ENTRY 41605 20150220 41684160500000001 SUBENT 41605001 20150220 41684160500100001 BIB 13 45 4160500100002 INSTITUTE (4ZZZDUB) 4160500100003 REFERENCE (J,YF,24,(3),473,1976) 4160500100004 (J,SNP,24,245,1976) Engl.transl.of YF,24,(3),473,1976 4160500100005 AUTHOR (A.G.Popeko,V.I.Smirnov,G.M.Ter-Akop'yan,B.V.Fefilov, 4160500100006 L.P.Chelnokov) 4160500100007 TITLE Multiplicity of prompt neutrons in spontaneous fission 4160500100008 of U-238 . 4160500100009 SAMPLE No information. 4160500100010 METHOD (COINC) Coincidence of FF and neutrons . 4160500100011 DETECTOR 1(PROPC) 28 proportional He3 ( pressure 7 atm) filled 4160500100012 counters ( detection efficiencies from 0.21 to 0.38 ) 4160500100013 in paraffin block. 4160500100014 Counters of 500 mm length, 32 mm diameter. 4160500100015 Was used as neutron detector. 4160500100016 (IOCH) Ionization chamber was placed inside of neutron 4160500100017 detector. Filled by 95% Ar + 5% methane at 760 mm Hg 4160500100018 pressure. 4160500100019 Used in third series of measurements. 4160500100020 2 In series 1,2,4 of measurements - detector described 4160500100021 in REL-REF of G.Flerov+ was used. 4160500100022 REL-REF 2(I,,G.N.Flerov+,J,YF,20,472,1974) 4160500100023 (I,,G.N.Flerov+,J,SNP,20,254,1975) 4160500100024 MONITOR (94-PU-242(0,F),PR,NU) To define detection efficiency.4160500100025 Pu-242 was used as standard. Pu-242 sources of 0.1 to 4160500100026 0.5 fis/sec activity were used in calibration 4160500100027 measurements. 4160500100028 MONIT-REF (30367004,J.W.Boldeman,C,73KIEV,4,114,1973) 4160500100029 ANALYSIS Neutron registration efficiency was defined to be: 4160500100030 Series number 4160500100031 1 0.216 +- 0.006 4160500100032 2 0.264 +- 0.002 4160500100033 3 0.383 +- 0.002 4160500100034 4 0.264 +- 0.002 4160500100035 Series number Number of events with multiplicity n 4160500100036 n=0 n=1 n=2 n=3 n=4 n=5 4160500100037 1 3029 1400 294 27 0 0 4160500100038 2 5113 2907 702 75 3 0 4160500100039 3 18209 17522 5945 906 93 7 4160500100040 4 - - 20644 2391 163 16 4160500100041 4th series was carried out by uranium block, in a mine 4160500100042 at a depth of 1100mwe in the "internal start" mode. 4160500100043 ERR-ANALYS (DATA-ERR) Includes statistical accuracy, 4160500100044 the instability of the apparatus, 4160500100045 accuracy of the consents used. 4160500100046 HISTORY (20150220C) M.M. 4160500100047 ENDBIB 45 0 4160500100048 COMMON 2 3 4160500100049 MONIT MONIT-ERR 4160500100050 PRT/FIS PRT/FIS 4160500100051 2.109 0.007 4160500100052 ENDCOMMON 3 0 4160500100053 ENDSUBENT 52 0 4160500199999 SUBENT 41605002 20150220 41684160500200001 BIB 3 4 4160500200002 REACTION ((92-U-238(0,F),PR,NU)/(94-PU-242(0,F),,NU)) 4160500200003 Average prompt neutron multiplicities ratio . 4160500200004 ANALYSIS Ratio was defined by measure numbers of events. 4160500200005 STATUS (TABLE) Text, page 475 of J,YF,24,(3),473,1976. 4160500200006 ENDBIB 4 0 4160500200007 NOCOMMON 0 0 4160500200008 DATA 2 1 4160500200009 DATA DATA-ERR 4160500200010 NO-DIM NO-DIM 4160500200011 0.943 0.007 4160500200012 ENDDATA 3 0 4160500200013 ENDSUBENT 12 0 4160500299999 SUBENT 41605003 20150220 41684160500300001 BIB 3 4 4160500300002 REACTION (92-U-238(0,F),PR,NU) 4160500300003 Average prompt neutron multiplicity. 4160500300004 ANALYSIS Defined from measured ratio U238/Pu242 by NU of Pu-242.4160500300005 STATUS (TABLE) Text, page 475 of J,YF,24,(3),473,1976. 4160500300006 ENDBIB 4 0 4160500300007 NOCOMMON 0 0 4160500300008 DATA 2 1 4160500300009 DATA DATA-ERR 4160500300010 PRT/FIS PRT/FIS 4160500300011 1.99 0.03 4160500300012 ENDDATA 3 0 4160500300013 ENDSUBENT 12 0 4160500399999 SUBENT 41605004 20150220 41684160500400001 BIB 3 4 4160500400002 REACTION (92-U-238(0,F),PR/NUM,NU) 4160500400003 Probability of emission of various numbers of neutrons.4160500400004 ANALYSIS Method of least squares was used. 4160500400005 STATUS (TABLE) Text, page 476 of J,YF,24,(3),473,1976. 4160500400006 ENDBIB 4 0 4160500400007 NOCOMMON 0 0 4160500400008 DATA 3 6 4160500400009 PART-OUT DATA DATA-ERR 4160500400010 NO-DIM NO-DIM NO-DIM 4160500400011 0. 0.052 0.010 4160500400012 1. 0.277 0.030 4160500400013 2. 0.366 0.035 4160500400014 3. 0.247 0.030 4160500400015 4. 0.050 0.010 4160500400016 5. 0.008 0.003 4160500400017 ENDDATA 8 0 4160500400018 ENDSUBENT 17 0 4160500499999 ENDENTRY 4 0 4160599999999