THE SOVIET JOURNAL OF ATOMIC ENERGY VOL. 8 NO. 2

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• Document Page Count: 82
• Document Creation Date: December 27, 2016
• Document Release Date: February 19, 2013
• Sequence Number: 2
• Publication Date: May 1, 1961
• Content Type: REPORT

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--vc?s7to
Volume 8, No. 2
May, 1961
THE SOVIET JOURNAL OF
TSATi) OM7,'?,,SSJAN?
CONSULTANTS BUREAU
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1=60'
the latest Soviet techniques:
CONTEMPORARY EQUIPMENT
for ;WORK with
FADIOACTIVE ISOTOPES
c1:01
A comprehensive review of the Soviet method 'and tech-
nological 'procedures used in the production of isotopes and
. the preparation of labelled compounds from them. The shield-
- ing and manipul,ative devices .are described as well as illus-
trated -in detail. It is an excellent, guide ,for all scientists
and technologists concerned With radioactive isotopes.
CONTENTS'
Some technical and technological aspects of the production
of4Sotopes and labeled-compounds in the USSR,.
? INTRODUCTION
.
Development of remote handling methods in the radiochem-
ical laboratories, of the Academy of Sciences, :USSR.
Shielding and manipulative devices for work with radio-
active isotopes.
INTRODUCTION ,
CHAPTER I. Development of Shielding Techniques in
, I Ra`diopreparative Operations
?
CHAPTER II. Mechanical Holding Devices ".,
CHAPTER ILI. Remote Pneumatic Manipulators _
,CHAPTER IV. Liquid Dispenses
CHAPTER V. RadioChemical Hydromanipulators
CHAPTER VI. Radiopreparative 'pneumatic "Hydromanip-
, ulators
CHAPTER VII. Toothed Mechaisins for Manipulative De-,
vices
? CHAPTER VIII. Non-Destructive Methods of Ampule' In-
spection
'CHAPTER
CONCL. USION
Some' Decontamination Method?
durable paper covers - 67. pages illus. $15.00
CONSULTANTS BUREAU
227 W. 17th ST., NEW, YORK 11? N. Y.
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?
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EDITORIAL BOARD OF
ATOMNAYA 2NERGIYA
A. I. Alikhanov
A. A. Bochvar
N. A. Dollezhal'
D. V. Efremov
V. S. Emel'yanov
V. S. Fursov
V. F. Kalinin
A. K. Krasin
A. V. Lebedinskii
A. I. Leipunskii
I. I. Novikov
(Editor-in-Chief)
B. V. Semenov
V. I. Veksler
A. P. Vinogradov
N. A. Vlasov
(Aseistant Editor)
A. P. Zefirov
THE SOVIET JOURNAL OF
ATOMIC ENERGY
A translation of ATOMNAY A ENERGIY A,
a publication of the Academy of Sciences of the USSR
? (Russian original dated February, 1960)
Vol. 8, No. 2 May, 1961
CONTENTS
Thermal Stresses in Reactor Constructions. A. Ya. I4amerov, Ya. B. Fridman, and
PAGE
RUSS.
PAGE
S. A. Ivanov 1
91
101
The Deformation of Uranium Under the Influence of Thermal Cycles During the Simultaneous
Action of an External Tensile Load. A. A. Bochvar, G. Ya. Sergeev, and V. A. Davydov. .
100
112
The Separation of Pa233 Without a Carrier from Thorium Nitrate Preparations Irradiated by
Slow Neutrons. V. I. Spitsyn and M. M. Golutvina
105
117
Determination of the Optimum Yield of Enriched Ore in Radiometric Enrichment of Uranium
Ores. E. D. Mal'tsev
108
121
Strong Focusing in a?Linear Accelerator. P. M. Zeidlits, L. I. Bolotin, E. I. Revutskii, and
114
127
V. A. Suprunenko
LETTERS TO THE EDITOR
Stability of Plasma Bunches in a Waveguide. M. L. 'Levin
120
134
Self-Reproducing Solutions of the Plasma Equations. B. N. Kozlov
121
135
Complex Fission of Uranium by 2.5-Mev Neutrons. Z. I. Solov'eva
124
137
Fission Cross Sections for Th236, Pu246, Pu241, and Am241 by Neutrons with Energies of 2.5 and
14.6 Mev. M. I. Kazarinova, Yu. S. Zamyatin,, and V. M. Gorbachev
125
139
Analysis of Neutron Interactions with He4 , C12, and .016 Nuclei Using an Optical Nuclear
Model. E. Ya. Mikhlin and V. S. Stavinskii..
