SCIENTIFIC ABSTRACT BRODACKI, Z. - BRODER, D. L.

• Document Type: CREST
• Collection: Scientific Abstracts
• Document Number (FOIA) /ESDN (CREST): CIA-RDP86-00513R000306930003-7
• Release Decision: RIF
• Original Classification: S
• Document Page Count: 100
• Document Creation Date: November 2, 2016
• Document Release Date: June 9, 2000
• Sequence Number: 3
• Publication Date: December 31, 1967
• Content Type: SCIENCEAB

Chamical Abst.

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, cm
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Har. 25. 1954
Hapive T)D. 5, 311-
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AUTHOR;
TITLEs
P/008/62/000/005/003/003
D265/D308
Brodacki, Zdzislaw, ErWineer
Aircraft valves
-PE-RIODICALt Technika lotnicza, no- 5, 1962, 144 - 146
TEXTs Sectional drawings and description are given of
the following hydraulic and pneumatic values: gaBOlone-delivery
valve working at 0-5 kg/cm2 for quick out-'off of fuel delivery;
fuel injection pump used for starting where vacuum of 80 mm, Hg
is
produced for sucking in the fuel and then ejecting it into cylin-
ders and air control valve working at 50 kg/cm2 for controlling
the flaps during the flight. There are 9 figures.
Card 1/1

117 V
TRANMUSSION
"Remote Sigz2alization and Remote Control over Radio
Relay Lines", by
N.V. Brodakiy, V.V. Petrov, G.D. Novspasskiy, and
V.F. Zatsepin,
osvyaz
Elekt~r ) No 8) August 1957, PP 26-31-
Rrief presentation of the fundamental principles of
the construction
of a:atomation, remote-control, and
remote-signalization circuits for
the :presently designed radio R-60 and "Vesna",
relay lines with a num-
ber of trunks up to 2.5. The operation of the relay
remote-control and
remate-signalization circuits in the -in and
intermediate stations is
analyzed.
Card 1/1 - 56 -

BRODACKI, Zdzislaw, inz.
Aeronautical valves. Techn lotn 17 no.5:144-145 YV
'62.

BRODAN, J.
Bxperiences with the treatment of the perianal,
Memorrhoidal
comples by injections. Cook. dorm. 25
no,7-8:271-273 July
1950. (CIM1 20:1)
1. Of the Tirst Dernato-Veneroological Clinic in
Prague (Read
--Prof. 1. Gawalowski, M. D.).

eIZOID-A#J, VCADIIALe--~,
SURN.C-2, Gi*;on G9
Cour'k-'-'Y: C7r:clrlinslovallcia
Academe Dogroes: 1.1,D
I,,t=aj-p~tp ~rtmen~tof b011cres Irstitute for People's Health
(Interni oddel
-6T,,.Z) Chief.Dr. F. MN~ EMBEEK
SourOI:Prague, Pralkticlky Le'kar, Vol 41, No 15-16) Aug 21, 1961;
I)p 694-696
a"t" "Scme Czinen o-.1 Peroral Poisoning vith the Cleaning Fluid
Cikali Mixture of
trichlorethylene and tetraebloroethylene/.'
GOO 981643

BRODAN,V.; MAREK,I.; h'UHN,E.
A mathematical evaluation of oxygen consumption during
physical
exercise and recovery. Physiol. Bohemoslov. 14 no.W01-205
165.
1. Institute for Human Nutrition and Institute of
Mathematics,
Charles University, Prague.

BRODAN, V.; Technicka spoluprace CIHOVA: Z.
Determination of lactic acid in the blood serum
using a modified
Barker-Summerson method. Cesk. gastroent. vyz. 19
no-5:313-318
i1 165.
1. Ustav pro vyzkum vyzivu lidu v Praze (reditel
prof. dr. J.
Masek, dr. Sc.).

BRODAV, V.
Physical fitness tests in man. Cesk. gastroent.
vyz. 19 no.6:
376-383 S 165.
1. Ustav pro vyzkum vyzivy lidu v Praze (reditel
prof. dr.
J. Masek, DrSc.).

SOURCE CODE t - CZMM/65/007/003/0268/0268
AUTHOR: Kuhn# Z*j-
OhG: Institute of Human Nutrition, PraM
TITLEs Facperimental procedures used in studies 6n
psychotropic-dru"nduced changes
in physical fitness ffhis paper was resented at the 7th Annual
PsychoRharmacologi
Meeting, jesenikp 20-23 january, 196j
SOURCE: Activitas nervosa superior# vo 7p no, 3p 1965.. 268
TOPIC-TAG-S% biologic respiration, central nervous system, nervous
system drug, enzyme
ABSTRACT: -Indicators of physical exertion are described; their
-mocli-N-cation by psychotropic drugs Is discussed. The drugs calf I
facilitate enzymatic reactions, providing energy to the muscles#
the bod func-
~ ro
decrease fitness by affectipg.respiration ar o y
~tlons, or affect the CNS.'-'Lorig.- art. in En&j/---'ZJPBSj
SUB CODE% 06/ Sum DATE: none/
Card 1/1

L 29466-66
ACC NRs A
SOURCE CODE:
AUTHOR: jtq4gn, V.;
CZ/0079/65/007/003/0270/0271
ORGs Institute of Human Nutritiona Fravue
TITLE: Effect of cy man ~T-his
_gloserine isomers on physical fitness in paper was
r
esented at the 7th Annual EUchopharmacological Meetingt jesenik,
20-23 january
p
196g
SOURCE: Activitas nervosa superior, v. 7, no. 3, 1965, 270-271
TOPIC TAGS; biochemistry, pharmacology, man, biologic metabolism,
human physiology
ABSTRAM Cycloserine (m) isomers affect physical performance
~in different ways. d-CS has an excitory effect similar to some
narcotic drurs. 1 and dl increase absolutely and relatively
,the anaerobic component of energy turnover. The 1 Isomer also
increases the level of pyruvic acid. No phamaeodynamic effect
on circulation and respiration was found. The somers act
C3rolrig. art. in
mainly on the metabolism. Orig. art. has: 1 table. L Ent3
SUB CODE: 06/ SUBM DATE: none/ ORIG REF% 005/ OTH REF: 005
1 /1 Al

Physiology
CZLCHOSLOVARIA
KUHN, E.; STRIBRNA, J.; BRODAN V.; SCHUCK, 0.; Institute
for
Human Nutrition (Ust P-:ri- ~z u)
yz Z~~-Vyzivy Lidu) Prague, Director
av
(Reditel) Prof Dr J. 14ASEK; Research Institute of
Mcperimental
Therapy (Vyz1mmny Ustav Experinentalni Terapie), PrE)gue,
Direc-
tor (Reditel) Prof Dr 0. SMAHEL.
"Renal Response to a Water Load in Subjects on a Low
Sodium Diet."
PraQue, Casonis Lekaru Ceskyc , Vol 105, No W~, 4 Nov 66,
p 1209
Abstract: In people with Na depletion water load is
eliminated at
a slowe'rF rate than in normal people. Experiments on 8
men aged
21 to 46 years showed that the maximum minute diuresis is
lowered
when Na is lowered; the total amount of excreted water
also decreas-
es; the concentration index of endogenous creatinim is
hiRher at
reduced Na; osmolar clearance of Na and C11 is reduced; no
change
in the elimination of NH and K v~as observed , acid
content in-
creased; excretion of wader is lowered when excretion of
solutes
is lowered; Na resorption takes place at an increased
ratio of C11
to Na. I Table, 2 Western references.
1/1

T
CZEC-.-.C)SLOVAXIA
BRODA11,M11A, 1,11.; HOENILGj IT. BRODn~T VALEX, J.;
KTITTI-M, E. ; Lab -
oratory of Pathcbhysiolor, om"Ro~odFormation and of
Liver Dis-
Z71Y
eases at the ls~ internal Clinic, Faculty of General
iledicine,
Charles University (Laborator pro Patofyziologii
Krvetvorby a
Ja-uer pri 1. Interni Klinico F-ak. Vseob. Lek. IM),
Prague, Head
(Prednosta) Prof Dr V. HOENTIG; institute of Human
Nutrition (Us-
tav pro Vyzivu Lidu),' Prague - Kre, Director (Reditel)
Prof Dr
J. I-Iks E:-,L.
"Influence of Des'Lerrioxanine B or, Blood Sugar Curves."
--Ira-ue, Casopis Lekaru Ceskyc , Vol 105, No 45, 11 Nov
'06, pp
I
123~ - 1236
Abstract: Peroral glycenic curves a.-i"Ler an
application of Des-
fer-ioxamine B are lower than witihout ttie
apnilication. A`ei,
-L u
intravenous adi-Anist-ration of glucose Desferrioxa-mine
B causes
a significant shortening of the tine required for
disappearance.
;-'he resulting plasmati-a clearance of glucose is
increased. It
0
is not cortain whether the fast disappearance is due to
glucose
absorption by the tissues, or its transformation in the
blood.

br\0913~1)0\)A"
S'J*.L-.'.*2, Given Nana3 013
Cour~"'T: Czl~,clnozlovakia
Acadwdc Degrees: XD
I-,,',-,-cx.nnI-2qR~rtmcnt of Okres Institute for PeopIcI5 Health
(Interni odde
Affiliation: --OUI,,Z) Chiaf.bi-.F. K&FIbERABEK
S our
ce Prague., P-akticlky Lekar, Vol 41, No 15-16p Aug 21, 1961; pp
694-696
Lk-Ital "Sc,-,c Cnnen of Peroral Poisoning with the Cleaning
Fiuia cikai /mixture of
tric'hlorethylene and tetrachloroethylene/1,
ZR02a,41,7017A Marie
Gpo 9s1643

-Z.,. ) D A I%II -N( N ~ G117
if--vel c;f p"lasim iron, copper and to-tual iron
binding capacity
of the serum. j-P --.hronic hepatopathi.es. Cas. lek.
cesk. 103
110-33:90-15-909 11, Ag It")4.
laborator pro patofyz1ologli ki-vetvar-by a jator pri
1 interni
klinice fakulty vseoliec-cho iEkarstvi Karlovy
Univers-ity v Fraze,
(prednosta prof. dr. V. Hoenig, D.-Sle.).

