal Tar Research Assn. (Leeds, England)
Consultants Bureau
American Institute of Physics
Acta Metallurgica
Acta Metallurgica
Scientific Information Consultants, Ltd.
National Science Foundation*
Acta Metallurgica
American Institute of Physics
American Geological Institute
National Science Foundation**
Consultants Bureau
Taylor and Francis, Ltd. (London)
Instrument Society of America
Am. Society of Mechanical Engineers
National Research Council of Canada
Consultants Bureau
Am. Institute of Electrical Engineers
AM. Institute of Electrical Engineers
Iron and Steel Institute
Production Engineering Research Assoc.
Consultants Bureau
Br. Welding Research Assn. (London)
Soc. for Industrial and Applied Math.
Primary Sources
American Institute of Physics
Chemical Society (London)
Cleaver-Hume Preis, Ltd. (Lisndon)
Production Engineering Research Assoc.
National Institutes of Health**
Instrument Society of America
Consultants Bureau
American Institute of Physics
Chemical Society (London)
Chemical Society (London)
Consultants Bureau? .
Consultants Bureau
Consultants Bureau
American Institute of Physics
Pergamon Press, Inc..
National Institutes of Health**
16
18
7
23
4
la
1
14
2
6
26
25
6
53
2
4
3
22
4
16
6
19
30
13
5
1
33
66
29
15
39
7
24
7
28
33
4
19
23
1
26
1
11
1
3
1
1
1
3
1
a
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
1
4
1
1
1
1
1
4
1
1
1
1
7
1
1
1
1
1
1
1
1952
1954
1957
1958
1960
1959
1960
1959
1952
1957
1958
1957
1960
1957
1960
1959
1962
1958
1962
1959
1958
1953
1958
1962
1961
1961
1959
1959
1956
1959
1956
1960
1958
1960
1960
1959
1961
1958
1952
1955
1959
1959
1949
1950
1960
1956
1962
1961
*Sponsoring organization. Translation published by Consultants Bureau.
**Sponsoring organization. Translation published by Scripta Technica.
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
Declassified and App- roved For Release 2013/02/25: CIA-RbP10-02196R000600110002-5
s2p
.4?Z 4
L.0.41.
?
,??
CALCULATION OF
THERMAL STRESSES
IN NUCLEAR
ri REACTORS -
by I. I. Gol'denblat
and N. A.' Nikolienko
r, Translated from ,Russian
,
Mk, -??????;.1%
?
v." ?
Soa.\:?,4?S,Sal r4 *I. ?
? ? ??? ?
"
?
.* ?
;s/
EZ*1.C.?..3V1.
*?? N.:14 '-
0 N.
ce;
-,41; ? s,ci
?..7.;.?sM
4:>'41-kW5
1.1.74%;
17.70-4
N.1:44
;ttfi,
? ktirit:.
. ? esto..,16x.
rv33/-
7s9%4
The *sent book sets forth methods of calculating?the
temperature stresses in the constructional elements of
'nucleat reactors ? principally stationary type nuclear
reactors. Methods are given for calculating the tem-
perature stresses?in different .shape fuel elements and
for designing reactor elements ifor thermal shock, as
well as methods of designing tiousings and other re-
actor elements for thermal creep. A particularly large
amount of attention is given t?alculating the tempera-
ture stresses and creep deformations in the concrete
biological shield of reactors. Methods of calculating
the temperature stresses in special constructional ele-
ments of 'nuclear reactors are also given.
The book takes the view that the thermoelastic stresses
occurring in reactor elements may be investigated inde-
pendently of the Mechanical stresses produced by ex-
ternal forces, since because of the linearity of the
thermoelastic' equations the final values for the stresse:s
may be found by simply adding together the tempera-
ture and mechanical stresses. The same approach
applies to the linear theory of thermal creep, 'which
is used in the book to calculate the'stresses and thermal'
creep deformations" in the concrete biological shield
of a reactor.
? \ ?
The thermal plasticity equations are nonlinear. Ac-
cordingly, it is impossible to make a study of the
thermosplastic stresses without including the mechan-
ical stresses. This is also true with regard to all the
nonlinear thermal creep theories. Therefore, in, the
piesent? book, the thermoplastic stresses (as well as
the thermal 'stresses associated Ivith 'nonlinear Creep)
are treated together With the mechanical' stresses pro-
duced by external force.
