ENTRY 40297 20201010 41934029700000001 SUBENT 40297001 20201010 41934029700100001 BIB 11 36 4029700100002 INSTITUTE (4RUSNIR) 4029700100003 REFERENCE (C,73KIEV,4,57,1973) 4029700100004 No INDC(CCP) rep. for this conf.proc. at NDS web-site.4029700100005 Data in Tables. 4029700100006 AUTHOR (K.D.Zhuravlev,Yu.S.Zamjatnin,N.I.Kroshkin) 4029700100007 TITLE Energy spectra and average prompt neutron number 4029700100008 for fission of curium isotopes 4029700100009 METHOD (TOF) Time-of-flight method.Flight base is equal 50 cm.4029700100010 DETECTOR (SCIN) Gas scintillation detector for registration 4029700100011 of fission fragments and plastic scintillation detector4029700100012 of 100 mm diameter, 30 mm length for prompt neutrons 4029700100013 registration 4029700100014 ANALYSIS Spectrum of fission neutrons was approximated 4029700100015 by expression N(E)=E**(1/2)*exp(-E/T). 4029700100016 here E - energy of fission neutrons, 4029700100017 N(E) - a number of fission neutrons with 4029700100018 given energy E, 4029700100019 T - average temperature of spectrum 4029700100020 of fission neutrons. 4029700100021 For U-235 value of T is equal 1.29 MeV. 4029700100022 For definition of average number of prompt fission 4029700100023 neutrons spectrum of fission neutrons was been 4029700100024 integrated and this result was regarded to number 4029700100025 of fissions registered at the time of measurements. 4029700100026 MONITOR (92-U-235(N,F),PR,NU) 4029700100027 PART-DET (PN) 4029700100028 (FF) 4029700100029 ERR-ANALYS (DATA-ERR) In this article there is no information 4029700100030 about the type of uncertainty. 4029700100031 HISTORY (19750514C) 4029700100032 (20201010A) M.M. Ref.C,70HELSINKI,2,183,1970 was added.4029700100033 Upper -> lower case correction. 4029700100034 Dates were corrected for 4-digits year. 4029700100035 BIB information was added - SAMPLE, STATUS. 4029700100036 Subent 002 was deleted - duplication of 40064.009. 4029700100037 Subent 005 was deleted - duplication of 40064.010. 4029700100038 ENDBIB 36 0 4029700100039 COMMON 1 3 4029700100040 MONIT 4029700100041 NO-DIM 4029700100042 2.407 4029700100043 ENDCOMMON 3 0 4029700100044 ENDSUBENT 43 0 4029700199999 NOSUBENT 40297002 20201010 41934029700200001 SUBENT 40297003 20201010 41934029700300001 BIB 8 12 4029700300002 REACTION (96-CM-243(N,F)0-NN-1,PR,KE) 4029700300003 FACILITY (REAC,4RUSNIR) 4029700300004 INC-SOURCE (REAC) Thermal reactor 4029700300005 INC-SPECT Spectrum of thermal neutrons from reactor SM-2 4029700300006 horizontal channel. Measurements with and without Cd 4029700300007 to obtain pure thermal neutrons. 4029700300008 SAMPLE Cm-242 - 0.48 %, Cm-243 - 54.0 %, Cm-244 - 45.52 %. 4029700300009 MISC-COL (MISC1) Average temperature of fission neutron spectrum4029700300010 STATUS (TABLE) Table 2 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029700300011 HISTORY (20201010A) Reaction was corrected: 4029700300012 ),PR,AKE,N) -> )0-NN-1,PR,KE) 4029700300013 MISC2 -> MISC1-ERR 4029700300014 ENDBIB 12 0 4029700300015 NOCOMMON 0 0 4029700300016 DATA 5 1 4029700300017 EN DATA DATA-ERR MISC1 MISC1-ERR 4029700300018 EV MEV MEV MEV MEV 4029700300019 2.5300E-02 2.15 0.06 1.43 0.04 4029700300020 ENDDATA 3 0 4029700300021 ENDSUBENT 20 0 4029700399999 SUBENT 40297004 20201010 41934029700400001 BIB 5 7 4029700400002 REACTION (96-CM-246(0,F)0-NN-1,PR,KE) 4029700400003 SAMPLE Cm-244 - 0.25 %, Cm-245 - 0.29 %, Cm-246 - 99.46 %. 