BRODANOVA, M.; RVA1011C, A.; MERU,, j
Level of serum iron and copper and total binding
capacity of the
serum for iron in relation Lo Lhe activity of
progressive
polyarthrIt4s. Cas. lek. cesk. 103 no-45:1242-1246 6 N
164.
1. 1 interni klinika fakulty vseobecneho lekarstvi
Karlovy
University v Praze a Vedeckovyzkumna laborator pro
patof~yziologii
krvetvorb,v a jater pri 1. interni klinice v Praze,
(prednosta
prof. dr. V. Hoenig, PrSc.) a Pevmatologicke oddeleni
fakultni
poliklinilky, Krajzk-,- stav Narodniho zdravi v Praze,
(vedouci
MUDr. V. liojriolec,

BRODANOYA,_LI.
Genealogical study of hemochromatosis. Acta univ.
Carol. [med]
(Praha): Suppl. 18: 205-21.1 164-
1. 1 Idemi -Iinika fakulty vgeobacneho lekarstvi
University
Karlovy v fraze (prednosta: prof. dr. V. Hoenig).

C ZEC , --HOSLONJ~'.X !A
110211IG V. - B.11"OD.LN, V. ; VALEM, J. ; MiTITIM, E. ;
Lab-
iolo- o' d of Liver Diu-
oratory oP 1`athcbhys ty I Blood Formation an
eases at the Ist Internal Clinic, .-Paculty ol' Goneral
!-:edicine,
Charles University (Laborator pro Patofyziologii
Krvetvorby a
jater ori I. Interni Klinico -Pak. Vsoob. Lek. ICU),
Prague, Head
(Prednosta) Prof Dr V. HOETIZIG; Institute of Human
Nutritu-ion (Us-
tav pro Vyzivu Lidu),' Prague - Krc, Director (Reditel)
Prof Dr
J. JiS EK.
"Influence of Desferrioxanine B on Blood Sugar Curves."
"'Ira-ue, CasoDis Lelcaru Cesicych, Vol 105, ',%To 45,
11 Nov '06, pp,
123 1236
Abstract: Peror-1 glyce-mic curvos a~`uer an application
of Des-
fer---iox ino B are lower than without the application.
Aftei,
intravenous acb-Anis'..-ration of glucose
Desferrioxamine B causes
a sig.nificant shorton-ing of the time required for
disappearance.
"Llhe rosultin- plasmatic clearance of [,-,lucose is
ircreased. It
is not cortain -.1hather the fast disappearance is due
to clucose,
absorption by the tisnues, or its transformation in the
blood.
I,Table, 11 Western, 3 Czech references.

BRODAR, S.
"The Otosim cave, a pal-olithic station." p. 203
(Razprave Dissertati-ones Vol. 1, 1951, Ljubljana.)
50-- -.,Ion'h1-;' Li3t of ""q.'qt.EurQprWLII ACCOLUI Vol. 2, INo. 9,
Library of Con~ro-s, 3?epte.~Ober
91a
953, Uncl.
1
5

BRODAP, S.
"Paleolith-L-C trz--c,-~s in the Posto-ina- - . 24-1
.1 i
(Razpravo Disscrtationes Vol. 1, 19-1, Ljji~bljrina)
SO: 11ton-Unly List of East Zurooean Accessions, Vol. 2, 11-4o. 9,
Library of Congress, Septe.-..-aer
1953, Uncl.

CATZGCRY
ABS- JOUR-
MIG,
IAMTRA(rL
RMdn,p Koo 5 1960s, So,
!9642
i3y-ism., 'fi. rind Srodarec, A.
-i-e Detef~tjor. of t~e Pre~~encu of Raffinate Pe an ii t.
i)ij jr, :Edible Dils -n.-I P..'per
Kenija u Industriji, 1, 1-1-2 (195~)
i,0 abstract.
CA

BRODAREC, A.; BRISKI, B.
Determination of arachis oil in edible oils by
partition chromatography
on filter paper. Pt. 2 (Conclusion) P. 93.
K&UJA U INDIJ5THIJI. (Drustvo kemicara-tehnologa NRH)
Zagreb, Yugoslavia.,
Vol. 7, no- 4,, Apr. 1958,
Monthly List of East European Accessions (EEAI) LC'
Vol. 8, M. 6,
June 195!~.
Uncl.

BRODAREC, Ivo, dr
Basic health'problems and development of public
health services.
Lijeen. vj~sn. 83 no.7:677-686 161. .
1. Iz Republickog.zavoda za zistitu zdrav1ja u
Zagrebu.
(PUBLIC HEALTIO

A -66 &rP(k)/M4P(W)/EWP(V) IM0 EM/W
L39923
ACC NRI AT6ol830O (4 W) SOURCE CODE: PO/2540/65/013/001/0001/0010
'AUTHOR: Brodacki.. Jo ef Brodatski Ye
ORG: none
TITLE: Elastic stresses in a thick-walled spherical container at
short-term inter'napr'essuire
SOURCE: Warsaw, Instytut Mechaniki Preoyzyjnej. Prace, v. 13,
no. 1(47). 1965* 1-10
TOPIC TAGS: elastic stress, differential equation,
012f5 Z; rcc k),j
Srxe!;~-,.j CZ.4571C, 0e.-0A-fn19r1'01V
ABSTRACT: Analytical formulas have been determined for elastic
stress
and deformations in a thick-walled spherical container under a
pulsed
internal pressure. On the basis of the dynamic equation of internal
equilibrium in the container wall and Hooke's law, the differential
equation of the radial displacement U(r,t), considered fundamental,
was derived. With the given load of the container,.appropriate
initia
C-,d UDC: 531.252.3:621.64:531-787
1/2

L 39923-60'
ACC NR- AT6018300
0
and boundary conditions were assumed. The entire procedure for
solving
the equation is given. The analytical formulas have been
obtained for
stresses and deformations by carrying out operations on the
function
U(r,t) according to the relationships determined between this
function
and deformations and stresses. A specific form of the arbitrary
function v(r,t), which appears in the formulas,,has been
proposed.
The functions y (r), y (r), and f(r,t), which are necessary for
calculating the coefficients, have been determined. The
conditions
for determining the proper values of parameter CJ-,, are given
Orig.
art. has: 2 figures and 49 formulas. [Based on author's
abst;act)
(NT)
SUB CODE:
20/ SUBM DATE: none/
ORIG RF.F: o06/ sov REF:
2/2

BRODECYI, A., inz.
An~lysi Itihe., activities of the Lodz Branch otthe
Printers'
tectionq o' the-'Association of Polish Mechanical
Engineers and
Tachnicia*n's., Pbl-igrafika 13 no.10:20-22. 0 161.
1. Sekretarz ZarmiLdu Sekaji Foligrafor

BRODECKI, Apolinary
Do the eponoraists of printing have nothing to
say about?
Foligrafika 14 no.2:22-13 F 162,

BROBECKI Apolinary, inz.
P
C- ,
Technological reading and its influenco upon the
level of
-professional qualitications. Poligrafika. 13
no.9:1-2 8 161.

BRODECKI, A., inz.
Plenary session.of the Executive Board of the 11pinters'
Section of the Association of Polish Mechanical
Engineers
and Technicians. Poligrafika 13 no.0:21-23 S 161.

KUBICKI, Roman, inz.; PEPSCIIYX,
VIECIA1111K, Marian, inz.;
Boleslaw
Jerzy, inz.; DOBCSZ, Stanislaw, inz.;
MIUJI-IGZUK, Mieczyslaw~~D_~,U...'
Two-sided raw material feedi-ng of rotational
clinker burning
furnaces. Gosp paliw 11 Special issue no.(95):ll Ja
163.
1. Cementownia, Chelm. ~

BRODECKY, Tadeas (Praha)
Portable equipment for truing packing surfaces of
steam boiler
manholes. EDergetika Cz 13 no.9003 S 163.

M.-S&

4

-1W
svmptoins oUthe actl

Akad;-~,
at func )n.

'Wilis 1953-N6, M-

chIoronApkiL

function ebang-es witblirZto
4. sn'Onths.--Deo~ I
n the

urem level of~tiui and W'blodd-sujO the
It Were Om"t I

- bwvabla symptows, -, Iti.later itagn;,the blood-mqmr -
st 0
I

Jevel agaln Increased. ; Othei.~hanja *ere lnc~eaic In the

cholesterol and.decreme In the ns=bk 'atld- mutent - of

BRODEIZI-17.-,
Sanitary and hygienic conditions in Nrniture workshops
of Riga which
use urea-formaldehyde glueso Vestis Iatv ak
no.1:135--d38 161.

USSR/Pliarrjacolo-"~-Y a-ad Toxicology - Toxicolo~,7. V-9
Abs Jour RQf 7',Aur - Biol.,, Yo 21, 1958, 986L>2
Author DroC~clc!, N.
Inst AS Iitvian SSR
Title 1;arly Sigas of the Chlorona)yatalcne Effect on taic
of t1liz, Liver.
Orig Pub : Izv. jUI LatvSM, 1955, iio 9, 31-85.
Abstract : It was established in c.,pQrimnts on rabbtis
that prolon-
3ce.. inIialation of chloronaplitnionc vapors (2-4 raconths)
lcads to an effect on livur Tunctions. In blood, Vho
c1hanges of the sugar and urca content are expressed
'n::)ovc
all. In early stages the: ayaoiuit of sugar in th-- blooc!
az:crcascs; in later onas it. increases* Lowering of urca
J-s observed in early sta'-C's. Lowering of sugar aad ur--a
in the blood my serve as an carly sign of liver function
Card 1/1 dicturbance. -- A.G. Pinuo
- 36 -

-BRODFJZ, N.
Sanitary and bygienic conditions in furniture workshops of
Riga using
urea-fornaldebyde glues. Vestis Latv ak no.1:135-138 161.
(EEU 10-9)
(Furniture) (Formaldebyde) (Urea)
(Glue) (Riga)

BRODELIS, ~~?,,Jprodelis, J. ]
Seven-year plan assignment carried out in five years.
Prof.-tekh.
obr. 20 no.12:4-5 D 163. . (MIRA 17:1)
1. Nachallnik Glavnogo upravleniya
profes6ionallno-tekhnicheskogo
obrazovaniya pri Sovete Ministrov Latviyskoy SSR.