127
141
Experimental Investigation of Heat Transfer in Slit-Type Ducts with High Heat-Transfer
Rates. Yu. P. Shlykov .
130
144
An Investigation of the Alloys of the Uranium-Germanium System. V. S. Lyashenko and
132
146
V. N. Bykov
Coprecipitation of Pu (IV) with Organic Coprecipitants. V. I. Kuznetsov, and T. G. Akimova.
135
148
Contribution to the Problem of Electron Injection to a Betatron. V. P. Yashukov
137
150
Some Data on the Distribution of Radiations Emanating from the Synchrocyclotron of the.
Joint Institute for Nuclear Research. M. M. Komochkov and V. N. Meldiedov
138
152
Dose Field of a Linear Source. V. S. Grammatikati, U. Ya. Margulis, and V. G. Khrushchev.
140
154
Experimental Investigation of Scintillation Counter Efficiency. V. P. Bovin
142
155
A Mobile Neutron Multiplier Unit. T. A. Lopovok
145
158
NEWS OF SCIENCE AND TECHNOLOGY
The Production and Use of Stable Isotopes in the USSR
147
160
Conference on the Uses of Large Radiation Sources in Industry and Particularly in Chemical
Processes
151
164
Annual subscriptions 75.00 .0 1961 Consultants Bureau Enterprises, Inc., 227 West 17th St., New York 11, N.Y.
Single issue 20.00 Note: The sale of photostatic copies of any portion of this copyright translation is expressly
Single article 12.50 prohibited by the copyright owners.
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CONTENTS (continued)
PAGE
RUSS.
PAGE
Tashkent Conference on the Peaceful Uses of Atomic Energy. A. Kiv, and E. Parilis
154
167
[Atomic Energy in Italy
1691
[Experiments on Doppler Broadening of Resonance Levels in Uranium and Thorium
171]
[Shielding Design Nomograms
172]
[Uranium Prospecting Methods in France
1721
Stafidardi. Tina? Gamma Sources
156
177
Brief Notes
157
174
INFORMATION AND BIBLIOGRAPHY
New Literature .
158
178
A Message from the Central Committee of the Communist:Party of the Soviet Union and the
Council of Ministers of the USSR
163
Insert
Mikhail Mikhailovich Konstantinov ;.
166
0
NOTE
The Table of Contents lists all material that appears in Atomnaya fnergiya. Those items
that originated in the English language are not included in the translation and are shown enclosed
in brackets. Whenever possible, the English-language source containing the omitted reports will
be given.
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THERMAL STRESSES IN REACTOR CONSTRUCTIONS
A. Ya. Kramerov, Ya. B. Fridman, and S. A. Ivanov
Translated from Atomnaya rnergiya, Vol. 8, No, 2, pp. 101-111,
February, 1960
Original article submitted May 9, 1960
Conditions for the appearance of thermal stresses in reactors are investigated; also their magnitude and the danger
they create are estimated. The influence of the form of the heat-generating elements (HGE) on the temperature
drop and magnitudes of thermal stresses is analyzed; recommendations are given with the aim of decreasing the
harmful effect of thermal stresses.
The methods from the theory of elasticity employed in the calculation of thermal stresses have significant
limitations. In many cases when estimating the magnitude and degree of danger created by the thermal stresses,
when combining such stresses with mechanical stresses, and also when seeking a way to decrease them, other effects
such as fluidity, creep, initial breakdown, and microscopic processes must be taken into consideration.
INTRODUCTION
In recent years the study of thermal stress has enjoyed
great attention, particularly in connection with the known
framework of atomic reactors. Among the characteristics
of reactors we make particular note of the following;
a) the intensive neutron and y radiation at moderate
temperatures which leads to a decrease in plasticity;
b) internal radiational heat sources;
C) high thermal current (106kcal/m2-hour) and heat
production density (109 kcal/m3-hour), resulting in a
large temperature gradient (-400? C/mm );
d) the use of new little-studied materials (sometimes
undergoing undesirable structural transformations upon
heating) and combinations of materials with different
coefficients of thermal expansion;
e) sharply repeated changes in the temperature result-
ing in a thermal shock in the structure (for example, in
the case of an emergency stoppage of the reactor);
f) the use of new complex structures, for which there
have been neither analogies in the usual engineering
techniques, nor long-run operational tests. Significant
thermal stresses also may arise in structures associated
with long established areas of engineering (for example,
in reactor turbine construction). However ,the many vari-
ants and long operational tests which have accumulated
in these areas in many cases permit by extrapolation the
use of structures near to those tested in practice, and there-
by some of the dangers from thermal stresses may be
avoided.
