SCIENTIFIC ABSTRACT -

• Document Type: CREST
• Collection: Scientific Abstracts
• Document Number (FOIA) /ESDN (CREST): CIA-RDP86-00513R000927920017-4
• Release Decision: RIF
• Original Classification: S
• Document Page Count: 100
• Document Creation Date: November 2, 2016
• Document Release Date: March 13, 2001
• Sequence Number: 17
• Publication Date: December 31, 1967
• Content Type: SCIENTIFIC ABSTRACT

- KUTUZKINA, TO.Y.
fte genus Icranthux in Sarmatian deposits of the Northern Caucasus.
Phleont. zbur.-no.4t13q-141 60. (Km 14a)
1. Botanicheskiy institut iment. Y.L. Komarova, Akademii nauk SSSR.
(Armavir region-Mistletoe, Posell)

KIJTIJZFI!v'Ap Yfi.Fe
Sf-ruati,Ln I'lora of Axv;;,Lvtr. Tri.-y 1,ol.. Init. Fal,,ob,)t. Ser. 8 no.51
145-230 164. (@f lq.A 1%, 16)

de
rou 13" 1 3-1125 ,j7. 16%
m.@@ i s r

MUM. A.
began by Anna Kaslovaia Is growing. lrhim.prom. no.2t
120-121 Mr 154. OUR A 7: 6)
(Chemical Industries)

FD-I"V
WSR/Chemls try - Miscellaneous K*1 'Z 0 VJ f-
Card 1/1 : Pub. 50-i4/iB
Authors : Kutuzov. A., Krivosheyev, S. A.
Title : News Items
Periodical : Xhim. -prom., No 1, 53-54, Jan-Feb 1955
Abstract : The results of the prcduction plan for 1W' carried out by the Minis-
try of Chemical Industry, the improvement of the quality of scientific
research work, the training and employment of specialists, awards
made to the foremost enterprises of the chemical industry, and the
results of a 1954 competition on the improvement of the production of
fertilizers and the production of new types of fertilizers are discussed

AUTHOR: - - ----- 64-53-4-17/20
TITLE: On Improving the Organization of PlAnning (Uluchshit'
postanovku. proyektirovaniya)
PERIODICAL: Khimicheskaya promyshlennost', 1956, Nr 4, pp. 258 - 256 (US;H)
ABSTRACT: In the first quarter of this year the Council of the Ministry
of Chemical Industry investigated a number of problems concernin@;
the work mentioned in the title in connection with cl-anees in
the direction of industry and development. This is connected
with the decisions made by the !:--y-Gencral Meeting of the TsK
KPSS (Central Committee of the C? of the Soviet Union). A number
of institutions, with their directors beini, mentioned, is
seriously criticimd and the backwardneso as compared to the atan-
dards fixed ic condemned and com:-ionted on. Among others an in-
sufficient coordin;@tion is mentioned as main cause for these
chortcomingS, and practical decisions on the publication of tech-
nical documentations for complying vrith t'@e prefixed atandarda
as well as for the maintenance of quality are -mentioned, The
respective individuals ii. chaarr-e of these institutions were
Card 1/2 forced to control the fixed te@ma, the dia,-rams for the fi@lfil-

On Improving the Orc;anization of Projectin;1- Work
ment Of VIO docuumentatior.,on planning
the data on the ac',ii,@,vc-q.
4 - 513-4-17/2o
and Uic publicrition of
i. Chemlclll
,
Card 2/2

DIROZDOV, S.N.; KMUZOV, A.A.
Boron requirements of spring wheat and barley in their ontogenic
development. Rauch. dokl. vys. ahkoly; b1ol. nauki no.1:129-131
16o. (MIRA 13:2)
l.Rokomendovana kafedroy fisiologil rastenly Leningradskogo
sel'skokhozyaystTennogo instituta.
(Wheat--Fertilizers and manures)
(Barley--7artilizerv and manures)
(Plants, Zffact of boron on)

AUTHOR: AliTONOV,YU.N., VAVILOV,YU.11., PA - 2665
KUTUZOV,A.A., SKVORT-S0V,YU.V,, KIIHISTIANSEIT,G,.B.
TITLE: Structure of the Periphery of Extengive Atmospheric Cosmic Ray
Showers. (Struktura periferii shirokikh atmosfernykh livney koomi-
cheskikh luchey, Russian).
PERIODICAL: Zhurnal Eksperim. i Teoret. J@iziki, 1957, Vol 32, fir 2, pp 227-240,
Russian)
Received: 5 / 1957 Reviewed: 6 / 1957
ABSTRACT: The present paper investieates the spatial distribution of the
different components of a broad atmosDheric cosmic ray shower at
great distances from its axis (200 - 800 m). For a detailed study
of this problem the Pamir-Expedition of the Academy of Science of
the U.S.S.R. (su;*mer and autumn 1950 and 1951) used a new method:
In different places of the observation plain the flux density of
all charged particles (and separate from it that of penetrating
particles) was simultanously determined with hodoscopic devices.
(Method of correlated hodoscopes).
SummaEX of results: The shower domain investigated here consists
of an eleotron-photon component andef apenetrating component
(apparently myons).With increasing distance from the shower axis
the relative share of the penetratine, com@-,onent increases consider-
ably and at a distance r - 800 m the flux denaity of penetrating
Card 1/2 particles and of electrons is equal. The spatial distribution of the