BRODELIS, Ya. [Brodelis, J.]
Vocational and technical schools of the Latvian S.S.R.
in the
anniversary year. Prof.-tekh. obr. 22 no.7:6-7 J-1 165.
(MIRA 18:8)
1. Nachallnik Glavnogo upravleniya
professionallno-teldinicbeskogo
obrazovaniya pri Sovete Finistrov Latviyskov SSR.

pvr I)
27-11-5/31
AUTHOR: Brodelis, Ya., Chief of the Administration of Labor
Reserves
of the Latvian SSR
TITLE: The Schools of Latvia on the Rise (Uchilishoha Latvii na
pod"yeme)
PERIODICAL: Professionallno - Tekhnicheskoye Obrazovaniye, 1957,
# 11,
p 6-7 (USSR)
ABSTRACT: The article is a report of what has been done by the
Latvian
Schools of the Labor Reserve in connection with the 40th Anni-
versary of the October Revolution. They pledged to re-equip
16 school rooms, workshops and laboratories, to manufacture
the standard equipment f6r 25 school rooms, to modernize 20
metal-cutting machines and to introduce 28 improvement sug-
gestions. The Too "hnical School # 3 fulfilled its yearly plan
by 153.5 %, and the students of Art Trade School # 17 ex-
ceeded their year's plan in the manufacture of cupboards, chairs
and tables, of 142,000 rubles worth. Trade School # 7 made
overcoats, costumes and dresses worth almost 300,000 rubles,
exceeding by far the year's quota. The article mentions a
Card 1/2 number of other schools, including agricultural
mechanization

The Schools of Latvia on the Rise
schools and their achievements.
27-11-5/31
ASSOCIATION: The Latvian Republic- Administration of Labor
Reserves
(Latviyskoye respublikanskoye upravleniye trudovykh
rezervov)
AVAILABLE: Library of Congress
Card 2/2

BRMF,R J~-;

Modlatlon.of 2 c*. :A.

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*S
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CI th, ~3-
7,468

.
1. 325,:k 2 c -v. The energy or )-rays corre-spondil
.k

the conversio of ZrOI with a k-elizetroat to Cuts is 1122 S
n

Chemical Abstracts

e.kv.: e1fl4- (A-5 + 0-5) X 10 theno.ofconversion:
'
+

'

/-r was established with the belp
G
electrons). The ratio 0

Vol.
48. No~ 3

of the photoeffect, a pirce of Zn wire, activated by slow

Maro IOP
1954

neutiums and enclosed in 11b real Wing used wt n pholock-t-

'
'
0 !

.
Ngelear Phenomena

: 0.
Amn source; $
Pr - (3-
) X 10" oic :Z 0.9 &K . L:
iml - (1-5 + '0-2) X 10 4 which corresponds to a MI

transition type.
The #+-decay of Zn" leads to the ground
*
't

Oft

. The -r line is emitted when Zn9s is transformed
statrofCu
'

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into an excited7state 1122 e.kv.
nf Cu". P for the transition
'

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j-

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to the ground statr
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2
I(P
h
d
f

state o
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.
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e groun
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excited state ~5/2. ITM can have transitions to the 1122-

e.kv.
level%of CUO and. to a-12nd higbrr level, 1440 e.k-%--

-cral facts
remain,routradictory. S. P.

AUTHOR: Broder, D.L. 89-7-1V32
TITLE: On the Reduction of Neutron Currents in Chalybeate
Mixtures
(Oslableniye potokov neytronov v zhelezovoanyk,, smesyakh)
PERIODICAL: Atounaya Energiya, 957, Vol. 3, Nr 7, P 55 OSSR)
ABSTRACT: The author measured the relaxation length of fast
neutrons de-
pendent on the concentration of iron in water. The nuclear
re-
actions ],)(d,n)He3 (energy of the neutrons Eo = 4.0 + 0.2
Mev) and
T(d,n)He4 (energy of the neutrons Eo = 14.9 � 0.4. If-eV)
served as
sources for t e neutrons. The dimensions of the sources did
not
exceed 0-7 cm - At the reaction D(d,n)He3 the maximum values
of
the deuteron current amounted to 30 microamperes and at the
reaction
T(d n)He4 to 12 microamperes. Furthermore, a Po-Be neutron
source
in form of a cylinder of 6 mm diameter and '220 mm height
was used.
The chalybeate mixtures consisted of fittings of 6Ox6O =2
large
steel packets in a water mixture. By variation of the
thickness of
the steel packets at a constant water interspace the
concentration
of the iron in the water couldbe varied. TIds water vessel
on its
part was surrounded by protective vessels filled with water
and
Card 1/2 paraffin. Impulse-ionization-chamberes Trith a
layer of the fission

On the Reduction of Neutron Currents in Chalybeate Mixtures
89-7-14/32
material were used as neutron detectors. The thermal
neutrons
were recorded in a chamber with enriched uranium, and the
fast
neutrons in a chamber with Th232. The measured dependence
of the
relaxation length of the neutrons of the above mentioned
sources
on the concentrations of the iron in water is illmstrated
by a dia-
gram. The relaxation lengths were computed of the curves of
reduc-
tion of the currents of fast and slow neutrons for
distances of
from 10 to 15 free lengths of path. The relaxation length
of the
fast neutrons decreases at the sources of neutrons with Eo
= 14-9
MeV and at the Po-Be source with an increazing
concentration of
iron in water, but the relaxation length of the therinal
neutrons
produced by slowing down the fast neutrons has a minimum at
a con-
centration of about 60% of iron (with respect -to volxune).
There is
1 figure.
SMMITTED: March 7, 1957
AVAILABLE: Library of Congress
Card 2/2 1. Neutron capture-Test results 2. Neutron capture-
Equipment 3- Neutron capture-Theory 11. Nuclear
reactions-Applications 5. Neutron detectors-Applica-
tions 6. Neutron capture-Effects of iron in water

21(4) PHASX I BOOK EXPLOITATION 3OV/2583

.

International Conference on the Peaceful
Uses or Atomic Zng*rgy.

2nd, Geneva, 1958.

Doldady sovetakikh uohonykh; yadarnyys
reaktory L yadern&Ya an*r-

gettka. (*spo
rts
of Soviet Scientists; Nuclear Reactors and
less Itar
0
(So

Nuclear JPower)
?rady, "1. 2)
r
7 P.
Moscow, Atomizdate 1959. 7
Rrrata allp Inserted. U,000 copies
printed.

general Zda.v N.A. Dolloxhal,
Corresponding Member, USSR Academy Of

Sclono*op A.F. Kraminp Doctor of Physical
and Mathematical Sclonossr

A.Z. Loypunakly,
Member, Ukrainian SSR Academy Of Soleness,
X.I.

MovLk*v, Corresponding Member, USSR
Academy or Sclonasso and V.S.

PUrsov#
Doctor of Physical and Mathematical
Sciences; Rd.z A.?.

Alyablywvj Tech. X4.x
To. 1. Memel-.

PURP0SZz This book Is
Intended ror scientists and engineers
engaged

In reactor designing, as wall as
for professore and students of

klghor
technical, schools where reactor design Is
taught.

vo~%PV-0momod "Iwo Or.& eix~volvmo
actuation ca the P--ftt

o
a *n orgy. The six vol umes contain the
reports pro-

@anted by Soviet so lOntists
at the Second International Conference

an
Peaceful uses or Atomic Rnorgy, hold front
September I to 13,

190 In Geneva. Volume 2
conslats or thme parts. The first 12

dew
tod to atoolo power Plants under
construction in the Soviet

Volonj the
second to experimental and research
reactors, the ex-

POrlmonts carried out on
themp and the Work to Improve them; and

tJ&S thirdo which to Predominantly
theoretical, to problems of

nuclear reactor
physics and construction ongingering. To.
1.

lbrY&kln Is the science editor or this
volume. Sao SOV/2081

for titles Of All
volumes of the oat. Referenz,48 appear at
the

T.I[_* V.S. Dlkxr*v, X.B. Togizamvp and
To. S. SaltykOv.
Mostovoy

,
measuring Neutron Spectra In Uranium Water
Lattices (Report 546

$0. 2152)

A.Z., B-0.
DubOysldY* M-N- Lantmov, TU.Tu. Glazkov,
trasin

,
R.K. Goncharov, A.V. Kamayev, L.A.
Geranovs, V.V. VSTIl0V,

1. InyutLn, and
A.T. Senchankov. Studying the Physical.
To

.
CharaoterLstlas of & gor7illum-maderator
Reactor (Report No.
55
5

-
,
2L46)

~"I.p A.D_ S.A. Namirovskaya, A.?.
Rudlk# Yu. 0. Abov, V.P.

iment an an Zxperl-
bolkla, and P.A. Krupchit kly. Critical Ez
"

(Report No. 2036 570
mental Beavy~wster Reacto
r

Marchukp G.I.p V. To. ftpkos To. 1.
Pogudal1n&p.V.V. 3=lovp

X.P. Tyutorev, B.T.
Platonova, and 0.1. Druzhinina- Certain
Pro-

bless in Nuclear Reactor Fhysics and
Methods of Calculating

Them (Report No.
2151) 588

Sinyutin, G.V. and V.X. Stmonov.
Determination of Control Rod

Iffectiveness
in a Cylindrical Reactor (Report So. 2469)
613

Gel-fand, I.N., S.M. ftynberg, A.S.
Frolov. and N.M. Chentsov.

going the Monte
Carlo Method or Random Sampling for
Solving the

Kinetic Squation (Report No.
2141) 628

Laletin, 9.1. Neutron
Distribution in a Heterogeneous Redlum

.
* port No. 2189) 634

klyv N.V.# A.V.
Stepanov, and F.L. Shapiro. Neutron
FALxmLrnov

Ther-11 stion and Diffusion in
Heavy Media (Report No. 2148) 651
:

Taynlkp A.Z.p V.S. YermAlcov, and A.V.
Lykov. Using the Onsager

Theory for
Studying Neutron Diffusion in the
Absorbing Media of

a. 2224)
Waclear Reactors (Report N

3.A. Markin,
A.A. Eutuzov, V.V. Lorin, and
ft2"r_jj"

_
T-.V. orlov. studying the Spatial and
Znorgy Distribution or

Neutrons in
Different media (Report No. 2147) 674

ftitriyev A B. Boron ronization Chambers
for Work In Nuclear
;-
2084) 690
t N
I

o.
Or
RO
Reactors

r2rillin, V.A., and 3.A. Ulybin.
Experimental Determination of

specific
volumes of 111*&77 Water in a Wide
Temperature and ft-es-

Range (Report No.
24T1) 696

21(8)t2l(7)
AUTHORS:
TITLE:
PERIODICAL:
ABSTRACT:
Card 1/3
Broder, D. L., Kutuzovq A. Aeq BOV/89-6-5-19/33
_ro_n-d`ra-kio_v, A. P.
The Dependence of the Removal Cr6se Sections of H2 Ot B 409
C, Fep Pb on the Energy of Neutrons (zavisimost, secheniy
vyvedeniya H 0, B C, C, Fe, Pb ot energii neytronov)
2 4
Atomnaya energiya, 1959,.vol 6. Nr 59 pp 578-581 (USSR)
By means of the removal cross section it is comparatively
easy to calculate a shield consisting of a mixture of water
and various elements. The-removal cross sections were
measured .for 4 and 14-9 Mev neutrons (D(d,n)He3 and T(d,n)He4~-
reactions), for which purpose not water but boron carbide
was used as the principal component. The measuring apparatus
consisted of 3 cylindrical tanks (diameter 100 omt thickness
in the direction of the deuteron beam 115 cm). The first
was filled with boron carbide (1.1 g/cm3)' which contained
the neutron source in a special channel. A second and a
third tank were connected with the first. During removal
cross section measurement the material to be investigated

The Dependence-of the Removal Cross Sections of
SOV/89-6-5-19/33
H20, 3 4C, C, Fe, Pb on the Energy of Neutrons
took the place of the third tank. The fiselon chambers, which
contain Th 232 p are used as neutron detectors in a number of
channels provided for this purpose. The channels not in use
are enclosed in aluminum shells which are filled with boron
carbide. The material to be investigated is filled into boxes
(cross section 71-100 cm) of 9 cm thickness. The thickness of
the lead plates is, however, 9 and 18 om respectively.
Measuring results:
material
density
removal
cross section

9/cm3
E
0 4 Mev
E
- 14.9 Nev

n
n
.H20
1
0.165�0.008
0.084+0-004
B4C
1.67
0-083�0-003')
0-05~-+0-002+)
Fe
7.83
o.169�o.007
0.137.t0.005
Pb
11-3
0-113�0-005
0-097�0-0.05
+) from removal cross secti

on measurements fo
r
boron carbide
Card 2/3 and graphite,
corresponding
to the
reciprocal
relaxation

The Dependence of the Removal Cross Sections of
SOV/89-6-5-19/33
H~O' B4C, 0, Fe, Pb on the Energy of Neutrons
lengths at such distanoesp which correspond to 8-15 free
lengths of paths of neutrons in B 4C and C. The results ob-
tained are compared with those of 5 other publications
(table and diagrams), and satisfactory agreement was found.
The method of removal cross sections may be extended also to
calculation of fast neutron distribution in materials con-
taining other light elements instead of hydrogen.
Professor A. K. Krasin and Candidate of Physico-mathematical
Sciences V. V. Orlov acted as advisers. Go No Deryaging
No 1. DAdkint A. P. Klimov, V. Go Liforov, Z. So Blistanova,
A. I. Chusov, and V. S..Tarasenko assisted in experimental
work. There are 2 figuresp I table, and 7 references,4 Of
which ate Soviet.
SUBMITTED: January 21, 1959
Card 3/3

21M
AUTHORS:
TITLE:
PERIODICAL:
ABSTRACT:
Card 1/2
SOY/89-7-3-17/29
Androsenko, A. L., Brod?r,, D. L., Lashuk, A. 1.
Gamma-Rays Aocompanying the Inelastic Scattering of Neutrons
With Energies of 3 Mev
Atomnaya energiya, 1959, Vol 7, Nr 3v pp 268-271 (USSR)
By means of a I-scintillation spectrometer the energies of
y-rays were measured which are produced when 3 Mev neutrons
are scattered inelastically on titanium, bromine, strontium,
iodine, barium, tungsten, iridium, and bismut For the pro-
duction of the neutrons the reaction D(d,n)*-was used
(the neutrons were aceeleratel up to 200 kev). The neutron
source had an intensity of 10 n/sec. The crystal NaJ(Tl) with
a diameter and a height of 40 mm was shielded against the
y-radiation of the accelerator, together with the correspond-
ing light pipe and multiplierp by means of a strong lead cone.
In order to reduce the influence of the neutrons scattered
on the walls of the chamber, the entire measuring apparatus
was suspended by nylon threads, so that it hovered freely in
the middle of the room. The elements under investigation were
produced in form of rings from full material, and the rings
themselves were placed over the crystal during measurement.
The multiplier was connected with a 128-channel amplitude

SOV/89-7-3-,17/29
Gamma-Rays Accompanying the Inelastic Scattering of Neutrons
With Energies
of 3 Mev analyzer and a ferrite accumulator. The energy
rppolution of
the spectrometer in the case of the y-rays of Zn'--l amounted
to about 10%. The constancy of the neutron flux was checked
by means of a boron counter. The measuring results are recorl-
ed partly graphically, and partly by tables, a number of new,
hitherto unknown y-lines being found especially in the ease
of titanium ` strontium, iridium and bismuth, A. K, Krasin
showed constant interest in this work and assisted in building
up the experimental arrangement. A. N. Serbinov took part in
the experiments. The results were discuesed with 1, 1. Bonda-
renko and V. V. Stavinskiy. There are 4 figures, 1 table,
and 4 references.
SUBMITTED: January 6, 1959
Card 2/2

21 (8)
AUTHORS. Broder, D. L.p Kutuzov, A. A., Levin, SOV/89-7-4-1/28
V . V . , TYMM," V. V. Tarusova, A. V.
TITLE: The Passage of Fast Nbutrons Through Lead and Iron
PERIODICAL: Atomnaya energiya, 19599 Vol 7P Nr 4P PP 313-320
(USSR)
ABSTRACT: The present paper gives the results obtained by
measuring the
spatial distribution of fast neutrons (originating' from
monoenergatic neutrons of the energy E = 4 Mev and E . 14-9 NaO
and of neutrons of atomic reactora in Iron and,lead. krat,
the experimental arrangements are discussed. The reactor of
the Pervaya atomaya 61ektrostantsiya (First Atomic Power
Plant)p an experimental nuclear reactor of the VVR type with
ordinary.water and enriched uraniump and a neutron generator
were used as neutron sources. The spatial distribution of
neutrons in iron and lead was measured by means of a neutron
generator, a neutron detector, and D- and T-targets. A
Th 232_fission chamber and threshold indicators flAl 2'(n, p)Mg2,
P31(n,p)Si3l , and S32 (n,p)P 32 ) were used as detectors. The
distribution of thermal and epithermal neutrons was measured
Card 1/3

The Passage of Fast Neutrons.Through Lead and Ir6h
BOV/89-7-4-1/28
by means of a U 235_fission chamber. The results of these
measurements in iron and lead are shown by 4 diagrams. The
authors then theoretically investigate an infinite homogeneous
medium in which an unbounded, DIans isotropic source of mono-
energetic neutrons with the energy Eo is located. Neglecting
the moderation of neutrons in elastic scattering, the kinetic
equation for the neutron collision density y(F,B) is written
down. The inelastic scattering is here assumed to be isotropic.
The aforementioned equation is then transformed '~y means of a
Fourier transformation, and is solved by employing the method
of spherical harmonies. The calculation is then followed step
by step, and the asymptotic solution is explicitly written
down-A for=la is written down for the neutroA flux with the
energy-E in a medium with point source. The results shown by
some diagrams for iron agree well with the experiment. The
same also applies to the results for lead. The computation
method suggested makes it possible, if the differential cross
sect" of elastic and inelastic scattering of neutrons a
iav 17
sufficiently well known, to determine the spatial- and energy
distribution of neutrons in thick layers of matter having
Card 2/3 comparatively high nuclear charge numbers (e.g.
greater than 56)

The Paccage of Faut Neutrons Through Liad and Iron
SOV/89-7-4-1/28
vdth sufficient accuracy. At large distances from the source,
the neutron speotram is enriched with considerably sl(nved-
down nentrons. If the energy distribixtion is known, the
shield
may be calculated accordirg to the multigrouP theory. The
authors thank Professor A. K. Krasin, Candidate of Technical
Sciences A. N. Serbinovv and the saientific co-worker
V. A. Romanov for their constant interest in the present
paper a-ad for their collaboration in the experiment. Besides,
the authors thank V..G. Liforov, Z. S. Blistanov, and V. S.
Tarasenko for their assistance in the experiments. S. A.
Kurkin assisted'in working o1A the calculation method, and
M. B. Yegiazavov, V. S. Dikarev, V. G. Madeyev, Ye. N.
Korolev,
and N. S. 111inaiiy further took part in the experiments.
There are 9 fig-area and 14 references, 4 of which are Soviet.
SUBMITTED: January 21, 1959
Card 3/3

21-1310
77216
SOV/89-8-1-10/29
AUTHORS: Broder, D. L., Kondrashov, A.. P., Kutuzov, A. A.,
TITLE: Effect of Layers Containing Boron on the Yield of
Secondary Gamma Radiation. Letter, to the Editor,
PERIODICAL: Atomnaya energiya, 1960, Vol 8, Nr 1, PP 119-51
(USSR)
ABSTRACT-. Since in most cases the size and shape of the reactor
shielding Is detennined by the amount of hard secondary
gamma radiation, the authors investigated the pos-
sibility of reducing this amount by capturing In boron
carbide the thermal neutrons producing the radiation.
Ne~itrons captured in boron cause soft "/,-rays of
approximately 0.5 mev, while neutrons captured in
other building materials, particularly steel,' prod
duce high energyv Z-radiation. The geometry of the
experiment is gi e in Fig. 1.
Card 1/9

Effect of Layers Containing Boronon
the Yield of Secondary Gamma Radiation.
Letter to the Editor

WON,

I rI

CA

/// a
Z IZZZA

~3 z.4 re.)