4029700400004 MISC-COL (MISC1) Average temperature of fission neutron spectrum4029700400005 STATUS (TABLE) Table 2 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029700400006 HISTORY (20201010A) Reaction was corrected: 4029700400007 (N,F),PR,AKE,N) -> (0,F)0-NN-1,PR,KE) - spon.fission 4029700400008 MISC2 -> MISC1-ERR 4029700400009 ENDBIB 7 0 4029700400010 NOCOMMON 0 0 4029700400011 DATA 4 1 4029700400012 DATA DATA-ERR MISC1 MISC1-ERR 4029700400013 MEV MEV MEV MEV 4029700400014 2.09 0.06 1.39 0.04 4029700400015 ENDDATA 3 0 4029700400016 ENDSUBENT 15 0 4029700499999 NOSUBENT 40297005 20201010 41934029700500001 SUBENT 40297006 20201010 41934029700600001 BIB 5 7 4029700600002 REACTION (96-CM-248(0,F)0-NN-1,PR,KE) 4029700600003 SAMPLE Cm-244 - 5.57 %, Cm-246 - 1.85 %, Cm-248 - 92.58 %. 4029700600004 MISC-COL (MISC1) Average temperature of fission neutron spectrum4029700600005 STATUS (TABLE) Table 2 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029700600006 HISTORY (20201010A) Reaction was corrected: 4029700600007 (N,F),PR,AKE,N) -> (0,F)0-NN-1,PR,KE) - spon.fission 4029700600008 MISC2 -> MISC1-ERR 4029700600009 ENDBIB 7 0 4029700600010 NOCOMMON 0 0 4029700600011 DATA 4 1 4029700600012 DATA DATA-ERR MISC1 MISC1-ERR 4029700600013 MEV MEV MEV MEV 4029700600014 2.15 0.06 1.43 0.04 4029700600015 ENDDATA 3 0 4029700600016 ENDSUBENT 15 0 4029700699999 SUBENT 40297007 20201010 41934029700700001 BIB 8 12 4029700700002 REACTION (96-CM-247(N,F)0-NN-1,PR,KE) 4029700700003 FACILITY (REAC,4RUSNIR) 4029700700004 INC-SOURCE (REAC) Thermal reactor 4029700700005 INC-SPECT Spectrum of thermal neutrons from reactor SM-2 4029700700006 horizontal channel. Measurements with and without Cd 4029700700007 to obtain pure thermal neutrons. 4029700700008 SAMPLE Cm-244 - 5.04 %, Cm-246 - 18.32 %, Cm-247 - 76.64 %. 4029700700009 MISC-COL (MISC1) Average temperature of fission neutron spectrum4029700700010 STATUS (TABLE) Table 2 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029700700011 HISTORY (20201010A) Reaction was corrected: 4029700700012 ),PR,AKE,N) -> )0-NN-1,PR,KE) 4029700700013 MISC2 -> MISC1-ERR 4029700700014 ENDBIB 12 0 4029700700015 NOCOMMON 0 0 4029700700016 DATA 5 1 4029700700017 EN DATA DATA-ERR MISC1 MISC1-ERR 4029700700018 EV MEV MEV MEV MEV 4029700700019 2.5300E-02 2.20 0.06 1.47 0.04 4029700700020 ENDDATA 3 0 4029700700021 ENDSUBENT 20 0 4029700799999 SUBENT 40297008 20201010 41934029700800001 BIB 3 9 4029700800002 REACTION (96-CM-244(0,F),PR,NU) 4029700800003 STATUS (TABLE) Table 3 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029700800004 Subent 40297.008 superseds Subent 40064.003 - 4029700800005 Conf.Proc. 70HELSINKI,v.2,p.183,1970 Table 3 4029700800006 data value - 2.77+-0.08 prt/fis( normalized to 4029700800007 NU=2.426 prt/fis for U-235) 4029700800008 HISTORY (20201010A) Reaction was corrected: 4029700800009 (N,F) -> (0,F) - spon.fission. 4029700800010 NO-DIM -> PRT/FIS for DATA and DATA-ERR. 4029700800011 ENDBIB 9 0 4029700800012 NOCOMMON 0 0 4029700800013 DATA 2 1 4029700800014 DATA DATA-ERR 4029700800015 PRT/FIS PRT/FIS 4029700800016 2.75 0.08 4029700800017 ENDDATA 3 0 4029700800018 ENDSUBENT 17 0 4029700899999 SUBENT 40297009 20201010 41934029700900001 BIB 7 9 4029700900002 REACTION (96-CM-243(N,F),PR,NU) 4029700900003 FACILITY (REAC,4RUSNIR) 4029700900004 INC-SOURCE (REAC) Thermal reactor 4029700900005 INC-SPECT Spectrum of thermal neutrons from reactor SM-2 4029700900006 horizontal channel. Measurements with and without Cd 4029700900007 to obtain pure thermal neutrons. 4029700900008 SAMPLE Cm-242 - 0.48 %, Cm-243 - 54.0 %, Cm-244 - 45.52 %. 