Structure of the Periphery of Extensive Atmo-- PA - 2665
suharic Cosmic Ray Showers.
total flux density of electronn and of punetratiniz particles is
determined by the formul*(r) -- 1/rn wit,, n - 2,0. On account of
the relatively slow decreane of flux densities of shower particles
the periphery of the shower playn an eonential part in the
general balance of the flux of the Bhower particles, The mechanism
of the transition of electronn to the periphery of the shower is
reduced to the Coulonb f)cattr.,r,nj- of tho3e electrons by the
nuclei of air atoms. The transition of Myoria to the periphery of the
ahe.wer is effected by their Coulomb scattering and also apparently
at the expense of the emingion in tho elementary acts of the
nucleus cascade proceau of th- pouitive and nei-ative myons pro-
duoing these myons, Finally, data on the intensity ?g primary q6V
cosmic particles with extremr-.1y high energies of 10 up to 10
are given. (10 illustrati,,-ns)
ASSOCIATION: Physical Institute "P.N',.Lobedev" of thn Academy of Science of the
U.S.SIR.
PRESENTED BY:
SUBMITTED:
AVAILABLE: Library of ConiTress,
Card 2/2

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AUTHORS: Broder, D. L., Kutuzov, A. A.9 SOV/89-6-5-19/33
Kondrashov, A.
TITLE: The Dependence of the Removal Cross Sections of H 20, B 4C,
C, Fe, Pb on 'the Energy of Neutrons (ZavisimoBtl eacheniy
vy-vodeniya H20, B4C, C, Fo, Pb ot energii neytronov)
PERIODICAL: Atomnaya energiya, 1959f Vol 6, Nr 5, PP 578-581 (USSR)
ABSTRACT: 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 cm, thicicneso
in the direction of the deuteron beam 115 cm). The first
was filled with boron carbide 11.1 g1cm3), which contained
the neutron source in a special channel. A second and a
third tank were connected with the first. During removal
Card 1/3 cross section measurement the material to be investigated

The Dependence of the Removal Cross Sections of SOV/89-6-5-19/33
H2 0, B4C, C, Fe, Pb on the Energy of Neutrons
Card 2/3
took the place of the third tank. The fission chambers# which
contain Th 232 9 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 am) of 9 cm thickness. The thickness of
the lead plates is, however, 9 and 18 cm respectively.
Measuring results;
material density removal cross section
g/cm3 a 4 Mev
E = 14.9 Nev
E
n n
H
0 1 0.165
to.008 0-084;tO-004
2
B4C 1.67 .
0-08L+O-003') 0-0581-0-002')
Fe 7.83 o.1691o.007 0-137@+-0-005
Pb 11.3 0.11 L+0-005 0-097-+0-005
+) from removal croon section measurements for boron carbide
and graphite, corresponding to the reciprocal relaxation

The Dependence of the Removal Cross Sections of SOV/69-6-5-19/33
H20, B4C, C, Fe, Pb on the Ener,7, of Neutrons
lengths at such distances, which correspond to 8-15 free
lengths of paths of neutrons in D 4C and C. The results ob-
tained are compared with those of 5 other publications
(table and diagrams)s and satisfactory agreement was found.
The method of removal croon 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. Orloy acted as advisers. G. H. Deryaging
11. 1. Dudkin, A. P. Klimov, V. G. Liforov, Z. ;. Blistanova,
A. I. Chusovj ani V. S. Tarasenko assisted in experimental
work. There are 2 figures, 1 table, and 7 references,4 of
which are Soviet.
SUBMITTED: January 21, 1959
Card 3/3

D. L. 101 tny. Leviz., '1189 -7-,* - 1128
7. V., Urlov, V. Tur--i:-ova, V.
The Passage of Faot Ncutrona Through Lead and Iron
-a,
Ator=Liya onorgi) 10511, Voli Nr 4, pP '@13-320 (U.-SSR)
The prooont paper gives tho results obtained by measuring the
spatial distribution of f4iit neutrons (originating from
nionoenergotic neutrons of the erergy E - 4 Mev and E - 14.9 Kirr)
and of neutrons of atomic reactors in ?ron and lead. hrst,
the experimental arrwigemento are discussed. The reactor of
the Pervaya atomnaya elektrostantniya (First Atomic Pawer
Plant), an experimental nuclear reactor of the VVR type with
ordinary water and enriched taranium. and a neutron generator
viere used as neutron so!lrcev. The spatial distribution of
neutrons in iror- and lettd wao measured Ly =eanv of a neutron
- rator, a neutron detector, and D- and T-targets. A
-erw
r32 27 27
Th fission chamber and threilin1d indicators (11.1 (n,p)Yg
P31 (n,p)Si 31 , and S32 (n, P) P32 ) were usod an detecters. Me
Carl 1/,7) distribution of thormal and epithormal noutronn was measured

The flasoage of Fast Neutrons Through Lead "d Ir-,n -OV/8@-7-4-1/28
by means of a U 235-fission chamber. Thoreaults of these
measurements in iron and lead are shown by 4 diagrams. The
authors then theoretically investi,3ate an infinite homogeneous
medium in which an unbounded, plans isotropic source of moac-
energetic neutrons with the energy Eo is located. Neglecting
the moderation of neutrcna in elastic scatteringt the kinetin
equation for the neutron colli3ion density ty(;,E) is written
down. The inelastic scattering is here assumed to be isotropi@.
The aforementioned equation is then transformed by means of a
Fourier transformation, and is uolved by employing the method
of spherical harmonies. The calculation is then followed step
by stop, and the asymptotic solution is explicitly written
dawn. A formula is written down for the neutron flux with the
energy E in a medium with point source. The reaulto shown by
come diagrazza for iron agree well with the experiment. The
same also applies to the results for lead. The computation
method suggested makes it posoiblo, if the differential cross
seat" of elastic and inelastic scattering of neutrons J@co
sufficiently well known, to detaraine the spatial- and energy
distribution of neutrons in thick layorn of matter having
Card 2/3 comparatively high nuclear charge numbers (e.g. greater than 56)