-t-n 44 M on

77216
sov/89-8-1-io/29
Fig. 1. Geometry of the experiment.
Card 2/9

ECI*ect of Layers Containing Boron on 772:L6
the Yield of Secondary Gamona Radiation. SOVdq-8-1-10/29
Letter to the Editor
The cross section of tbe Prism was 710 x 710 and
the steels under Inveotigation weve St-3 and stainless
steel IKII18N9T. The Po- CL - Be L3ource- of 2-167
neutrons/see strength was located 1n the water shield-
ing-in front of steel. Both the steel and plexiglas
(lucite) had channels for indicator probes. Neutron
distribution was determined using circular foils of
indium 20 mm in diameter, enclosed sometImes In cadium
containers. Figure 2 shows the neutron distribution
in steel St-3.
Card 3/9

Effect of Layers Containing Boron on
the Yield of Secondary Gamma Radiation.
Letter to the Editor
77216
SOV/89-8-1-10/29

CV

P

Card ~/9 Fig. 2. See Card 5/9 for caption
-Z3

E,Cfect of I;qero Contall-lin-, Boron DfI
th.,~ Yield of Secondary Gaiiuna Radiation.
Letter to the Editor
See Card 4/~9 f or Fig. 2.
113 011,,48 8 - 1 - 10/2 9
Fig. 2. Spacial distribution or neutrons in St-3
steel and plexiglas, (lucite) prlsm: (1) Indium
measurements (no B)C layer); (2 measurements with
Indium in cadmium ~no BIC layers; (3) indlum
measurementn (between sveel and plexlfrlaoo i.-, placed
a layer of B 4C 20 mm thick and of' density 1.1 gm,/cm3);
(11) measurements with Indium in cadmium (between steel
and plexiglas is placed a layer of B),C 20 mm thick
and of density 1.1 gpi/CM3
Spectrum of X-rays was meaSUred by means of a'NaJ(TI)
single-crystal -/-spectrometer. The diameter and
height of the crystal were 110 mm. Resolving power for
the Zn65 line was 11%. The analysis of impulses Was
Card 5/9 performed by means of a 128-chanriel amplitude
analyzer

Effect of Layers Containing Boron on 772:L6
the Yield of Secondary Gamma Radiation. sov/89-8-i-io/29
Letter to the Editor
with ferrite core memory. Figure 3 and 4 show the
measured -/-spectra.

60
23

1.6

J~ 50

40

4!

%
e

4- 70

Card 6/9 0
10 10 M t

o

W-T
o d
o v too It

o v
o

n
u- bee

Fig. 3. Spectrum of 7-quanta
produced In the St-3 steel
prismi (1) No B4C layer; (2)
between steel and plexiglas
(lucite) Is placed a layer
of B C, 20 iron thick and
4
3
density 1.1 gm/cm

E i.'fe c tof* I;uyerj Coi-itainin-'r Borun wi
E.")
the Yield of Secondary Garmna Radiation. SOV16')-8-1-10129
Letter to the Editor
-6 Fig. 11. Spectrum of '/-qU.'11_1ta
0
produced in a priL;m froiP. stain-
__r less steel IKhl8N9T. (1) No
Bj,C layur; (2,)1) between 3teel
and plexlL~Iao lo placed a layer
of B4 C (alternative II, Fig. 1),
or a composite section with
plexiglas, St-3 and B C (alter-
native IV, Fig. 1); ffi between
steel and plexiglas is placed
a layer of plexiglas and a
ayer of A C(alternative III,
Fig. 1).
W Jo to so W 70 00 Ju twou fro 110 &V

23 me
11

if

7.6
Ili
&V

-

Card 7/9

Effect of layers Containing Boron on -(7216
the Yield of Secondary Gaquna Radiatioa. SOV/89-8-1-10/29
Letter to the Editor
In the ~.Iasu oV i"he St-3 !jteel, the Intensity o!' the
7.6 mev 7--vais is rekl.iced.13.41 times. In the case
of the .3teel 1KI-118t.19T -Uhe red-iction for the zarne
energy Is 'r.8 t1me~o. This oteel contaln3 clivomi,,ull
and IlIckel, and prod~ice;~ iome aiditional '/-lilies.
The autho.-s calculated the decrease of thd neutron
capture of 7- radlations from St-3 after Introduction
of the boroii carbide between the steel and plexiglas,
using the measured neatron distribution from Fig. 2.
The spectriuii of neutrons in steel used in this cal-
culation wao determined approxiiiiatin.- a half-infinite
steel block with an absolutely "black" middle boundary.
Corrections were made for tile Self-shielding of the
detectors at the T.W.1 ev re~,-,onarice. The computed
d(--!crease of :." e coridary 7-(IuMIta at' (':).5 tinies io
in
Zood a,-Poemerit with the eXI)O"I'llont oil St-3. N . A.
Alez;hli~, V. S. Borisov, f;. V. ]-~)rkov, and E. V.
SheStOpalOV W-_~:re lICIPCLII the work. There are
Card 8/9 11 flgureo; and 2 i-ef'openueo, 1 Soviet, 1 U.S.
The U.S,

Effect of Layers Containing Boron on T1216
the Yield of Secondary Gamma Radiation. SO1v/8)-8-1-10/?-q
Letter to the Editor
reference is: Reactor Physics Constants, ANL-58oo
(1958).
SUBMITPED: August 3, 1959
Card 9/9

85564
S/089/60/009/005/008/020
B0061BO70
AUTHORS: Androsen~ (Deceased), Broder, D. L., Lashuk, A. 1.
TITLE: Gamma Rayelproduced by Inelastic Soattering of 3-Mev
Neutrons
PERIODICAL: Atomnaya energiya, 1960, Vol. 9, No. 5D PP. 403 - 406
TEXT: Experiments on the inelastic scattering of 3-Mev neutrons from
titanium, chromium, strontiumv iodinev bariump tungstenv indium, and
bismuth nuclei. resulting in the production of gamma rays were
described
by the authors of this paper in Ref.l. The gamma rays were studied
and
their energies determined. The present paper gives data of
analogous ex-
periments on other soatterers in the form of Tables and Diagrams.
The
deuterium target of an accelerator was surrounded by blocks of
paraffin
with admixture of boron carbide. The neutron beam was iollimated
through
an opening 20 mm in diameter in the paraffin lithium-hydride blocks.
An NaI(Tl) crystal (40)(40 mm) and the photomultiplier were
arranged in
a lead chamber. The.samples to be studied were attached to a thin
rod
Card 11i

85564
Gamma Rays Produced by Inelastic Scattering S/089/60/009/005/008/020
of 3-Mev Neutrons Boo6/BO70
and placed at a distance of 4 cm from the surface of the crystal. The
results obtained from a carbon scatterer were used for bac~kgraund
correction. There are 4 figures, 1 table, and 8 references: 2 Soviet
and 6 us.
SUBMITTED: July 17, 1959 Vr
Card 2/1

32993
S/641/61/000/000/020/033
B108/B102
.9
AUTHORS: Broder, D. L., Kondrashev, A, P,, Kutuzov, A. A#
TITLE: Spatial neutron distribution in mixtures of boron carbide
with iron and lead
SOURCL Krupchitskiy, P. A., ed. Neytronnaya fizika; sbornik statey.
Moscow, 1961, 263 - 277
TEXT: The results of experiments given in this paper are to verify
the
possibility of calculating the spatial distribution of fast
neutrons in
media containing boron carbide. The fast neutrons were obtained
from
interaction of 1-Mev deuterons with heavy ice (4-Mev neutrons) and
of
400-kev deuterons with tritium adsorbed on zirconium (14.9-Mev
neutrons).
These neutron sources were placed before 9 steel tanks filled with
boron
carbide and each containing a thin-walled cavity in the middle to
place the
detector in. The free cavities were filled with boron carbide. In
some
of the experiments, tank 2 or tank 2 and 3 were replaced by
laminated
iron or lead blocks. Other experiment.s provided steel and lead
plates
between the tanks. Since the tanks were CT-30 (5T-30) steel, all
the
measurements were made with boron carbide "containing" 3.61; by
volume of
Card 1/2 -1

32993
S/641/61/000/000/020/033
Spatial neutron distribution... B100102
iron. The results showed that iron and lead have similar
removal cross
sections. Substances with small inelastic scattering cross
sections, as
boron-carbide, have greater removal cross sections in water
than in other
moderators not containing hydrogen. The ratio of intermediate
and slow
neutrons (E n< 1-5 Mev) to the fast neutrons was calculated.
It was found
to be 3 6 for 4-Mev neutrons and 2.58 for 14.9-Mev neutrons.
The ex-
perimeneal values were lower and closer to each other. This is
due to a
lower sensitivity of the U235 fission chamber at neutron
energies E >100 tl/
kev. The authors thank Professor A. K. Krasin, V. V. Orlov,
Candidate of
Physical and Mathematical Sciences, G. N. Deryagin, N. N.
Dudkin,
A. P. Klimov, V. G. Liforov, Z. S. Blistanova, A. I. Chusov,
V. S. Tara-
senko, and R. G. Bulycheva for help. There are 10 figures, 1
table, and
11 references; 4 Soviet and 7 non-Soviet. The four references
to
English-language publications read as followsi Blizard E. P.
Ann. Rev.
Nucl. Sci., 5-, 73 (1955); Doldstein H. The attenuation of
gamma rays and
neutrons in reactor shield, NDCA, N. Y~, 1957; Burgeois I. et
al. Methcus
and Experimental Coefficients Used in the Computation of
Reactor
A/Conf 15/P/1190 France, 1958; Duggal V., Puri S., J. Appl, I.
Phys., 29,
675 (1958).
Card 2/2

