ENTRY 40081 20150910 41704008100000001 SUBENT 40081001 20150910 41704008100100001 BIB 14 49 4008100100002 TITLE Measurement of the cross section for fission of U-238 4008100100003 by 2.5 MeV neutrons, by determining the neutron flux 4008100100004 by the method of accompanying particles 4008100100005 AUTHOR (I.M.Kuks,V.I.Matvienko,Yu.A.Nemilov,K.A.Petrzhak, 4008100100006 Yu.A.Selitskii,V.B.Funshtein) 4008100100007 Yu.A.Selitskii=Yu.A.Selitskiy 4008100100008 INSTITUTE (4RUSRI) 4008100100009 REFERENCE (J,SJA,30,64,1971) Eng.Trans.of AE,30,55,1971 4008100100010 (J,AE,30,55,1971) 4008100100011 SAMPLE Uranium-fluoride was placed on aluminum foil(natural 4008100100012 uranium). Sample thickness was 0.1 mm and sample 4008100100013 diameter was 19.0 mm. Uranium isotope composition was 4008100100014 checked on alpha spectrometer. Uranium weight was 4008100100015 about 10.0 milligrams and was determined by alpha- 4008100100016 activity layers measurements 4008100100017 MONITOR Absolute measurement 4008100100018 FACILITY (ACCEL,4RUSRI) No information available 4008100100019 METHOD (ASSOP) Direct detection with neutron flux 4008100100020 determination by method of accompanying particles 4008100100021 (FISCT) Stack of ten layers of U and 5 layers mica, 4008100100022 each mica layer registered fragments from two layers. 4008100100023 PART-DET (FF) Fission fragments 4008100100024 DETECTOR (SOLST) Five mica layers recorded the FF from ten 4008100100025 uranium layers. 4008100100026 Registration efficiency (96.0+-1.0)% . 4008100100027 (PROPC) Neutron flux was determined by He-3 4008100100028 proportional counter with low pressure 4008100100029 ERR-ANALYS (DATA-ERR) No information available 4008100100030 CORRECTION Corrections were introduced on 4008100100031 * efficiency of fission fragments registration by 4008100100032 mica 4008100100033 * account from uranium-235 fission fragments - 2.0% 4008100100034 * shape correction was 1.0% 4008100100035 * irregularity of neutron flux density in uranium 4008100100036 layer limits - 2.0% 4008100100037 * correction on fissions by scattered neutrons - 4008100100038 limits - 4.+-1 % 4008100100039 * correction on efficiency of neutron flux 4008100100040 registration and its change 4008100100041 * count-pulse amplitude analysis - (2.0+-1.0)% 4008100100042 STATUS (TABLE) Numerical data from AE,30,(1),55,1971, p.57 4008100100043 HISTORY (19711122C) 4008100100044 (19870712U) Institute code corrected, several keywords 4008100100045 changed, ISO-QUANT into REACTION converted 4008100100046 (20141115A) SD: Updated to new date formats,lower case.4008100100047 Ref. on Engl.transl. of AE added. 4008100100048 (20150910A) M.M. Article was checked, BIB information 4008100100049 was updated in TITLE, AUTHOR, CORRECTION,DETECTOR, 4008100100050 METHOD. Subent 003 was added. 4008100100051 ENDBIB 49 0 4008100100052 NOCOMMON 0 0 4008100100053 ENDSUBENT 52 0 4008100199999 SUBENT 40081002 20150910 41704008100200001 BIB 2 3 4008100200002 REACTION (92-U-238(N,F),,SIG) 4008100200003 INC-SOURCE (D-D)Thin deuterium-titanium target on molybdenum foil 4008100200004 with 0.3 mm thickness was used 4008100200005 ENDBIB 3 0 4008100200006 NOCOMMON 0 0 4008100200007 DATA 3 1 4008100200008 EN DATA DATA-ERR 4008100200009 MEV B B 4008100200010 2.5 0.55 0.02 4008100200011 ENDDATA 3 0 4008100200012 ENDSUBENT 11 0 4008100299999 SUBENT 40081003 20150910 41704008100300001 BIB 5 8 4008100300002 REACTION (92-U-238(N,F),,SIG) 4008100300003 INC-SOURCE (D-T) 4008100300004 METHOD This CS was measured to test reliability of setup 4008100300005 working. It's compared and agrees well with data from 4008100300006 W.Hart,Authority Health and Safety Branch, UKAEA, 4008100300007 R.(1969), p.169. 4008100300008 STATUS (PRELM) 4008100300009 HISTORY (20150910C) M.M. 4008100300010 ENDBIB 8 0 4008100300011 NOCOMMON 0 0 4008100300012 DATA 3 1 4008100300013 EN DATA DATA-ERR 4008100300014 MEV B B 4008100300015 14.1 1.13 0.04 4008100300016 ENDDATA 3 0 4008100300017 ENDSUBENT 16 0 4008100399999 ENDENTRY 3 0 4008199999999