T@A; Pw37-ai;p of --"-.3t Neutrono 0 -@
With JUffiGiOW ftCC4Za.-'d. diotwices from the 30Urce,
the neutron 5pectr= -ii; enr'-e.',@ed v@ith considerably z3lcA7ed--
(iown ne,@tronr;. If tfie onr-'i@-j i!4-1txiUition is lzuiown, th,@ shield
mtK., ba calculateA ac-,or-lit,g tn the :,-.,Ati@-,roup theory. The
-.uthor3 thwik Profesac-r A. K. Kravin, Candidate of Technical
Sciences A. 11. Sorbinov, @u-.d ttio s-,lontific co-worker
V. A. Romanov f,@r their @-:lcstLrit interont in the present
paper ruid fz)r their in tl.e exporizent.
the authors thank V. 0. Z. j. bliatanov, ruid V.
Tara3enko for their assistzx.@@e in the experiments. S. A.
Kurkin assisted i4 vr*rVJr,;, Q-a crkl,.ulation method, and
M. B. Yogiazarw, V. 'J. V. 0. Madeyevo Ye. N, Forolov,
SiLd if, S. 111inshly furt..@.r @ouk part in th,@ experi.--ienta.
There tire 9 V-br.res wd '14 of which are Soviet.
January 21, 1959
C @Ir -I

21 .1310
AUTHOM., l3rudi,-r, D. L. , Yonflra;;h ),;, A. P. , Elit A. A.
laotioic, A. 1.
TITLE: El'fuct of Dtyu@v,;
Secoiclary Garfaria liacilatll@jn. I.;-*,*, t :- t
PD1,10DICAL: Atomriayu erif--vj@,,lya, 1,I)fO, V:)J- @,,, li.,- !, lip w"-:,l
(tjssl@)
AMTRACT: Since In moot; caw--.i ths@ wid @A' t'll" v t r: to r
.3 h I e ld I rl, 1 :3 do t. e I., n I I It @,,, 11 :" -
"
! i t ,: i i;. @ @ I I t
gwrima radiation, the a@itliovz. Iiive@;t1gateJ po-, -
sibility of redLl(,iTl,?' thlo capt,win:L In bcron
carbide the thennal t",w
11 L'@l t rolin captil red 111 L k" ll 1:;#-@ "Y - va y .3 o 1,
approximately 0.1-: mev, vinlAc. iteatrcrij uapt,.ire-l Iii
other buildin',, unat(.@vllalj, lu@,ilavly iteel, pnj-
duc,e hlt@h ener-Cj
Y-vafllatl@-, -
n. Ti;e
experlment Is gtlrt@h In Yl@@. 1.
Card IP

ECI'ect of layers Coritulnin,,, -i,
the Yield of Secondary Gamiria Ra(A s 0,[/ 0/2
L-,,",zer to the Editor,
Lj
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17
ILI 111111, -1
PIg I Geumet ry of'
Card 21o

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3/9

tll(! Yleld of' secoll(I'll"i Galluna Hadial-l-l"
Letter to the EdItor
T-T-F-- I
LLI 1 1 1 1 1 L 11'.

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3 2 9) 3
( 4 1 /@ I ,'(, @_ @; /.- @ :, 110 2 G / 0 3 3
A B 1 Ce /B 1() 2
AUTHORS: Brodtr, D. L., Kondrashev, A. Kutuz(jv, A. A.
TITLEs Spatial neutron distribution in i;Uxture3 ot' boron carbide
with iron and lead
Souftc@, Krupchitskiy, 11. A., ed. @1eytrolinn.,,-a fizika; -,bornik ntntey-
Moscovit 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 c3rbide. The fast neutrons were obtained from
interaction of 1-Mev deuterons with heavy ice (4-ljlev 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 c3rbide. In so:Le
of the experiments, tank 2 or tank 2 and 3 were replaced by laninated
iron or lead blocks. Other experiments provided steel and Ivad plates
between the tanks. Since the tanks were CT-50 (ST-30) ste el, all the
measurements were made with boron carbide "containing" 3,8,* by volume of
Card 1/2

_3 2991
S164116110010116@010201033
Spatial neutron distribution... B108/B102
iron. The results ohowed that iron and lead have simil ir re:aoval cross
sections. Substances with small inelastic scatterinj.@' cros3 sections, ao
boron-carbide, have greater removal cross section3 in watt:r th-li. in other
woderators not containin, -it w
g hydrogen. The ratio ol intt:r:. --fiiate all, 310
neutrons (E < 1 5 Mev) to the fa3t neutrons saa calculatt_@d It W'j-;
to be 5-56 for 4-14ev neutrons ana 2.r8 for 14-9-1.1ev no-utruns. '7 h t@
perimental values were lower and closer to each other. This i-. cue to a
lower sensitivity of the U 235 fission chamber at neutron energies i@ >IC@O,
kev. The authors thank Profe.,@sor A, K. Kri3in, V V Orlov, Canci,_;:It-,@ of
Physical and Mathematical Sciences, G. Ii. beryagin, N. N.
A. P. Klimov, V. G. Liforov, Z. S 3listanova, A 1. Ch,.ijov, V. S. Tar:l-
8enko, and R. G. Bulycheva for help. There are 10 4igares, I table, @n-
11 referencest 4 Soviet and 7 non-Soviet The four ruflerences to
English-language publicntions read as follows: 13liz-arci i@, P A na @t-
Nucl. Scl., 2, '13 (19W; bolditein 11 The at t-11-At lot, 0!* N@t
neutrons in reactor shield, NLCA, 11, Y,, 19)'j; Burgr..0113 I et al
and Experimental Coefficients Used in the Computation of :@elctor Snit.!,@i,
A/Conf 15/P/1190 France, 1958; Duggal V , Puri L.. j. kppi I F'-.ys , 2j.
675 (1958).
Card 2/2