B1041/B138
-.2-2 0
AUTHORS: Broder D. Popkov, K. K.
TITLE: Physical-engineering calculation of a biological shield
against the radiation of nuclear reactors
PERIODICAL: Inzhenerno-fizicheskiy zhurnal, v- 4, no. 12, 1961, 118 -
130
TEXT: The problem under consideration requires the calculation of
neutron
distribution outside the shie*ld. -The integral
q g (r.) Id V.
TM 4
Vs
E(-o
has to be calculated in this connection. qV r a is the distribution
func-
tion of the power density of the source, and f f(68 , 6t, E) is the
radiation flux attenuation of energy E in the source and in the'shield.
The calculation of qE (r is one of the principal stages. Primary radia-
v
tion (instantaneous neutron fission, instantaneous gamma radiation,
gamma
Card 1/2
S/170/61/004/012/011/011

S/170/61/004/012/011/011
Physical-engineering calculation of ... B104/B138
and neutron absorption) and secondary radiation (capture
gamma rays; gamma radiation generated by neutron-activation
of the mate-
r,ial; neutrons generated by the (y,n) reaction) should be
allowed fo'r
when calculating, the shield. In the present review, the
voluminous
international literature is taken as a basis for a thorough
examinbticA..;;,
of the spatial and energy distributions of primary radiation,
the power
and dis 4. ribution of sources of secondary radiation, the
flux distribution
of fast neutrons, the spatial energy distribution of
neutrons, and the
attenuation of gamma radiation in the shield. There are 1
figure, 4 ta-
bles, and 51 referencess 25 Soviet and 26 non-Soviet. The
four most
recent references to English-language publications,read as
followss
Katooff S. Nucleonics, 18, 11, 201, 1960; John F. Stehn.
Nucleonics, 18,
11, 186, 1960; Troubetzkoy E. and Goldstein H. Nucleonics,
18, 11, 1711
1960; Clark M. D., Nuclear Engineering, ~06, jan, 1961.
Card 2/2

.S/048/61/025/002/016/016
B117/B212
AUTHORS: Broder,.D. L., Lashuk, A. I., Sadokhin, I. P.
TITLE: Gamma-radiation yield in inelastic scattering of
neutrons on
antimony nuclei
PERIODICAL; Izvestiya Akademii nauk SSSR. Seriya
fizicheskaya, v. 25,
no. 2, 1961 , 309-312
TEXT: The present paper was read at the 11th Annual
Conference on Nuclear
Spectroscopy (Riga, January 25 to February 2, 1961). The
authors have in-
vestigated the yield of 1.01-Mev gamma quanta which are
produced in inelas-
tic scattering of neutrons on antimony nuclei. In these tests
annular
geometry was used (Fig- 1). 30 mm high rings (3) with an
outer diameter of
85 mm. and an inner diameter of 60 mm, served as scattering
specimens. A lead
cone (2), height 360 mm, base diameter of 58 mm shielded the
crystal against
direct radiation. The gamma-radiation spectrum was
investigated by means
of a scintillation gamma spectrometeg with a 40 by 40 mm
NaI(Tl) crystal
with a relative half-width of the Zn 5 lines (1.12 Mev) of
about 9% WY -
photomultiplier). The amplitude distribution of the pulses
has been studJed
Card 1/4

S/048/61/025/002/016/016
Gamma-radiation yield ... B117/B212
with a 128-channel pulse-height analyzer. The neutrons have
been obtained
from a H3(pn)He3 reaction on anelectrostatic generator at a
proton energy
of 1.5-3.3 Mev. The energy spread of the neutron beam was
no wider than
30 kev. Two types of measurements have been made with and
without the
specimen. The given values are averaged over the two test
series. The
measurements with 0.9 to 2.5-Mev neutrons have confirmed
the gamma lines,
aegLven in Refs. 6-8: 0.49, 0.59, 1.01, 1.32, 1.50, 1.84,
1.96, and 2.16
Mev. A detailed investigation of the spectrum in the region
of 1-1.5 Mev
is very difficult duel.to a low intensity of the 1.32-Mev
line expected. It
is only mentioned thA the T.32 and 1-50 Mev-lines are
excited at neutron
energies of about 1.5 Mev; this indicates that the Sb121
and Sb123 nuclei
might have 1-50 Mev and even 1.32 Mev levels. A 1.5 Mev
cascade transition
to the 0.153 Mev level, emitting 1-34.7 Mev gamma quanta
might be possible
for Sb123. It has been established that antimony nuclei
have an energy
level near 1 Mev that is excited by an inelastic neutron
scattering. For
neutrons with an energy higher than 1.01 Mev, the 0.87 Mev
line is visible.
At higher energies this line and the 1.01-Mev line become
indistinct, which
is due to a low resolution of the spectrometer . Another
level can be as-
sumed near 900 kev. An other possibUity would be a
transition from the
Card 2/4

S/048/61/025/oo2/o16/oi6
-radiation B11
Gamma yield ...
7/B212
1.01-Mov. excited, state to th6 0.153~-Mlev level and emission of
0..8 Mev-
quanta. This is the case-if the 41.01-Mev--level is referred to SbI33
nuclei.
The following can be assumed, considering the 1.01-Mev gammw yield
for in-
ilastic neutron scattering on antimony nuclei with energiBs of
1.0-2-5,Mev:
For neutron-energies between 1.0 and 1-5 Mev the'eurve corresponds to
the
excited 1.01-Mev level of antimony nuclei. A cascade transition to
this
level from the 1.32 Mev-level is not possible, because no gamma line
with
an energy near 0.3 Mevcould be established in the spectra examined.
Fig- 4
shows the graph for the gamma~ yield with an energy of 0.84 Mev for
iron
nuclei. The data established by the authors of this paper are plot
'ted for
2.0-Mev electrons. The radiation sources which were used to scale the
gamma
spectrometer are given in the table. There are.4 figures, 1 table, and
8 references: 6 Soviet-bloc.
Legend to Fig. 1: 1) tritium target, 2) lead cone, 3) scattering ring,
4) proton beams
Card 3/4

S/048J61/025/002/016/016
Gaiama-radiati.on, yiel
B117/B212
4,
NeY

B/869 62*080~000/012/012
B102 BIe6
YB
AUTHORS: BE2der, D._L._t Leshuk, A. I., Sadokbin, I. P., Suvorov,.A. P.
TITLEt Inelas'tib scattering of it'
eutrons-from iron nuclei
SOURCE: Teoriya i metody rasoheta yadernykh reaktarov; sbornik
statey. Ed. by G. I. Marchuk. 'Moscow, Posatomizdat, 19627
254 259.
-The aim 'of the work was to determine- the energy dependence of the
inelastic scattering cross section-in-the-range 0.80 - 4-0 Mev-by ana-
lyzing experimental data as aocurately-As'possible. Supplementary
exper-
iments were carried out to provide miasing,da.ta I. The reaction
T3(p,n),He3
was used 3as a source of neutrons for the P.80 -'2.5 Mev -range, and
D(d,n)He for 2.5 - 4 Mev. The y-ray dete~torwas an NaI(Tl) crystal with
a (O~Y-13(F *EU-13) photomultiplier.-,Hence the pirls .es were*fed th
.rough an
amplifier to a: 128-channel pulse-heiFbt analyzer._-The investigations
were
carried out for the components of, the-most, abundaiLt natural
isotopic.com-
56 54 57 56
,positioni. 91.68.% Fe , 5.484 Fe . 2.17 % Fe, and 0.31 % Fe . The
cross sections'of the y-qu"tum yield when neutrons of various energies
Card 1/2

8;/B69/62/000/000/012/012
Inelastic scattering of neutrons Bip2Z~186
are inelastically scattered.were measured. Thejollowing values of E
Y
were found for E. M 4-0 Mevs 0-84, 1.02, 1.23,''V-44, 1-81, 21-15 2.6
Mev.
With the exception of 1.41 Mev, all these are associated with
scattering
from Fe56 levels- 1-41 Mev.is attributed to scattering from the first
54
Fe level. The other E are assigned as followst 1.23 Mev appears when
Y
the 2.06-Mev level is excited and then de-excited via Ahe 0.84 Mev
level
to the ground state. 1.81 Mev is attributed to excitation and cascade
de-excitation of the 2.62 Mev level. 2-15 Mev quanta are emitted when
the
3.02 Mev le4el decays via 0'-84 1~ev to the grbu.Tid state. 'The
0;-64 Mev
quanta are -the result of direct traniii-tions..from--this level'to
the ground
state. In some cases,the cross sections oVtained differ.'oonsiderably
from
the calculated'yaluee. There is 1 figure.
Card 2/2

33472
1400
8/170/62/005/002/004/009
A o2.11 0 0 B104/B138
ADTHORS: Broder,-D.' L., Kutuzov, A. A., Levin, V. V.
TITLEt Shielding
-properties of water, polyethylene, and Plexiglas
PERIODICAL: Inzhenerno7fizicheskly zhurnal, v. 5, no. 2. 19629 47 51
TEXTt Jn an effort to. estimate the shielding action of hydrogenous
mix-
tures'against fast neutrons, the authors calculated the distribution
of
-fast'neutr*o*ns in bydrogen,and water. The attenuation of a stream
of fast
-neutrons-in ahydrogenous mixture with.the initial energy E can be
calcu-
0
lated f rbm E
1o)(1
po", (L D)r
V Q (E0)
4) (i., E0 E, y(E, dE,
EO 0 r)
-47C r2 Erp
Where.Q(E is the power of a point source of neutrons, q is the volume
~o
part of hydrogen nuclei in the shield-, and f(Et Eo~,Or) is the
spectrum of
moderated neutrons. ~he results.are consistent with H. Goldstein's
(Funda-
mental Aspects of Reactor Shielding. Pergamon Press, London-Paris,
1959).
Card 1/2