The literature on theoretical questions having to do
with thermal stresses is fairly large, but it consists pri-
marily of papers treating the analytical solution of differ-
ent problems in the field of eleasticity [1], and, far
more rarely, in elastoplasticity [2-5]. In this literature
only macroscopic stresses (of the first kind) are considered.
We mention also papers [6-13].
Estimate of the magnitude of temperature
stresses
Basic notation: 00.or, 0 z are the normalstresses acting
in the angular, radial and axial directions respectively; a
is the thermal coefficient of linear expansion; E,the
modulus of elasticity (kg/cm2); v,Poissori's coefficient;
AT=Tr?Tinit the deviation of the temperature from that
of the initial( Tinit)unstressed state; T,the average
value of AT with respect to cross 'section; Q,the total
rate of heat generation (kcal/hour); qF the thermal flux
(kcal/m2-hr); a the density of heat generation (kcal/m3-
hr); a, 12. the internal and external radii of a tube; ri; the
radius of a cylindrical rod; p = a/ bthe dimensionless radius
of the hole in a tube; and lir is a form factor, equal to
the ratio of stress (or temperature drop) in a body of the
shape considered,to that in a circular cylinder (other
conditions being equal).
The magnitude of the thermoelastic stresses of the
first kind is estimated by the formula
a =EA (aT) and a =BaAT (for a=const). (1)
In the presence of internal heat sources in bodies
with more or less smooth shapes the temperature change
in a cross section is equal to
qp ro
AT ( 2)
X X Fq Fq 4? 1?'
where ro = 1.2V/Fq is a quantity proportional to the
mean path taken by the flow of heat in the body; V is
the volume of the body (m3); qr. Q/Fctt the thermal flux;
and F,the heat transfer at the surface.
91
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If the thermal stresses reach the yield point for the
material, then the body or its individual parts enter the
plastic state and thermoplastic stresses arise. In the elastic
region the stresses at each moment are determined by
the existing temperature field, whereas in the plastic
region the stresses depend also on the past history of the
body.
The exact temperature field, and also the thermal
stress and displacements of the first kind in the elastic
region are found from a known system of equations from
the theory of heat conduction and the theory of elasticity.
These equations differ from the usual by the additional
ternii ct.O.T in the expression for the generalized Hooke 's
law. In this case only mathematical difficulties are en-
countered, which however limit the possibility of obtain-
ing exact solutions in practice.
There exist approximate methods of calculating the
thermoelastic stress [2, 3, 5, 14]. Methods for calculating
thermal stresses of the second kind have also been little
studied.
In reactor construction one often has to deal with
problems relating to cylindrical bodies of revolution:
housings, heat generating elements, and their casings.
In these cases in the absence of external forces the
thermoelastic stresses of the first kind are determined,
as is known, by the relations
E r2 a2
r2 b2 a2S aAT (Or dr
a
1
aAT (r) dr aA (r)) ;
a
b,_a, 3 ctAT (r) dr ?
a
(3)
? aA 7' (r) rdr) (4)
az + (5)
Ordinarily the largest stresses occur at the inner (r=a) or
outer (r=b) bounding surface [depending on the form of
the function AT(1)1 and equal
and
92
E
(UO)r v X
X (9
b2_,72 aAT(r) dr ?aAT (a)) ;
U
(e)1.--b= 1?v X
b2 I S aA 7' (r) r dr ? aA 7' (b)
a
(6)
Thermoelastic stresses of the first kind in a thin plate
with built-in edges or temperature field symmetric with
respect to the mean surface may be found from the formu-
la
+6
1= 1?E v ( 216 aA7, (x) ? aA T (x)) . (7)
?6
The first terms included in the parentheses in formulas
(6) and (7) represent the mean (with respect to cross sec-
tion) temperature difference or, more accurately, the
mean value of the free thermal expansion aAT.
Formulas (6) and (7) may be combined in the rela-
tion
a = 1?Ev (aA7' ? aA T), (8)
which permits one to find the greatest stresses in a circu-
lar rod, thin-walled tube, in a plate with built-in edges
with symmetric temperature distribution, and in certain
other cases, when the principal deformations at each
point are equal among themselves, or some of them are
equal to zero (linear and plane stressed states) and more-
over, are constant in some principal plane.?Actually
under these conditions the relative stretching in the plane
indicated may be determined by the formula
a (1?CV)
E = aAT,
where cis equal to 0, 1, or 2 for the one-dimensional, two -
dimensional, or volume stress statearespectively. Integra -
ting over the entire cross section of the body in this plane
(sF =l?Ecv 1:TdF aAT dF)
and using the equilibrium condition
a dF
we find that e = aAT dF = aA T , and, finally,
we obtain the relation [8]:
a = 1_ cv (aAT ? aAT).