3-,4-12
7 Ll 3/1 70/62/O05/002/0Q4/0':)
/1 12.41 0 0 B10,1,/B138
.2 -2.2 t/
AUTHORSt Broder, D. L., Kutuzov, A. A., Lovin, 7. 7.
TITLEi Shielding properties of water, polyethylene, %ni
PERIODICAL. Inzhenerno-fizicheskiy zhurnal, v. 5, no. 2, 196):), 47 - 51
I
TEXTs In IM effort to estimate the shiel4inp, action of hyrlro@@,@nouz; mix-
tures againit fast neutrons, the authors calculated tho distribution of
fast neutrons in hydrogen and water. The attentiation of a )tre:t,-,i of' 1"!uIt
neutrons in a hydrogenous mixture with the initial eni.,rr_"7 E can be cllcu-
0
lated from plif (E0) (I - O)rF
4) (r, E0 , E,;,) Q (E0)e fem 7 (E, E, dE, (1),
4 rc r' Erp
0) is the power of a point source of neutrons, is the volumc.
where q(E
. r) 13 the -.ectrii:.-. o'
part of hydrogen nuclei in the shield-, and 1., 1", 0, P I
moderqted neutrons. the results nro conni3tpnt -with H. Gold.-3t(_'in1!] (Fiinl,i-
mental Aspects of Reactor Shielding. Pergamon Pre:_,3, Lonlon-V@.iri.@I, 1T),!
Card 112

@a I
S/ I /On')
Shielding properties of ... B 104/ ii i ." 0
T1.e removal cross section for oxye,,-n wu3 obtuin,ldl frorn @istri-
bution of neutrons in water and hyllro,,-,en. For tLhQ 1,irpn7.,@ of
validity of Eq.(1), th.,, distribution of .4-%:(@v s-in! n..,.tr-n.i
ethylene nnd Ploxiglas was measured. Dc-ut,@riwq ;iril t-JtN::i
zirconium were used as tarrets, which were bombailr@l ;,ith :in-'. v
deuterons. The -experiments showel th,tt n shiell! t@-,tinnt neutr@ nf; of
0.2 - 15 Mev, connisting, of 0, C, Fe, ;inl Plb, C111) be c:11"111 @t.@A
neutron spoctrum In hydrogon, tho removal crwjo soeticn.,@ f@)r n-utrf.,r@@!
functions of energy, and the analoF,-ous cross svction;- for 'ron 1'1,1 1. i
Z. S. Blistanova, V. P. Bogdanov, G. V. Rykov, ani V. T. r,--.-nrrr_) r.;!
pated in the work. Thore are @, f ipuron nnI
non-Soviet.
SUBMITTED: April 17, 1961
Card 212

ILI 00 S/080/62/012/001/OC4/019
B102/Bl)8
AUTHOR-': Broder, D. L., Kayurin, Yu. P., Kutuzov, A. A.
T IT U i Passage of' gamma radintion throu#@h heturog-@neous :nedia
Pk-RIODICALs Atomnayu energiya, v, 12, no. 1, 1962, 30 - 35
TEXT: The buildup factor was measured f*-r heterogen-t-ous mvdia, consisti.ni.
of diffr ent combinations of* shieldinF materials (polyethylene, Al, Ft.,
Pb). Cogo was used as point source (r-,l g-equ. i(a, i@o . 1.25 Mev).
V.arious combinations of /v1O mm thick pl:1tes (Fe ,ind Pb: 7UO * 700 mm;
polyethylene (P) and Al: 1000 - 1OU0 mm) were inv,!:;tigated. A plastic
scintillator connected via a lightpipe to a @31J-2,j (FE.U-24) photomultiplier
was used as a detector, Dose rates were varied in the range 1 - jo5
relative units. Measurement accuracy was about t 1C@';. The following
combinations were investigated: (P) + Fb, (P) + Fe, Fe + Pb, Fb + (P),
Fe + (P), Pb + Fe, with the f'irgt mat(-rifil neareit to 11he 3QUrCe@ The
buildup factor was calculated by 'he empirical f'crmula
n n-1
B xi) B)I, x1) i B1, i@i th4: buildup f-ictor of
heter. n( 1 7- n
Card 112 n-1 i.1 n-2

'120-1
'JI08916216 12700110041019
Passa6u of' raciation ... B102/Bl,,,O
thu n-th matcrial, p,x, iH the lap-,r thicknt-nii in ter,as o, 1'ree. Patri
/@P) 0'661 cm @LA1 - 0 1"9 C 71 U cm
T Y-.,- b u i 16 u p f u c t o ra c% I cu 1 a t . d Y6 i t :i !'o i - @a u I , i a v- r Ld i t t h m c. a 3 u r r;
ones withir. the limits oi' experi:;..--ntal accar-:jry I t i:3 r,-Cc)::...,crac-d for
ujik.t*!ji..:i xii@ar 1 Illev A . L; li@.l @ i ji @i nul h L/
' V ifykov lre t jrik
@or as.- is n art-- 7 fiturk!:j --tnc: 7 :3oviut arld
':,aviet T h f-- r,@, f f, r;! n c e t o th e- " r, j !j t; - I - n;
riun-- i, Aj I i c i t i o r. r d s a s,
a a --y P, r L,, r , J o, t t i H4--a ;,-it, I Bu@ -'t,mdards , @6, 8'4
17, Ilt6l
U314ITTLD Aj)r i I
Cara 212

ERODER, D.L.; KUrUZOV, A.A.!, LEVIN, V.V.; FROLOV, V.V.
Application of "yield cross.-section" methods to the calculation
of shielding containing no hydrogen. Inzh.-fiz.zhur. 5 no.12t
65-70 D 162. (MIRA 160)
(Neutrons--Scattering) (Shielding(Radiation))

33234
@'.'!')O? o'), /01
.2 2 B 102// B 15
A7T7,'.OR3 Brod e r, D. L. , Kond raohov, A. @. _Kli t li
V. .'-, Sorgeycv, Yu. Turunov,
IT LF '.:,jltigroup met'hods of calculutinf,,
T )
Ator-maya enerf-ipi, v. 12, no. @, 1)t@:)' 1"I'l
T F: Y'l The spatial enerfry (I istribution for I)i.-)l oj-ic;il ;i:. 1- Id s i L,
calculated for a source tit a distance of 40 cm. Seven- anl
.-methodg are used and the calcl.ilations are made in.
diffusion approximat ions, respectively. An t`ie lower 0'
groups the iollowinr energie3 nere chocen for the :,cven-i )un
6 6 5 3
and 0 ev, anl '.'or tin et en 7
.5-10 , 9-10 4.5-10 , 3-10 3.31 E 1 m -ro,ip L/
me tho(I : 4 , 10 62.5-10 6, 6 5 5 5 103 t') , I , E
1.5-10 9 7-10 10 , ,,10 1 9 1 lim
anl 0 ev. Spectrum anI I-roup conctants are c@tlciil;itel fcr bo", f-rOIA:)S
and tht, reoul tj are comoarel @,,raphicul ly vii t'% vx!@Fr
ex-nerimentn -iere ma-1v -nith the critic.;il ans(-:71)ly c,l' o r: io,J
Card 1/5