33472
S/170/62/005/002/004/009
Shielding properties of ... B100138
The'remdval cross section for oxygen was obtained from the spatial
distri-
..bution~of neutrons in water and hydrogen. For the purpose of
checking the
validity of Eq.(1), the.distribution of 4-Mev and 14.9-hiev neutrons
in pol3F--
t* lene andPlexiglas-~ was m
hy easured. Deuterium and tritium adsorbed on
e
zirconium were.used as targets, which were bombaided with 1-Mev and
0-4-1;'.ev
7 '.deuterons.. The-experiments showed that a shield again6t neutrons
of
0.2.- 15 Mev,*consisting of 0,- C, Fe,.and Pb, can be calculated using
the
neutron spectrum-in hydrogen,,the removal cross sections for neutrons
as
functions of energy, and-the analogous cross-sections for iron and
lead.
Z. S. Blistanova , V P. Bogdanov, G. V. Rykov, and V. S. Tarasenko
partici-
pated in the work. There are 4,figures and 5 references. 4 Soviet and 1
non-Soviet.
SUBMITTED: April 17, 1961
Card 2/2

43352
3,/170/62/005/012/005/006
B100186
AUTHORS: Broder, D. L., Kumuzov, A. A., Levin, V. V., Frolov, V. V.
TITLEt Using the method of removal cross sections for calculating
a shield that contains no hydrogen
PERIODICALt Inzhenerno-fizichesk,iy zhurnal, v- 5, no- 12, 1962, 65 70
TEXT: Attenuation of a monoenergetic neutTon. flux in Al and in
mixtures
of Al containing equal portions of Fb and Fe was measured; also
attenua-
tion in an assembly of Al plates with Fe, Pb, plexiglass or
polyethylene
blocks placed between source and detector. The neutron sources used
were
the reactions D 2(D,n)He No - 4 Mev), T3(]D,n)H04 (Bo M 14-91 Mev)
and a
235
U disk expoced'to a thermal neutron flux-extraoted from the reac.tor
of
the first atomic power plant in the world. A fiesion,chamber with
Th 232 was used as detector. Resultst (1)~the removal cross section
method can be used to calculate a shield in which light substances Are
used instead of water*; (2) in most cases the removal cross section
de-
pends on the moderat6r only slightlyl (3) the removal cross section
Card 1/2

S/170/62/005/012/005/008
Using the method of removal ... B104/B186
reaches saturation at relatively small distances from the souroe; (4)
the measurements with a U235 fission chamber*and those made with a
Th232 fission chamber are consistent for boron carbide and water. (5)
At
a sufficiently large distance from the source theirsoiptooll of the
relaxation length is equivalent to.the removal arose section of any
given substance. There are 3 figures and I table.
SUBMITTED: July 30, 1962'
Card 2/2

32001
ILI Do S/ov/62/012/001/004/019
B102 B138
.V- 6. ,2 .2 416
AUTHORS., Broder, D. L., Kayurin, Yu. P., Kutuzov, A. A.
TITLE: Passage of gamma radiation through heterogeneous media
PERIODICAL: Atomnaya energiya, v. 12, no. 1, 1962, 30 - 35
TEXT: The buildup factor was measVred for heterogeneous media,
consisting
of diffe;ent combinations of shielding materials (polyethylene,
Al, Fe,
Pb). CobO was used as point source (N1 g-equ. Ra, E0 = 1.25 Mev).
Various combinations of rj1O mm thick'plates~*(Fe and Pb: 700
'700 mm;
polyethylene (P) and Alt 1000 - 1000 mm) were investigated. A
plastic
scintillator connected via a lightpipe to a ~39-24 (FEU-24)
photomultiplier
Was used as a detector. Dose rates were varied in the range 1 -
105
relative units. Measurement accuracy was about t 10a. The
following
combinations were investigated: (P) + Pb, (P) + Fe, Fe + Pb, Pb +
(P),
Fe + (P),-Pb +-Fe, with t:he first material nearest to the
source. The
buildup factor was calculated by the empirical formula
n n-1
Bheter. BJL)bixi) --tB n(7 B)bix,); B n is the buildup factor of
Card 1/2 n=1 i=1 n-2 i=1

S/089/62A20102NO 1/004/019
Passage of gamma radiation... B102/B138
the n-th material, Pix is the layer thickness in terms of
mean free path.
'~P) - o-o61 cm-1' /LA1 0.149 cm -1 , PFe - 0.425 cm- 1, )~b
=0.680 cm- 1z
The buildup factors calculated with this formula agreed with
the measured
ones within the limits of experimental accuracy, It is
recommended for
use at energies near 1 hiev. V. A. Shalin and G. V. Rykov are
thanked
for assistance. There are 7 figures and 7 references: 4
Soviet and 3
non-Soviet. The reference to the English-language publication
reads as
follows: 1,11. Berger, J. Doggett. J. Res. Nat. Bur.
Standards, ~6, 89
(1956).
SUBMITTED: April 17, 1961
Card 2/2

33234
5/089/62/012/002/005/013
4, B102/B138
AUTHORS: Kondrashov, A. P., Kutuzov, A. A., Naumov,
- 77. A., Sergeyev, Yu. A., Turusov, A. V.
TITLE: Maltigroup methods of calculating biological shielding
PERIODICAL: Atomnaya energiya, v. 12, no. 2, 1962, 129 - 139
TEXT: The spatial energy distribution for biological shields
is
calculated for a source at a distance of 40 cm. Seven- and
ten-group
methods are usedand the calculations are made in
diffusion-age and
diffusion approximations, respectively. As the lower limits
of the
groups the following energies were chosen for the
seven-group method:
1.5-10 6, 9.106, 4-5-10 5, 3-103, 3.39 Elim and 0 ev, and
for the ten-group V~
6 6 6 5 4 3
5
method: 4,10 , 2-5-10 1 1.5-10 , 7-10 , 3 10 , 4-10 , 1-10 ,
6.7, Elim
and 0 ev. Spectrum and group constants are calculated for
both groups
and the results are compared graphically with experimental
ones. The
experiments were made with the critical assembly of a water
moderated
Card 1/3

33234
S/089/62/012/002/005/013
Multigroup methods of calculating... B102/B138
reactor with a water side reflector. The shield investigated
formed the
bottom reflector. Three types of shields were investigated,
consisting
of several layers of various kinds of steel, lead, boron
carbide and
polyethylene. The neutron flux in the assembly was measured
with a
cooper foil, the thermal-neutron flux in the core with a
copper indicator
and an U235 fission chamber, and, in the experimental
assemblies, with a
copper indicator in a Cd container. Comparison between
theoretical and
experimental results permits the following conclusions: 1)
Both the
multigroup methods, and the group-constants chosen, are
suitable for
calculating the spatial distribution of neutron energy in
shields
containing Fe, Pb and H. 2) For shielding systems containing
B the
agreement with experiment is within 20% error limits. 3) The
seven-group
method can also be used to determine the spatial distribution
of fast
neutrons which is characteristic of delayed-neutron flux
distribution.
For a source emitting 4-Mev neutrons and with large shield
thicknesses,
the ten-group results differ from the experimental ones by
not more than
3M"'. N. A. Gushchina, L. V. Marchenko, Z. P. Sokolova, Z. S.
Blistanova
and A. M. Astakhova took part in the calculations, N. A.
Aleshin and R.
Card 2/3

Multigroup methods of calculating...
33234
S/089/62/012/002/005/013
B102/B138
G. Bulycheva in the experiments. The reactor team members I. G.
Morozov,
Ye. I. Inyutin, V. K. Labuzov and N. G. Uvarov are thanked for
their work.
There are 4 figures, 1 table, and 12 references: 7 Soviet and 5
non-Soviet.
The reference to the English-language publication reads as
follows: D.
Hughes, L. Harvey. Neutron cross section, 1958.
SUBIITTED: April 17,
1961
01-K
Card 3/3

I
KARDASHIM, D.A.; STAVINSM, V.S.; BRODERv D-.L.; LASHUK,
A.I.,- SADOKM, I.P.
Analysis of the e=itation functions for levels of the
Fe'56
nucleus in the case of inelastic neutron scattering in
an optical
nuclear model. Atom.energ. 13 no.6*587-588 D 162. (MIRA
15t12)
(Iron-lootopei(q) (Noutrone-Seatterin )
Naclear optical Modelef

ERODER. D.L.; KAYURIN, Yu.P.,-, KUTUZOV, A.A.
I----
Calculating the factors of ~Uray build-up in
heterogeneous media.
Atm.energ.~ 13 no.6t593--595 V 162. (KM 15S12)
(Giams rays) (Nuclear reactions)

JROU,_D.L.,, red.1 VESELKIN, A.P.p red.j YEGOROV,
Yu.A., red.,*
ORLOVp V.V., red.j TSYPIN, B.G., red,; PODOSHVINA,
V.A.,
red.; NIKITINA, T.K., red.; VLASOVA, N.A., tekhn.
red.
(Problems in the pbysics of reactor shielding)
Voprooy fiziki
zaohohity reaktorov; sbornik statei. Moskvap
Gosatomizdat,
1963. 345 P. (MIRA 16:12)
(Nuclear reactors-Shielding (Radiation))

ACCESSION NR: AT4019031 S/0000/63/000/000/005Z/0.060'
AUTHOR: Broder, D. L.; Kutuzov, A. A.; Levin, V. V-.; Frolov, V. V.
TITLE: Application of the "removal cross section" method to the
computation of non-
hydrogen-containing shielding
SOURCE: Voprosy* fizild zashchity* reaktorov; sbornik statey
(Problems In physics of
reactor shielding; collection of articles). Moscow, Gosatomizdat,
1963, 52-6;0
TOPIC TAGS: nuclear reactor, reactor shielding, Iron shielding,
lead shielding, non-
hydrogenous shielding, removal cross section, neutron, neutron
spatial distribution,
'i i neutron decelerator, aluminum shielding, boron carbide
ABSTRACT: The authors first briefly describe the removal,cross
section method for the
computation of the spatial distribution of neutron stroams in
hydrogcn-containIng shielding.
Some of the limitations of the method are discussed along with an
analysis of the difficulties
often encountered in its application (for example, in homogeneous
mixtures). The hyl>othesis
has previously been advanced that, by prescinding from the question
of the accumulation of,
low-energy neutrons, the removal cross section technique might be
applied to Inedia
:Card