?
The calculations presented in this volume will be of
significant interest to engineers concerned with the
indices of the maximum permissible dimensions of
various constructional elements in reactor, technology,
and those responsible for their reinforcement.
80 lines
v
?
A Special Research Report , '$15.00 ? ,
? Contents on'request ? ?
CONSULTANTS BUREAU''.
227 W. i7th St., NeW York. N.Y. 10011
,
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
?
r
f,
?
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5
RESEARCH IN
SURFACE FORCES
Edited by B.V, Deryagin ?
The 29 reports contained in this collection were presented at
the conference On surface forces held at the Institute of Phys-
ical Sciences of the Academy of Sciences of the USSR. Follow-
ing an introductory paper, the remaining 28 prisentations cover
results of investigations (theory ? and practice) ,on surface
forces in various systems, their properties, and methods,of
investigations parried out by. Soviet scientists. The editor:who
has cofitributed to nearly half the papers in this volume, is an
academician-of the Academy of ScieriPes of the USSR, and is
also the organizer and permanent Director of the Laboratory
of Surface Phenomena at the Institute.
Translated from Russian. A Special Research Report.
190 pages $27.50
CONTENTS .
Twenty-five Years in the Laboratory of Surface Phenomena of the Insti-
tute of Physical Chemistry of the Academy of Sciences of the_USSR
GENERAL PROBLEMS IN SURFACE fORCES
Surface Forces and Their Effect on the Properties of Heterogeneous "
Systems,
A Study of the State of Connate Water in-Oil Reservoirs
The General Theory of Type II Capillary Effects
diffusional Surface Forces in the Neighborhood of a Liquid Interface
' POLYMER ADHESION
A Luminescence Study of the Adhesion Bonding of Polymers
The Effect of Molecular Weight, Polydispersion and Polarity on the
Adhesion of High Polymers to High-Molecular Substrata
The Role of Surface forces in Mica CristOls
The Double Layer at a Solid Surface Resulting ;from Acceptor?Donor
, Bonds '
The Application of Infrared-Spectroscopy to the Studying of the Inter-
action of Adhesive and Substrate (Polymer?Glass)
-Measurement of the True DenSity of he Double Electric Layer at a
Metal-Dielectric Interface,
SURFACE FORCES IN THIN LIQUID FILMS
The PhysicalBasis of the Fundamental Law of Surface Function
The-Properties ef Solutions of Organic Acids in Liquid Hydrocarbons at
-Solid Surfaces
Certain ConsideratiOns Concerning the Laws Applying to Type I Friction-
New Experimental Data on External Friction
A Cinematographic Study of the Flow of Thin Films of Polymer Solutions
The Effect of -"Electrolyte Concentration on the Height of the Force
' Barrier for Adhesion of Platinum Wires ,
SURFACE EFFECTS IN DISPERSED SYSTEMS
A Radioisotope Study of the Movement of Moisture in Peats
Surface Effects in Soil MechOnics
"The Theory of Coagulation of Lyophobic Soils by Mixtures of Electrolytes ,
Studies on the Filtration', of Solutions of 'Electrolytes Through Highly ,
Dispersed Powders s
A Study of Slow Hydrosol Coagulation Using the Continuous Flow Ultra-
microscope . ?
An,Experimental Study of the Filtration of Air Through Porolis Bodies
in the Region of Transition-Pressures ?
A Metallie,Apparatus for Determining Specific Surfaces of Powders and
'Porous Bodies
SURFACE FORCES IN AEROSOLS
Diffusional Phoresis of Aerosol Particles ,
The Behavior of Small Aerosol Particles in a Nonuniformly Heated
Gaseous Mixture'
A Differential Counter for Condensation Nuclei
/ A New Method for Obtaining Constant and Uniform Supersaturations '
Solution of the Kinetic Equation for Coagulation
f
CONSULTANTS BUREAU 227 W.17th St., NEW YORK N.Y. 10011
?,?
Declassified and Approved For Release 2013/02/25: CIA-RDP10-02196R000600110002-5