33 23h
/089/62/0 12,/0 "W
3
i rrnli-) I n of c it I cu I -it ini@ . . . 5 1 o;?,/;i i
reactor wit'i- a wa. t e r r3ide ref lector. The s,.it_,1-l ii,v(_-J* i;-@tei tro
. pes (if !0lielfln eers@ ng
bottof.-. reflector. Three ty,
f)f @ieveral layer:j of various kinA!, of' steel, leiff, 1),ron c:irlilji@ arvA
!) 0 1 .-T e t hy I P n e . Tne neu t ron f lux i n the rinne@::l) I,,!, 7,;i@i re(j w i tn @i
llo@)per f0i I , tile hervi'l I -neut ron f lux in the core -., i t@j - coppor i rA i -i I ) r
Z.1nd in U 255 fission chamber, anl, in the experimentul assemblico, with .1
ropper indicator in it Cd contairiell. Co mna r i so n 1) e 1,N (, P n ro t i t,:i I -.@ TlI
PXT)eri,mentfil results permits the follo-Iiinif (1,)ncl,l!:iCll,3: 1) Tho
mu lti@.,,roup methods, and the r7rou p-cons t;j.,i ts @-Iiosen, ;jrc
--alculatini- the opatial distr'iblition of neutr@,.n enor!-Iv
contain@nf@ Fe, Pb and H. 2) For shielding syste--@i conl.%;nin@; I` tne
af;reement with experiment is within 20;' error li-it-
can alao Ile uned to determine the 2:)"itial I r '. 1 :)f f;i:,,
neutrons which is characteristic of -i'l-.ix I iLtricition
For a source emitting ?,-','cv neutrons an:1 -.%ith larrv
th(@ ten-rroup results fliffer from the experiment;Ll one!-, 1 v -@,re
Gii.,ilichina, L. V. Mlarchenko, 7. 1). S0lf010V.L, I 111 t;1 110 V%
ariff A A n ta V h o vit took ;)art in tile C,Iloo lilt lorl:j, 1 !3 1 .11 and R
Car@ 2/5

332Nt
S/O A )/02 /0 1
@.:'l It It: roll T) met hol!) of ca I cul It t i rii-.
G. Rulycheva in the experiments. The reactor team Y'-)rjz')v,
Yo 1. inyutin, V. K. Labuzov aril N. il. Uvarov are thankeJ for tn' eir iior@
There are 4 fi"reu, 1 table, and 12 reference.-i: '( Soviet and ', non-Soviel
The reference to the Enpli3h-lanmiape publ ic,,it ion reni.-. '..i "CO D.
nlwtiv@i, L. Harvey. Nelitron cronn. nection, l)-.
Anril 17, 1961

BRODER, D.L.; KAYURIN, Yu.P.; KUTUZOV
Calculating the factors of, @Lray build-up in heterogeneous mediao
Atm.enerrg. 13 no.62593.-D5 D 162. (MTRA 15,12)
(Gamma rays) Okoloar reactions)

ACCESSION NII: AT4019031 S/0000/63/000/000/0052/0060
AUTHOR: Brodor, D. L.; Kutuzov, A. A.; Lovin, V. V.; Frolov, V. V.
TITLE: Application of the "removal cross section" method to the computation of non-
hydrol,en-containing shielding
SOUTICE: Voprosy* BMW zanhchity* reaktorov; nborrilk nLaUey (Problems In phynIcB of
reactor shiolding; collection of articles). Moncow, Goantornizdat, 1963, 52-60
TOPIC TAGS: nuclear reactor, reactor Milelding, iron shielding, lead shielding, non-
hydrogenoue shielding, romova.1 crostj necdon, neutron, neutron spatial distribution,
neutron decelerator, aluminum shielding, boron carbide
ABSUIACT: 'llie authors first briefly describo the removal cross section method for the
,en-containing nhieldin
coinputaLion of the spatial dinLribution of neutron ntreanin in hydroj,
Some of the limitationa of the method are diticussed along with an analysis of the difficulties
often encountered in Its application (for example, In hornogoncou6 mixtures). The h)-,).othef3lfj
has previously been advanced that, by prencinding from the question of tho accumulation of
low-energy neutron s, the removal croso section tecluilquo ralght be applied to mcdi,l
Card
I __ A

ACCESSION NR: AT4019031
containing other light deceleratorij in place of hydroj;on. III (hi%o pruvinwi ifivf'-@Jfgafionlj,
boron Carbide in a mixture with Iron :knd lead wa,,i stwiied as the dreelerator. Some of
the findings of this research are discussed in the present article,which also given addiLional
experimental data which prove the feasibility of extending ano' generalizing th'e removal
cross section method to leavler slowing media. Aluminum was employed a!i the decelerating
medium in the tents reported on In thin paper. Neutron sources with E' = 4 Mcv and 14. 9 Mov
Nvero used. In addition, measurements Won, 111adv of tho rcilloval eross sv(-tiolui of iron and
lead in boron carbide in the fission neutron spectrum and the removal cross section of iron
In the Bpec m of the VVR reactor. As neutron sources the authors used the reactions
@ru 4 (E ,%Iev),
-i D (d, n) fie with ar@jpjtlal neutron energy of E = 4 Alev, and T (d, ti) Ile
U. 3 .
and also a disk of 0 removed from the reactor of the Porvoy v mire atomnoy clektrostants
(World's First Atomic Power Station) mid placed In a 8trearn of thermal neutrons. The
sourcos were In tho form of disks with a diameter of 10 cm for the Diono-energeLic neutron
sources, and 46 mm for the fission Bpoctrurn sourco. Fast neutrons were detected by
means of a fission chamber with 7112,32. Further details on the experimental apparatus are
given in the article. Graphs are preBented showing tho spatial distribution of the fast
V4
ard