ACCESSION NR: AT4019031
f
containing other light decelerators in place of hydrogen. In these
previous investigations,
boron carbide in a mixture with iron and lead was studied as the
decelerator. Some of
the findingo of this research are discussed in the present
article,which also gives additional
experimental data which prove the feasibility of extending and
generalizing the removal
cross section method to heavier slowing media, Aluminum was
employed as the decelerating
medium in the tests reported on in this paper. Neutron sources with
E = 4 Mev and 14.9 Mov
were used. In addition, measurements were made of the removal cross
sections of iron and
lead in boron carbide in the fission neutron spectrum and the
removal cross section of iron
in the apeckfum of the VVR*reactor. As neutron sources the authors
used the reactions
D (d, n) He' with an T (d, n) He4 (E = 14.9 Mev),
,,,Wtial neutron energy of E = 4 Mov, and
and also a disk of U removed from the reactor of the Pervoy v mire
atomnoy olektrostants
(World's First Atomic Power Station) and placed in a stream of
thermal neutrons. The
sources were in the form of disks with a diameter of 10 cm for the
mono-energetic -neutron
sources, and 46 mm for the fission spectrum source. Past neutrons
were detected by
means of a fission chamber with Th232. Further details on the
experimental apparattrs are
given In the article. Graphs are presented showing the spatial
distribution of -the fast
'X d__-~2/4
ar

_4~
ACCESSION NR: AT4019031
neutrons in different substances and mixtures, as well as the
dependence of the removal
e.ross sections of iron and lead in aluminum (and of polyethylene
and plexiglass in aluminum),
for neutrons with E = 4 Mev and 14.9 Mev on various controlled
experimental factors
(distance between source and detector, distance between block of
removed material and
detector, etc). A table is given showing removal cross sections
measured in water, boron
carbide and aluminum. It is shown that the removal cross section
method-is applicable to'
the computation of shielding In which other light media are
employed as decelerators in
place of water: for example, boron carbide or aluminum. The
magnitude of the removal
sections for the majority of the substances tested depends only
slightly on the choice
of the decelerating medium. If a light component is lacking in the
shielding, the authors
found that the use of the removal cross section method is possible
provided the removal
cross sedion of the material in the given medium is known or if the
lower boundary of the!
energy group is substantially raised. Several other significant
conclusions are discussed
In the article. 117be authors thank V. P. Bogdanov, B. G Oslporv,
G. V. Ry*kov, V. 's.
Tarasen1w and A. L Chumv for'taking par. In the measurements.
I
3/4

ACCESSION NR: AT4019049 S/0000/63/000/000/0198/0207
AUTHOR.- Broder, D. L.; Kayurin, Yu. P..; Kutuzov, A. A.
TITLE: The passage of Gamma radiation through heterogeneous media
SOURCE: Voprosy* fizild zashchity* reaktorov; sbornik statey
(Problems in physics of
reactor shielding; collection of articles). Moscow, Gosatomizdat,
1963, 198-207
TOPIC TAGS: nuclear reactor, reactor shielding, iron shielding,
lead shielding, Gamma
radiation, Gamma ray attenuation, Gamma radiation shielding, Gamma
radiation accumu-
lation factor, polyethylene shielding, aluminum shielding
ABSTRACT: The authors note that the computation of shielding
against gamma-radiation
requires a knowledge of one of the essential characteristics of
the material - the
radiation accumulation factor. For homogeneous media the
accumulation factor B(E x, z. g)
is a function of the initial energy of the -/ -radiation E , the
thickness of the materi x, .
the ordinal number of the substance z, and also the forK of the
source g. The significance
of the accumulation factor for such homogeneous media Is discussed
in some detail. Some
recommendations, based on general physical considerations, with
respect to the computation
cir 1/2

ACCESSION NR: AT4019049
of accumulation factors for heterogeneous shieldings consisting of
two materials are
analyzed. An experimental determination is made of the dose
accumulation factor for
heterogeneous media, consisting of various combinations of
materials (polyethylene,~
aluminum, iron, lead), and for (-quanta energies of 1. 25, 2.76
and ca. 6.4 Mev. As the
source of theY-quanta with an energy of 1. 25 Mev, Co60 was used;
for the quanta with the
2.76-mev energy level,Na24 was employed. In order to obtain the
high-energy (6.4 Mev)
)"-quanta the authors made use of an F 9 (p,cA )016 reaction. On
the basis of the experi-I
ments with CoGO and general physical considerations, an empirical
formula was derived
for the computation of accumulation factor in a heterogeneous
medi.Vjn consisting of any
number of layers of different materials. The experiments with Na4"
and the 6. 4-Mev
Y-ray source demonstrated that this formula may be used even In
the case of Y -quanta
energy levels in excess of the critical. Experimentally derived
accumulation factors
differ from those computed according to this formula by no more
than 15%. Orig. art.
has: 3 formulas, 1 table and 9 figures.
ASSOCIATION: none
SUBMITTED: 14Aug63 DATE ACQ: 27Feb6
4 ENCL: 00
SUB CODE: NP NO REF SOV: Oo4 OTHEFL- 004
rd-,'
,V2

!,ACCESSION NR: AT4019057 S/0000/63/000/000/0234/0242
AUTHOR: Droder D L Kondrashov, A. P. -, Naumov, V. ,k. ; Popkov,
X. K.
TITLE: Heat release In the shield and body of a reactor
SOURCE: Voprosy* fizild zashchity* reaktorov; sbornik statoy
(Problems In physics of
reactor shielding; collection of articles). Moscow,
Gosatomizdat, 1963, 234-242
TOPIC TAGS: nuclear reactor, reactor shielding, heat release,'
heat emission, reactor
heat dissipation
IABSTRACT: A considerable amount of energy is liberated in the
active zone of a reactor due
to the long-range neutron and Vradiation. This excess of energy
is particularly important in
the construction of water shielded reactors. Consequently, the
following processes. must be
considered in the calculation of heat release: (1) )**radiation
in the active zone of the reactor;
1(2) ~ radiation arising from the capture of neutrons; and (3)
CC-particles from the B10 (no*L17
reaction. The Yr'adiation thus comes from five processes: (a)
Flux of rays from the
active zone:
qQ
Card 1 6

1ACCESSI09-NR~-AT4bigo
(b) 'Flux of adiation from neutron capture in the* shield and
body- of the reactor;
b
b . qVh
{E. [(I +
TVh 2pra I+ QJFO CjIN) ILIX1.1
--E2 -pix, psd)
VV),
(3a)
2 +
~b fe -P5
VA.
PIXI
+a k1XI -e'
+ Ctirs) LI
j ) >3 I ] . I N j
A
d + + E, (I +
d-~
Lard 2/5

ACCESSION-j9A--AT4019057 -2
Aix,)
b~ (2) Are e AS E1.01 +are) +.:t2-j V
9v 2X2 "6j
(3b)
KA e
jLsd*+
x S d PIxi)\ + E, 0 + aj'.*) Yj*~41XI)II
(a) Flux of ~ra~s froM me rama.tive .cap'tiie of neutrons.
2 ' . - ~ ... .: . . . - .'
A 1 - - j(j+aj)pr,(d-x)j"~% i
(Pv yj (2o-Ejj(I+qj)~sxj E2 (4)
21,s I+CLJ
qy'
(d) Flux of -brays due to neutron capture in the water in the
space between the shielding;,
rd
qBy d
(Vvh AreE, (I + Qj JAji4
(6)

ACCESSION NR: AT4019057
(e) Flux of captured adiation in the water in the reactor
An e IdEj; +
22; _j i II
d
TE, [0
Ej (I + ajn) yj'.p,x', + Its d
J;
C +(&J )I
Ps
+ e tL,x + sd] (I
Ps
4/5
(7)

ACCESSION NR: AT4019057
The contribution of ocradiation is given by:
Q. (r) 1j"
The experimental determination of the heat release in a reactor
was performed by the ioniza-
tion method, which was -found to be more sensitive than the
calorimetric method in the ease
of a zero-power reactor. The energy loss in the solid medium
(heat release) is related to
the energy loss in the gaseous melum by
i (-dE1dx),D q
7W (9)
(L. H. Gray, Proc. Roy. Soc. A156, 578 (1936).) The theoretical
and experimental results
ishowed satisfactory agreement. Orig, art. has- 3 figures and
17 formulas.
ASSOCIATION: none
SUBMITTED: 14Aug63 DATE ACQ: 27Feb64 ENCL: 00
SUB CODE: NP NOREFSOV- 002 OTHER.: 004
Lcord 'A

- BRODER, D.L.; FOPKGV,, K.K.
Methods for calculatina radiation heat release in the vessel
and
0
shields of a nuclear reactcr. Atom. energ. 15 no.5:370-377 N
163.
(MIRA 16:12)

BRODER, D.L.; ZAYTSEVp L.N.; SYCHEV, B.S.; TUGOLUKOV,
A.M.
Effect of the water content of concretes on the
thickness and cost of
reactor shielding. Atom. anarg. 16 no.1:26-32 J& 164.
(MIRA 17:2)

AOCESSION NR: AP012262. S/0089/64/016/001/0026/0032
ATMWORRe _~rpdei~., D.L.; Zayteev, L.N.; ft1*Qh6Tq B.S.;
Tugolukov'j A.XJ
SOUROR:
Atomnaya energlya, v.16, no.1, 1964,, 26-32
---[TOPIO TAGS: reao!6i ahitld, biological react6r ~rotectjon,
reaotor
shield cost, reactor shield water concentration, optimal reactor
protection
ABSTRAOT: The purpose of the present work is to determine the eco-
.i nomical aspect of the increasing amount of water in concrete for
.1-reaotor shieldings. Increasing the water content in concrete
inorea-1
sea its hydrogen concentration which effectively reduoeo the leaks,
go
of fast and intermediate neutrons because of the large cross
section ,
of hydrogen for fast and intermediate neutrons, Various types
of.con-
crate used for reactor shieldings have hydrogen concentration
witbinj
the 12% range. The authors have computed the biological protection
J
A
Icard '1/2
TITLE: Effect of water content in concrete on the tbiolmess of the
reactor shield and its costs