In the cases examined, by virtue of the linearity of the
heat conduction equations, the temperature distribution,
and consequently the thermoelastic stresses of the first
kind,rnay be represented in the form of a sum of a solu-
tion to the homogeneous equation (without internal heat
sources) with the actual boundary conditions (index "AT")
and the solution to the heat conduction equation
*These results for thermoelastic stresses of the first kind
may be generalized to the case of variable a(r) by
replacing the quantity aAT by the quantity A (aT).
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with internal heat sources but zero boundary conditions
(index "q"). Each of these solutions in turn may be
written in the form of the product of three fact/ors, express-
ing respectively the influence of the physical properties,
the density of heat generation, and the dimensions ( or
AT bdy) and shape of the body. Hence we have
a = .+ 0, AT r aE 1 r gra ,
L v ii Gqm 4
[aE
1?v [ladl Taer
The factor [aE/( 1? v )]( 1A) conditionally expresses
the influence of the physical properties. Introducing the ratio
giciT' we obtain the factor [aE/( 1?v)]( 1/X T), condition-
ally characterizing the influence of the physical proper-
ties of the body, taking into consideration also the margin
in attaining the yield stress.
For structural elements in the active zone, where
the heat is generated by the absorption of energy from
y rays and neutrons, the complex of physical properties
(first factor) will depend as well on the corresponding
cross sections or coefficients of absorption. Neglecting
the self-screening and the heat generation from the ab-
sorption of neutron energy, we find that the first factor
is proportional to the mean coefficient of y -ray absorp-
tion or (for elements with moderate atomic weight) the
specific weight; i. e. ,the expression [aE/(1? v))( 1A) may
depend on the expression [ccE/(1? v)/y/ X).
When using materials with high a and low X and
a Tit is especially difficult to avoid going beyond the
yield point and the resulting residual deformations. In
this connection uranium and stainless steel possess undesir-
able properties. Thorium, black lead, and to a lesser
degree zirconium and aluminum are better behaved as
regards the appearance of permanent deformation, not-
withstanding their comparatively low a B and T. Even
if economical considerations and estimates as to the re-
sistance of the material to radiation, corrosion, etc., are
not entered into, still the estimates and comparisons of
different materials as to their resistance to thermal stress
are very complex and conditional; in the corresponding
complex coefficients there should enter characteristics
of durability, which for many plastic materials,worked
under conditions of thermal fatigue, are still unclear.
The influence of the quantity aT,introduced into the set
of coefficients, is not unique, since an increase in a T
may cause harmful (later release of thermal stresses
of plastic deformation), as well as useful effects (decrease
in the accumulated plastic deformations)[12].
The comparison of materials is still further compli-
cated in that many properties (especially aT, 6 , aB
and others) strongly depend on the working and structure
of the material.
Comparison of HGE of different forms
In order to have a dimensional relationship to charac-
terize the HGE, it is useful to require for all forms consi-
dered that they have equal volumes per unit heat-transfer
surface. This guarantees their approximate equivalence
as regards neutron physical calculations with identical
thermal conditions at the surface (for equal volume densi-
ties of heat generation q inside the HGE), i.e., among
comparable forms, ro =2V
HGE/Feidem.
Formulas are given below for the greatest tempera-
ture drop and for the high-temperature elastic stresses of
the first kind for four basic shapes for the cross sections
of the heat generating elements (no account taken of the
casing, and for uniform heat generation). For,-,conciseness,
the temperature drop qii/ 4X at the cylinder radius rt,
is denoted by ATo, and the maximal thermoelastic stress
[aE/(1?v)](AT0/ 2)in the solid cylinder is denoted by at,.
The expressions introduced below are obtained by
substituting into relation (8) the solution of the equation
of steady heat flow (? XAT=q) for suitable boundary condi-
tions?zero or prescribed values ATbdy (for a derivation
of the most complicated case, the third, see the Appendix).
Case 1. For a tube or cylinder cooled from the out-
side,
Arrnax = A TAW(1)t (an) 111(1)
- AT r-=-h, ? 0 ?
Case 2. For a tube cooled from the inside,
ATmax= A Tor.i4.4; (cre)1,-,a = a 04%2 4) ?
Case 3. For a tube cooled from the inside and the
outside (in this case the maximum temperature difference
is nonlinear relative to ATbdy),
AT = AT 1?~2Q ( Q1 ~2 )
max o _02
where
R2
2
-;t,-
r lbdy(i + Q2 _ 1
In Q2 1_ ATo
and R is the radius of the circle (within the limits of the
tube's wall thickness a