ACCESSION NR: AT4019031
neutrons In different substances and mixtures, as well as the dependence of the removal
crofm sections of Iron and load in aluminum (and of polyethylene and plexiglass In aluminum).
fr.,- neutrons with E - 4 Mov and 14. 9 Mov on various controlled experimental factors
(distwica, between nourco and detector, dintance between block of remove(] material and
detector, etc). A talAc is given showing removal cross tiections measured in water, boron
carbide and aluminum. It is shown that the removal cross section method in applicable to
the computation of shielding in which other light media are employed as docelevators in
place of water: for example, boron carbide or aluminum. 'nio magnitudo 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 UBO Of the removal cross section method to possible provided the removal
cross section of the material in the given medium is known or if the lower boundary of the
energy group ]a substantially raised. Several other significant conclusions are discussed
in the article. 117be authors Uumic V. P. Bogdanov, S. G Osipov, 0. V. Ry*kov, V..&
Tarasenko and A. 1. Chuoov for taking part in the measurements. 11
3/4

.ACCESSION NR: AT4019031
ASSOCIATION: none
SUBmiTTED.- 14Aug63 DATE ACQ- 27FcbG4 ENCL: 00
SUB CODE: NP NO REF SOV: 007 OTHER: 003
Cryrd 4/4

ACCESSION NR: AT4019032 8100001631000/GOQ(006(k(0074
AUTHOR: Droder, D. L.; Koadmehov, A. P.; Kutuzov, A. A.; Naumov, V. A.; Sergeyeve
Yu. A.; Turusova, A. V.
MTU-. An e3qmrimental Jugfflcation of multigroup Tnethode for the compu" of biological
shielding
SOURCE: Voprosy* fiziki zashchity* reaktorov; sbornik statey (Problems in physics of I
reactor shielding; collection of articles). Moscow, Viosatomlzdat, 1963, 60-74
TOPIC TAGS: nuclear reactor, reactor shielding, neutron scattering, removal cross
section, biological shielding, neutron, neutron distribution, mulUgroup method, diffusiod
approximation
ABSTRACT: The authors note that the computation of biological shielding involves the
determination of the space-energy distributions of the neutrons In media containing light
and heavy nuclei. A number of methods, based in one way or another on the solution of
kineLic equations, have been developed to meet this need. Several of them are briefly
examined and criticized. In the present article, two methods of solving the problem are
conoldered- a 10- group and a ?-group method in a diffusion and diffusion- ago approximation,
Cord 114

ACCESSION NR: AT4019032
respectively. 'I'lie applicability of this kind of approximation for shielding computations
is not evident if strong absorption is present. Hydrogen slowing also complicates the use
of there methods to a considerable degree. Neutron scattering with non-clastic collisions
is Isotropic, while the anisotropy of elastic scattering may be corrected by introducing the
transport section of the scattering. At lower energies, elastic scattering becomes more
isotropic and absorption processes begin to play an Important role only in the lower groups.
On the basis of this circumBtanco, an attempt was made to justify experimentally the appli-
cability of the methods of computation discussed In this article to the spacc-energy dis-
tribution of neutrons at any distance from the source. Ile 7-group method was developed
for the purpose of introducing certain corrections and improvements Into the calculations
of the fast neutron groups. Ile basic Idea resolves Itself to the assignment of the spatial
distribution of the group of fast neutrons with energy E > 1. 5 Mev by the somiempirical metho
of "removal cross sections" with subsequent computition in a diffusion-age approximation.
Ile authors note that it has been demonstrated that the difference in the results of calculationi
in the ago approximation and the exact solution even for water, at such distances from the'
source no Justify an ago approch, does not exceed 30%. 71do fact given rise to the hopo
Card Z/4 /

ACCESSION NR: AT4019032
that the results of the computations described in thic article will be favorable. T1.o
refinements described in the paper deal only with t1w neutrons with energies above 1. 5
Mev, since it Is these neutrons, as a rule, which deimr7nine the spatial distribution of the
neutron streams. Both computation methods were applied to the computation of three
varieties of BWelding, of rather small thickness, both with and without boron. The purposo
of the introduction of the boron was to study the prob:lems of the applicability of the diffusion
and diffusion-age approximations to the computation of shielding with different neutron
absorption in the thermal and superthermal regions. Ilese same varieties were investi-
gated experimentally. According to the original intention, the simplicity of the method was
to be expressed in the relatively small number of energy groups. llowc;,er, the transitiQn
from a larger number of groups to a smaller was natural and, for this reason, 7- and 10-
group systems of constants were developed. In the first sections of the article, the selection
of groups In the 7- and 10-group methods and the neutron spectrum in the 10-group method
are considered. Basic equations and group constants forthe 10-group method are presented
and discussed In a further section, after which the results of the 10-group computations
are analyzed. Ordy after this are the basic equations and group constants of the 7-group
method dorived. The experimental check of the computations was made with a reactor
having a waWr decelerator. Toot conditions are described in the article. lbo authors
Card 3/14

FIN
ACCESSION NR: AT4019032
found that both the 7- as well as the 10-group method and the selected systems of group
constants may be used to compute the space-enorgy distributions In mixtures of iron with
water and lead at the thickness considered in the study. noise methods yield satisfactory,
results (within 20%) for boron- containing media; for example, in boron steels. In the
present work, a direct experimental confirmation of the greater accuracy of the 7-group
method in comparison with the 10-group technique was therefore not obtained.' Orig. art.
has: 17 formulas and 8 figures.
ASSOCIATION: none
SUBAUTTED: 14AugG3 DATE ACQ: VF664 ENCL: 00
SUB CODE: NP NO RE, F SOV: OOG OTHER: 006
Card 4/4

