SCIENTIFIC ABSTRACT PETRZHAK, K. A. - PETRZHEK, I.

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CIA-RDP86-00513R001240630007-8
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RIF
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S
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100
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November 2, 2016
Document Release Date: 
June 15, 2000
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7
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Publication Date: 
December 31, 1967
Content Type: 
SCIENTIFIC ABSTRACT
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,r za TI u T na V,, Sul' f 1 C I e t , a Df an C iS,DtO',,-e.- an, in SS I L F, i r 1f e . L. e r - V .. i f c Ui -- d e e r: - F ' 3 nC e 411 U p r r - - ,33 f meas f is C, t,D - e. le a rn i.. ~.re to In t"I's Card 1/4 :aaximum eLer6y cf t 1-1 `2 e r ~.-a . T:.e Erl i L. of a r ca., :,a -a n a r a'_11 W'a 1: Ll r Ail A V; D S El a r 1 so r W-'j'- f f r 3 J c w r, in Card ~~/4 The Efficiency ol" an End-diridow Coun'-----.- al~ -4 F-unct:ior of P-Spectrum tLe absolute cou-nting efficiency is snown as a faricL-m 01 t:- surface density of the speci:7!en for various ener.-i-s. Ex -ents show that the absorption witlim the slec~.men ~;trjn--Uly depends on the maximum ener,~y in the O-s,)ectram. T i s e ffe r t reduces the efficiency by a factor of 3 for low ,,3,:-a- tion. For high ener,-y radiation (of r2ie order of I I'LI'l) the efficiency is in-ie~,endent of surface U4en3-L-7 ra,----- "Pae -fl ic)enc,,r at a z:-iven sity may be re~,rese:-ted aS a -fu-nz!r--)r. of t:-F! :2ax-- E- ol the O-emizter. Tv---Js is s,..ov;-- 4--, F-'~: f-3r cDnS4StF Of ~Wo v-,:r- er th'-:~,,~. T C sections. Tne firs,~ shows tne very of The efficiency on ener,~-y u- to, 3ay. NIeV ar-.1d ',~evor-` triis point y i. s iride-,,enclent of t..e enerj7,y of the it follows fro.,:,, F1-- ~x rro- th- a-wsolate efficiency for-:, ,f T~v,--~ sin,~e different v;-r- 'o T)Int this Tije roiaLive soled an,-,-Ie of' tl-,e Card 3/4 a a F,~I. t ~ D:~ L o-IL' P-Spectrum was 0. 111 Triere a--- - f I -i I table an, r o "'d 1 i 3 E: i --, i I--- 7 SUBMI'2'.ED: Janu-,i.-y Ca-rd 4/4 ROMANOV, Yu.F.; PE~BZRAKP K.A.; RAK, M.A. Cadmium ratios for Ag I(Y7 and Agl('9. Trudy Radiev.insi.!Y SSSR 9:84-86 159. 14: t ) (Si,lver-jeotopes) (cadmium) BPKP M.A.; P=HAK, K.A.; ROMANOV, YU.F. Amlysim of a neutron field of unifora density. Trudy Radiev.inBt. AN SSSR 9:87-90 159. (KMA 14 r6) (Neutrons) KRAZOV, Yu.L.; BAK, M.A.; Ph7RZRAK, K.A.; ROIWIOV, YU.F. Energy distribution of neutrons in the water surroundin the source. Trudy Radierv.inst.AN SSSR 9:91-103 159. 1012:RA 14: 6, (Neutrons) F01400V , Yu.F.; PETRZHAK., K.,L; BAK, M.A. Measurement of the diffusion length of thermal neutrons in water, Trudy Rudiev.inat.AN SSSR 9:104--106 159. (.1-fJPA -14: ~ " (NoutronB) BAK, M.A.; GORSHKOV, G.V.; MA';VIYKNKO, V.I.;-Ph7RZHAK, K.A. ; ROMAROV, YU.F. Radon neutron sources. Trudy Radiev.inst.AN SSSR 9:107-1-12 159. ( MCLEA 14 - 6 ) (Neutrons) (Radon) BAKY M.A.; GORSHKOV, G.V.; MATVIY11TKG, V.I.; P-P,7RZHAK, K.A.; SHIMANSKAYA, N.S. Determination of the neutron yields of the sources R&+ Be, AC + Be. MaTh + Be, and P + Be. Trudy Radiev.inst.AN SSSR 9:120-125 .*059. (MIRA 14:6) 1. (Neutrons) BAK) M.A.; PhTRZHAK, K.A.; ROMANOV, YU.F. Wall effect in ionJzation chambers. Trudy PAdie"v-inst.AN SSSR 9.192 206 159. Olal~A L4 6; fTonization ch&mbera) MALKINP I.Z.; PETRZRAK, K.A.; YAKOVLEV, V.A. Effect of &lpha-p&rticle reflection during measurements i-n a 277 sol-id angle chamber, Trudy Radiev.inBt.A1,EBSR 9:207-213 159. (MIRA 14.6) (Alpha rays) (Ionization chambers) &JGO;-AOV, S.S.; MAMIN, L.Z.; FETRZHAK, K.A.; YAKOVLEV, V.A.; YAKUNIN, M.I. Ionization chambers for 9(-particle counting. Trudy Radiev.inst. AN SS3R 9:214-228 159. (,MIRA 1-4: 61 (Ionization chambers) (Alpha rays) --UjRZHAK, K.A.; NIKOL'J"KATA. Te.B.: PETROV, Tu.G.; SHLYAMIN. N.A. Pospibilit7 of using a method involving thq slowing down and colloctlon of fission fragments of gag for t)o Rtvidy of frag-iont isotopes. Part 1: Radlochnnical study of the distribution nf frag-nents fron their paths. Raiinkhlmita I no.2:227-210 159. (MIRA 12:8) (Fissinn products) nM . e Y, 21(8) AUTHORS: Bak, M. A., Bugorkov, S. S.P SCV/89-6-5-18,:33 Illinskaya, T. A., Petrov, Yu. G;1 Petrzhak,-&, A., SolntBev, V. M., Sorokinat A. V. Ushats iy, V. N. TITLE: The Yield of Ru 103 and Ru 106 in the Fission of U 235 and Pu 239 by Fast Neutrons (Vykhody Ru 103 1 Ru 106 pri delenii U235 1 Pu 239 bystrymi neytronami) PERIODICAL: Atomnaya energiya, 1959, Vol 6, Nr 5, PP 577-578 (USSR) ABSTRACT: The yields of Ru 103 and Ru 106 were determined by means of a relative measurement with respect to the Mo99-yield. Uranium oxide (U 235_enrichnent > 90 %) and plutonium oxide were pressed in aluminum caskets. The latter were surrounded by a 1 ram thick Cd-sheet, and the whole was packed in a firmly closed aluminum cylinder. The cavities are filled with boron carbide (all-round thickness at least 2 cm). Two samples were made from uranium and 4 from Plutonium, and were irradiated for 52.2 hours in a water-filled beam tube of the heavy-water reactor of the AN SSSR (AS USSR). Card 1/3 The neutron spectrum is characterized by the ratio The Yield of Ru103 and Ru 1o6 in the Fission of sov/69-6-5-18/33 U235 and Pu 239 by Fast Neutrons En > 1.5 Mev : E n> 2-5 Mev - 4.0 + 1.5. From the irradiated samples Ru and Mo was chemically separated, after which thin P-preparations (thickness