ENTRY 13700 20220210 14981370000000001 SUBENT 13700001 20220210 14981370000100001 BIB 10 20 1370000100002 TITLE Delayed neutrons from fissionable isotopes of uranium, 1370000100003 plutonium, and thorium 1370000100004 AUTHOR (G.R.Keepin,T.F.Wimett,R.K.Zeigler) 1370000100005 REFERENCE (J,PR,107,1044,1957) 1370000100006 #doi:10.1103/physrev.107.1044 1370000100007 (J,JNE,6,1,1957) An extended version of the same data. 1370000100008 #doi:10.1016/0891-3919(57)90178-X 1370000100009 (R,LA-2118,1957) Preliminary version. 1370000100010 INSTITUTE (1USALAS) 1370000100011 FACILITY (REAC,1USALAS) 235U bare-metal assembly Godiva. 1370000100012 DETECTOR (BF3) 10BF3 proportional counter. 1370000100013 ANALYSIS Data obtained from least-squares fit to all data. 1370000100014 CORRECTION Corrected for background, detector dead-time, energy 1370000100015 variation of detector response, and isotopic 1370000100016 impurities. 1370000100017 ERR-ANALYS (DATA-ERR) Calculated probable errors. 1370000100018 HISTORY (19980814C) 1370000100019 (20170620A) BP: updated the entry using the latest 1370000100020 rules, added the second reference. 1370000100021 (20220210A) BP: Added LA report. 1370000100022 ENDBIB 20 0 1370000100023 NOCOMMON 0 0 1370000100024 ENDSUBENT 23 0 1370000199999 SUBENT 13700002 20170620 14291370000200001 BIB 8 12 1370000200002 REACTION ((90-TH-232(N,F),DL/GRP,NU,,FIS)/ 1370000200003 (90-TH-232(N,F),DL,NU,,FIS)) 1370000200004 RESULT (DFRCT) 1370000200005 INC-SOURCE (REAC) 1370000200006 INC-SPECT Slightly degraded fission neutron spectrum. 1370000200007 SAMPLE 232Th sample. 1370000200008 METHOD Determination of 4 long-period groups from 40 long 1370000200009 irradiations and determination of 4 shorter-period 1370000200010 groups from 40 burst irradiations. The 2 sets of 1370000200011 yield are normalized at an appropriate point. 1370000200012 ANALYSIS Least squares fit to all data. 1370000200013 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000200014 ENDBIB 12 0 1370000200015 COMMON 1 3 1370000200016 EN-DUMMY 1370000200017 MEV 1370000200018 1.0 1370000200019 ENDCOMMON 3 0 1370000200020 DATA 4 6 1370000200021 HL HL-ERR DATA DATA-ERR 1370000200022 SEC SEC NO-DIM NO-DIM 1370000200023 56.03 0.95 0.034 0.002 1370000200024 20.75 0.66 0.150 0.005 1370000200025 5.74 0.24 0.155 0.021 1370000200026 2.16 0.08 0.446 0.015 1370000200027 0.571 0.042 0.172 0.013 1370000200028 0.211 0.019 0.043 0.006 1370000200029 ENDDATA 8 0 1370000200030 ENDSUBENT 29 0 1370000299999 SUBENT 13700003 20170620 14291370000300001 BIB 7 10 1370000300002 REACTION (90-TH-232(N,F),DL/GRP,NU,,FIS) 1370000300003 INC-SOURCE (REAC) 1370000300004 INC-SPECT Slightly degraded fission neutron spectrum. 1370000300005 SAMPLE 232Th sample. 1370000300006 METHOD Determination of 4 long-period groups from 40 long 1370000300007 irradiations and determination of 4 shorter-period 1370000300008 groups from 40 burst irradiations. The 2 sets of 1370000300009 yield are normalized at an appropriate point. 1370000300010 ANALYSIS Least squares fit to all data. 1370000300011 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000300012 ENDBIB 10 0 1370000300013 COMMON 1 3 1370000300014 EN-DUMMY 1370000300015 MEV 1370000300016 1.0 1370000300017 ENDCOMMON 3 0 1370000300018 DATA 4 6 1370000300019 HL HL-ERR DATA DATA-ERR 1370000300020 SEC SEC PRT/FIS PRT/FIS 1370000300021 56.03 0.95 0.169E-02 0.012E-02 1370000300022 20.75 0.66 0.744E-02 0.037E-02 1370000300023 5.74 0.24 0.769E-02 0.108E-02 1370000300024 2.16 0.08 2.212E-02 0.110E-02 1370000300025 0.571 0.042 0.853E-02 0.073E-02 1370000300026 0.211 0.019 0.213E-02 0.031E-02 1370000300027 ENDDATA 8 0 1370000300028 ENDSUBENT 27 0 1370000399999 SUBENT 13700004 20170620 14291370000400001 BIB 8 12 1370000400002 REACTION ((92-U-233(N,F),DL/GRP,NU,,FIS)/ 1370000400003 (92-U-233(N,F),DL,NU,,FIS)) 1370000400004 RESULT (DFRCT) 1370000400005 INC-SOURCE (REAC) 1370000400006 INC-SPECT Slightly degraded fission neutron spectrum. 