ACCE'SSION NR: AT4019049 S/0000/63/000/000/0198/0207
AUTHOR: f3roder, D. L. -, Kayurin, Yu. P.; Kutuzov, A. A.
TITLE: The pafigago of Garnma radiation through heterogeneous media
3 7
SOURCE: Voprosy* fizild zashchity* reaktorov; sbornik statcy (Problems in physics of
reactor shielding; collection of articles). Moscow, GoBatomizdat, 1963, 198-207
TOPIC TAGS: nuclear reactor, reactor shielding, Iron shielding, lead shielding, Gamma
radiation, Gamma ray attenuation, Gamma radiation shielding, Gamma radiation accumu-
LtLion factor, polyothylene shielding, aluminum shielding
ABSTRACT: 'nic authors note that the computation of shielding against gamma-radiation
requires a knowledge of one of the essential characteristics of the material - the
%-,jd1aLiQn accumulation factor. For homogeneous media the accumulation factor B(E , x, z, g)
@ s a function of ltl'w- initial energy of the -/ -radiation E , the thickness of the materiA X, .
the ordinal numbor of the substance z, and also the fo& of the source g. The significance
of the accumulation factor for such homogeneous media Is discussed In some detail. Some
recornmendationij, based on general physical considerations, with respect to the computation
C--,d 1/2

ACCESSION NR,. AT4019049
of accumulation factors for heterogeneous shieldings consisting of two materials arc
analyzed. An experimental determination is mado of the dosc accumulation factor for
heterogeneous media, consisting of various combinaLlona of materials (polyethylenci
al.uminum, Iron, lead), and forr-quanta energies of 1. 25, 2.76 and ca. 6.4 IMov. As the
source of they-quanLa with an energy of 1. 25 Mov, COGO was used; for the quanta with the
2. 7 6- Mev energy level, Nft24 was employed. In order to obtain tho high-energy (G. 4 Mov)
),-quanta the authors made use of an F 9 (p,co( )016 reaction. On the basis of the experi-
ments with C060and general physical considerations, an empirical formula was derived
for the computation of accumulation factor In a heterogeneous mcdIjim consisting of any
number of layers of different materials. The experiments with Nal and the G. 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
SUB CODE: NP
DATE ACQ: 27FobG4
NO REF SOV: 004
ENCL: 00
OTHER: 004
'Cbrd-
.2/2

--..M(A(h)/ZdT(m)_ Ift
ACCESSION M A?5012480 uVoo8-9/65/018/004/0404/0408 ;23
621-039-538.7
Ito
I AUTTIORS: BrQder, D. L.; Zhilkin A. S.; Kutuzov, A. A.
t
TITLE: Spectra or fast neutrons.,in heavy media and in water
ISOURCE: Atomnaya energiya, v. 1 no. 4, 1965, 404-408
TOPIC TAOS: fast neutron, neutron moderator, water moderator, iron
moderator, lead moderator, neutron spectrum
ABSTRAGT: The main purpose of the investigation waB to determine'
@
!the behavior of the neutron spectrum near the interface between a
heavy medium and water, such as occurs in the construction of some
lbiological shields. The authors measured with a scintillation speo-
I tror:ieter-the~-spec-tra-~of--maderat--d-n,-.it;-O-----i.-.- _Jron,--lead-4.n,dwat-er--
F@ehind a layer of iron and lead. The @eu-trans came from monoenergetia'
isourcea of 3.4 and 15 MeV energy. Me spectromter used was a stil-
bene crystal in conjunction with a FEU-1@ photomultiplier and an
iAl-100 pulse-height .analyzer. The measurements were made. in priams
Card 1/3

L 58753-65..
ACCESSION HR: AP5012480 '7
of iron and lead measuring 110 x 710 x 600 mm. When measurements
:were made with water, the Iron and lead layers were located between
Ithe target of the accelerator and a tank with water. Plots of the
:,s.pectra In iron, lead,,Iiron and water, and lead and water are present-
ed for the various energies. In the case or iron alone, the spectrum,
did not agree with earlier calculations, probably because or the
oversimplification of the latter. The spectrum of neutrons in lead
l
idoes agree with earlier calculations. In the case of water-iron and
water-lead shields, the spectrum of the neutrons at a considerable
1distance in the water behind the layer of the lead or the shield
1differ8 appreciably from that of the neutrons in pure water at the
loame distance, being richer In scattered and slow neutrons than in i
;pure water. This is attributed to the softening of the spectrum in
!the metal and is in good agreement with the evaporation model of in-
@elastic scattering at the neutron energies involved. fThe authora
ithank V. G. Zolotukhin, B. A. Kalmykov, V. 1. Lobanov Mi. P.
lTarasko V, Ye. T V. Shestopalov for help with the work,
yrkich, Ye
L*_ Trykov for a disou-s-sion of aults of the work.t
Card 2/3

A,CCEOSION NR: AP5012480
Ipriginal artiole has: 6. rigurea
1ASSOCIATIONt None
;UP14ITTEDI, 08jun64 ENCM 00 SUB CODE: NP
R REF 030V: 0031. OTHER: 002
Card

L 27477-66 EWT(1)/T 1JP(c)
C IqR: Ai6oo842o SOURCE CODE: UFV3158165100010231000WO012
AUTHOR: Zolortukhin, V, a.; KutuZovp A. A.; Broder, D. I.; Khamlyancvp L. P.;
Yefimenko, B. A.; Ohil)dn, A.--�..
ORG:
None,
TrITLE: Analysis and generalization u! the correlation method of measuring the
-@-jarticle lifetime distribution in a physical system
i I
iSOURCE: Obninsk. Fiziko-energatiches Doklady., no. 21,, 1965p Ananz
)am UituiLts.- I
I obobshcheniye korrelyatsionnogo metods, izmereniya raspredelenlys, vremeni zhizni
chastits v fizichiekoy sisteme, 1-32
A13STRACT: The authors present a complete statistical analysis of the correlation
method of measuring the distribution of the lifetime of particles in a linear
physical system. The method Is reduced to a determination of the mutual correla-
Ition function between a pseudorandom signal used to modulate the intensity of the
measured particles coming from the source,, and the counting rate of the detectors*
iIt is shown that the statistical accuracy of the method depends both on the off-
duty factor of the modulating random signal and on the presence of a nolse back-
i Card 1/2 ... ... ..

