ENTRY 40356 20170116 41754035600000001 SUBENT 40356001 20170116 41754035600100001 BIB 12 35 4035600100002 INSTITUTE (4RUSKUR) 4035600100003 REFERENCE (J,SJA,2,17,1957) Eng.transl.of AE,2,18,1957 4035600100004 (J,AE,2,(1),18,195701) 4035600100005 AUTHOR (V.I.Kalashnikova,V.I.Lebedev,P.E.Spivak) 4035600100006 TITLE Relative measurements of the mean number of neutrons 4035600100007 emitted in fission of U-233, U-235 and Pu-239 by 4035600100008 thermal neutrons and by neutrons characteristic of a 4035600100009 fission spectra 4035600100010 FACILITY (REAC,4RUSKUR) RFT reactor 4035600100011 SAMPLE The material being studied was used in quantities 4035600100012 varying from 10-30 mg and was deposited on a fine 4035600100013 aluminum foil in a layer 0.3-0.5 mg/cm2 thick 4035600100014 INC-SOURCE (REAC) Thermal neutrons (with a flux of 4035600100015 ~ (2-3) x 10**3 neut./cm2/sec) and fast neutrons 4035600100016 (with flux ~ 5 x 10**4 neut/cm2/sec) were used. 4035600100017 Fast neutrons were obtained via 14 g U-235 converter, 4035600100018 boron-carbide 3.76 g/cm2 filter, graphite rod of 6cm 4035600100019 diameter, 42 cm long. 4035600100020 METHOD (COINC) Fission neutrons and fragments. 4035600100021 DETECTOR (BF3) 24 counters B-F3 in the paraffin block. 4035600100022 Neutron detection efficiency ~ 5% for fast neutrons. 4035600100023 STATUS (TABLE) Tbl.2 from AE,2,(1),18,1957 4035600100024 ERR-ANALYS (DATA-ERR) Type is not explained in the article. 4035600100025 (ERR-S) Statistical uncertainty 4035600100026 (ERR-1,,1.) Systematic uncertainty due to detector 4035600100027 efficiency . 4035600100028 HISTORY (19820617C) 4035600100029 (20150210A) SD: Updated to new date formats,lower case.4035600100030 Ref. on Engl.transl. of AE added. STATUS from 4035600100031 Subents 2-4 moved to Subent 1. BIB updated. 4035600100032 (20170116A) M.M. EN=1. MeV -> EN-MEAN-NM=2.MEV (p.17 of4035600100033 SJA,2,17,1957) . 4035600100034 EN-DUM-DN, ERR-S, ERR-1 were added. 4035600100035 Corrections were done in METHOD,DETECTOR,ERR-ANALYS, 4035600100036 INC-SOURCE . 4035600100037 ENDBIB 35 0 4035600100038 COMMON 2 3 4035600100039 EN-DUM-DN ERR-S 4035600100040 EV PER-CENT 4035600100041 0.0253 1. 4035600100042 ENDCOMMON 3 0 4035600100043 ENDSUBENT 42 0 4035600199999 SUBENT 40356002 20170116 41754035600200001 BIB 3 8 4035600200002 REACTION ((92-U-233(N,F),,NU,,FIS)//(92-U-233(N,F),,NU,,MXW)) 4035600200003 METHOD Two measurements: 4035600200004 Neutrons Number of fragments Number of coincidences4035600200005 1 fast 213888 28688 4035600200006 thermal 938240 117664 4035600200007 2 fast 215472 29236 4035600200008 thermal 760640 95568 4035600200009 HISTORY (20170116A) M.M. U-235 -> U-233 in denominator. 4035600200010 ENDBIB 8 0 4035600200011 NOCOMMON 0 0 4035600200012 DATA 3 1 4035600200013 EN-MEAN-NM DATA DATA-ERR 4035600200014 MEV NO-DIM NO-DIM 4035600200015 2. 1.075 0.01 4035600200016 ENDDATA 3 0 4035600200017 ENDSUBENT 16 0 4035600299999 SUBENT 40356003 20170116 41754035600300001 BIB 2 7 4035600300002 REACTION ((92-U-235(N,F),,NU,,FIS)//(92-U-235(N,F),,NU,,MXW)) 4035600300003 METHOD Two measurements: 4035600300004 Neutrons Number of fragments Number of coincidences4035600300005 1 fast 329892 44544 4035600300006 thermal 1762880 216320 4035600300007 2 fast 21200 28352 4035600300008 thermal 1323720 15944 4035600300009 ENDBIB 7 0 4035600300010 NOCOMMON 0 0 4035600300011 DATA 3 1 4035600300012 EN-MEAN-NM DATA DATA-ERR 4035600300013 MEV NO-DIM NO-DIM 4035600300014 2. 1.10 0.01 4035600300015 ENDDATA 3 0 4035600300016 ENDSUBENT 15 0 4035600399999 SUBENT 40356004 20170116 41754035600400001 BIB 3 11 4035600400002 REACTION ((94-PU-239(N,F),,NU,,FIS)//(94-PU-239(N,F),,NU,,MXW)) 4035600400003 METHOD Two measurements: 4035600400004 Neutrons Number of fragments Number of coincidences4035600400005 1 fast 160940 25336 4035600400006 thermal 942720 134428 4035600400007 2 fast 148876 23368 4035600400008 thermal 678208 95544 4035600400009 CORRECTION Background due to spontaneous fission of Pu-240 4035600400010 contamination ~ 2.5% of number of Pu-239 fissions by 4035600400011 fast neutrons, correction for this background in NU 4035600400012 quantity ~ 1% . 4035600400013 ENDBIB 11 0 4035600400014 NOCOMMON 0 0 4035600400015 DATA 3 1 4035600400016 EN-MEAN-NM DATA DATA-ERR 4035600400017 MEV NO-DIM NO-DIM 4035600400018 2. 1.11 0.01 4035600400019 ENDDATA 3 0 4035600400020 ENDSUBENT 19 0 4035600499999 ENDENTRY 4 0 4035699999999