SCIENTIFIC ABSTRACT -

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SCIENTIFIC ABSTRACT
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- 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 qt aq j a jR OVA 0 ito 24 . @!! :4 44 j zi V no on j awl 4 3 As 16 ed M 16 H 13 a A 21(8),21(7) 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 JIN 17 ILI 111111, -1 PIg I Geumet ry of' Card 21o 0': L I CL I L I I"id i t f II I I , t 1, L b I 1, 1, (-)! Iw: I: t ti. Fj 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'. I I I I L i t Illea :I ;Iv ('111'- 11 '.-1 r I v t, I I [V I 'IA t rX Yj Id to 10 Ic ?0 9.0 p Oito I.e.) a? i, CLI L I C L L I f f I I I I I In: j I 3Ml I P ED ca ! 'k I v I') 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 (