L 27477-66
ACC NR: AT6oo842o
ground against which the measurements are made. In particular, it is shown that
Ithe conclusions made by T. E. Stern et al. (J. of Nucl. An., p.A/B, 16, 499, 1962)
that the use of random (or pseudorandom) excitation can completely reduce the
measurement time compared with the classical method (ordinary periodic excitation)
is valid only when there is an appreciable background. When there is no backgroundo
on the average the statistical accuracy of the classical and correlation methods
is approximately the same. A new method of pseudorandom modulation of the particl.
source is proposed, to take advantage of this fact. If the modulation is made
coherent with the background noise, then it can be readily shown that the fast COM-1
ponent of the background can be readily eliminated in the same manner as in the
classical method,, and the slow component can be eliminated by suitable choice of
the off-duty factor of the modulating signal. This type of statistical modulation
1prevents loss of the peak value of the modulated intensity and thus permits the
use of the peak power of the source and retain the favorable advantages of the
correlation method, Orig. art, has: 6'figures and 13 formulas.
SUB CODE:. 20/ SUBM DATE- 00/ ORM IW: 001/ OTH REF: 002
Card

L 01@046_67 F.1,11r(m)1Yx1)(t)1zrj
ACC NR, AT6027924 SOURCE CODE: U11/0000/66/000/ooo/ooM/0103
AMIOR: Broder, D. L,; Zhilkin, A. S.; Kutuzov_, A. A.; Suvorov, A. P.
ORG: None
TITLE: Spectra of fast neutrons in heavy homogeneous media
:SOURCE: Voprosy fiziki zashchity reaktorov (Problc@as in phynics of reactor shielding)
isbornik statey, no. 2. Moscow, Atomizdat, 1966, 88-103
TOPIC TAGG: fast neutron, neutron energy distribution, radiation shielding, neutron
@scatterinf;
ABSTRACT: The spectra of fast neutrons in Iron and lead are measured directly and the
tasymptotic spectra are calculated in tile P4-th approximation of the method of spherical
1harmonics using recent measurements for tile excitation functions on individual levels
'in iron and lead. Approximate account is taken of neutron mo(I-ration, in elastic scat-
tering, anti anisotropy due to direct interaction in inelastic scattering. Experimental
measurements of the spatial energy distributions of neutrons were done on iron and lead
!specimens measuring 7lOx7lOx6OO mm. Two reactions were used as neutron sources:
iT(d,n)He4 (14.9 mev) and D(d,n)He3 (3.35 mev). Since the deuterium target had a thick-1
:ness of 20 mg/cm2, the resultant neutron spectrtun in the latter case is not monochroma-I
,tic. This fact wan taken into consideration in the calculations. The neutron spectro-,
Card 1

L O@0,146-67
ACC NR,
,meter was a stilbene crystal combined with an FEU-13 photomultiplier and a 100-channel
@amplitude analyzer. The theoretical and experimental spectra for iron and lead arc
t
icompared and show generally satisfactory agreement. Orig. art. has: 9 figures, 1
;table, 32 formulas.
SUB CODE:1.9,201 SUBM DATE: 12Jan66/ ORIG REF: 011/ M REF: 010
Card 212

1i _67 _Ewr
An 14R, A,,,6027925 SOURCE CODE: UR/0000/66/000/000/01014/01!6
AUTHOR: Broder, D. L.; Zhilkin, A. S.; Zolotukhin, V. G.; Tarasko, M. Z.- Kutuzov
A. A.
ORG: None
TITLE: Fast neutron spectra in metal-water shielding
,SOURCE: Voprosy fiziki zashchity reaktorov (Problvms In p-hyuicti of reactor sh-ielding),,
sbornik statey, no. 2. Moscow, Atomizdat, 1966, ioh-n6
TOPIC TAGS: faut neutron, rmUntion shit-lding, nt-lit-roll srecti-ILM
,AB5TRACT: The authors study the spectra of neutrons -in the enerKY rani!,e filove 1 mev
from Durces W.4h energies of 3.35 and 111-9 :'.1ev in water an-1 in water behind layers of
iron,Xd lead..'111A scintillation spectrometer with a stilbene crystal was used for the
measurements. The sensitivity to y-quarita was reduce(i 1,y tLme livision of irradiation.;
The reactions used for th neutron sources D(I jjf,3 produced by
t1re n) . ant,@
f1i A
using deutrons to bombard Airconium-tritium Ajid targr!ts with a
2. -uremeiiLn In water, %he source wa:-@ loc ted
thickness of 18 ffg/cm F@r the meas n in a
Paraffin block placed In direct contact to the wator tn,;'K. The overall dimensions of
f.he ohielding were 710x7IOx60O mm. The scintillation niectremvter wfis cmbined with
an FEU-13 photomultiplier and an Al-100-1 runplitude analyzer. Tite r0B11ltB shcw that
@i Card__1/2

ACC NR; AT602T925
Lne neutron n1je@ctrum fret.1 It tnrTV)Ciir(xWAJc so,irco it, 1-@iol ltril irorl (lifforl;
Irom til:kt, ill wiltur. T) I e 1 ro ;Illd I"lid ;Iv.w@; it rfj!o:(@ntratior, of low-
ellf-@rgy tv.-uLruns (