4029700900009 STATUS (TABLE) Table 3 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029700900010 HISTORY (20201010A) NO-DIM -> PRT/FIS for DATA and DATA-ERR. 4029700900011 ENDBIB 9 0 4029700900012 NOCOMMON 0 0 4029700900013 DATA 3 1 4029700900014 EN DATA DATA-ERR 4029700900015 EV PRT/FIS PRT/FIS 4029700900016 2.5300E-02 3.39 0.14 4029700900017 ENDDATA 3 0 4029700900018 ENDSUBENT 17 0 4029700999999 SUBENT 40297010 20201010 41934029701000001 BIB 4 6 4029701000002 REACTION (96-CM-246(0,F),PR,NU) 4029701000003 SAMPLE Cm-244 - 0.25 %, Cm-245 - 0.29 %, Cm-246 - 99.46 %. 4029701000004 STATUS (TABLE) Table 3 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029701000005 HISTORY (20201010A) Reaction was corrected: 4029701000006 (N,F) -> (0,F) - spon.fission. 4029701000007 NO-DIM -> PRT/FIS for DATA and DATA-ERR. 4029701000008 ENDBIB 6 0 4029701000009 NOCOMMON 0 0 4029701000010 DATA 2 1 4029701000011 DATA DATA-ERR 4029701000012 PRT/FIS PRT/FIS 4029701000013 2.98 0.12 4029701000014 ENDDATA 3 0 4029701000015 ENDSUBENT 14 0 4029701099999 SUBENT 40297011 20201010 41934029701100001 BIB 6 12 4029701100002 REACTION (96-CM-245(N,F),PR,NU) 4029701100003 FACILITY (REAC,4RUSNIR) 4029701100004 INC-SOURCE (REAC) Thermal reactor 4029701100005 INC-SPECT Spectrum of thermal neutrons from reactor SM-2 4029701100006 horizontal channel. Measurements with and without Cd 4029701100007 to obtain pure thermal neutrons. 4029701100008 STATUS (TABLE) Table 3 of Conf.Proc.,73KIEV,v.4,p.57,1973. 4029701100009 Subent 40297.011 superseds Subent 40064.004 - 4029701100010 Conf.Proc. 70HELSINKI,v.2,p.183,1970 Table 3 4029701100011 data value - 3.83+-0.16 prt/fis ( normalized to 4029701100012 NU=2.426 prt/fis for U-235) 4029701100013 HISTORY (20201010A) NO-DIM -> PRT/FIS for DATA and DATA-ERR. 4029701100014 ENDBIB 12 0 4029701100015 NOCOMMON 0 0 4029701100016 DATA 3 1 4029701100017 EN DATA DATA-ERR 4029701100018 EV PRT/FIS PRT/FIS 4029701100019 2.5300E-02 3.80 0.16 4029701100020 ENDDATA 3 0 4029701100021 ENDSUBENT 20 0 4029701199999 SUBENT 40297012 20201010 41934029701200001 BIB 4 6 4029701200002 REACTION (96-CM-248(0,F),PR,NU) 4029701200003 SAMPLE Cm-244 - 5.57 %, Cm-246 - 1.85 %, Cm-248 - 92.58 %. 4029701200004 STATUS (TABLE) Table 3 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029701200005 HISTORY (20201010A) Reaction was corrected: 4029701200006 (N,F) -> (0,F) - spon.fission. 4029701200007 NO-DIM -> PRT/FIS for DATA and DATA-ERR. 4029701200008 ENDBIB 6 0 4029701200009 NOCOMMON 0 0 4029701200010 DATA 2 1 4029701200011 DATA DATA-ERR 4029701200012 PRT/FIS PRT/FIS 4029701200013 3.14 0.12 4029701200014 ENDDATA 3 0 4029701200015 ENDSUBENT 14 0 4029701299999 SUBENT 40297013 20201010 41934029701300001 BIB 7 9 4029701300002 REACTION (96-CM-247(N,F),PR,NU) 4029701300003 FACILITY (REAC,4RUSNIR) 4029701300004 INC-SOURCE (REAC) Thermal reactor 4029701300005 INC-SPECT Spectrum of thermal neutrons from reactor SM-2 4029701300006 horizontal channel. Measurements with and without Cd 4029701300007 to obtain pure thermal neutrons. 4029701300008 SAMPLE Cm-244 - 5.04 %, Cm-246 - 18.32 %, Cm-247 - 76.64 %. 4029701300009 STATUS (TABLE) Table 3 of Conf.Proc.,73KIEV,v.4,p.57,1973 4029701300010 HISTORY (20201010A) NO-DIM -> PRT/FIS for DATA and DATA-ERR. 4029701300011 ENDBIB 9 0 4029701300012 NOCOMMON 0 0 4029701300013 DATA 3 1 4029701300014 EN DATA DATA-ERR 4029701300015 EV PRT/FIS PRT/FIS 4029701300016 2.5300E-02 3.79 0.15 4029701300017 ENDDATA 3 0 4029701300018 ENDSUBENT 17 0 4029701399999 ENDENTRY 13 0 4029799999999