1370000400007 SAMPLE (92-U-233,ENR=1.0) Sample 100% 233U. 1370000400008 METHOD Determination of 4 long-period groups from 40 long 1370000400009 irradiations and determination of 4 shorter-period 1370000400010 groups from 40 burst irradiations. The 2 sets of 1370000400011 yield are normalized at an appropriate point. 1370000400012 ANALYSIS Least squares fit to all data. 1370000400013 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000400014 ENDBIB 12 0 1370000400015 COMMON 1 3 1370000400016 EN-DUMMY 1370000400017 MEV 1370000400018 1.0 1370000400019 ENDCOMMON 3 0 1370000400020 DATA 4 6 1370000400021 HL HL-ERR DATA DATA-ERR 1370000400022 SEC SEC NO-DIM NO-DIM 1370000400023 55.11 1.86 0.086 0.003 1370000400024 20.74 0.86 0.274 0.005 1370000400025 5.30 0.19 0.227 0.035 1370000400026 2.29 0.01 0.317 0.011 1370000400027 0.546 0.108 0.073 0.014 1370000400028 0.221 0.042 0.023 0.007 1370000400029 ENDDATA 8 0 1370000400030 ENDSUBENT 29 0 1370000499999 SUBENT 13700005 20170620 14291370000500001 BIB 7 10 1370000500002 REACTION (92-U-233(N,F),DL/GRP,NU,,FIS) 1370000500003 INC-SOURCE (REAC) 1370000500004 INC-SPECT Slightly degraded fission neutron spectrum. 1370000500005 SAMPLE (92-U-233,ENR=1.0) Sample 100% 233U. 1370000500006 METHOD Determination of 4 long-period groups from 40 long 1370000500007 irradiations and determination of 4 shorter-period 1370000500008 groups from 40 burst irradiations. The 2 sets of 1370000500009 yield are normalized at an appropriate point. 1370000500010 ANALYSIS Least squares fit to all data. 1370000500011 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000500012 ENDBIB 10 0 1370000500013 COMMON 1 3 1370000500014 EN-DUMMY 1370000500015 MEV 1370000500016 1.0 1370000500017 ENDCOMMON 3 0 1370000500018 DATA 4 6 1370000500019 HL HL-ERR DATA DATA-ERR 1370000500020 SEC SEC PRT/FIS PRT/FIS 1370000500021 55.11 1.86 0.060E-02 0.003E-02 1370000500022 20.74 0.86 0.192E-02 0.009E-02 1370000500023 5.30 0.19 0.159E-02 0.025E-02 1370000500024 2.29 0.01 0.222E-02 0.012E-02 1370000500025 0.546 0.108 0.051E-02 0.010E-02 1370000500026 0.221 0.042 0.016E-02 0.005E-02 1370000500027 ENDDATA 8 0 1370000500028 ENDSUBENT 27 0 1370000599999 SUBENT 13700006 20170620 14291370000600001 BIB 8 12 1370000600002 REACTION ((92-U-235(N,F),DL/GRP,NU,,FIS)/ 1370000600003 (92-U-235(N,F),DL,NU,,FIS)) 1370000600004 RESULT (DFRCT) 1370000600005 INC-SOURCE (REAC) 1370000600006 INC-SPECT Slightly degraded fission neutron spectrum. 1370000600007 SAMPLE (92-U-235,ENR=0.999) Sample 99.9% 235U. 1370000600008 METHOD Determination of 4 long-period groups from 40 long 1370000600009 irradiations and determination of 4 shorter-period 1370000600010 groups from 40 burst irradiations. The 2 sets of 1370000600011 yield are normalized at an appropriate point. 1370000600012 ANALYSIS Least squares fit to all data. 1370000600013 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000600014 ENDBIB 12 0 1370000600015 COMMON 1 3 1370000600016 EN-DUMMY 1370000600017 MEV 1370000600018 1.0 1370000600019 ENDCOMMON 3 0 1370000600020 DATA 4 6 1370000600021 HL HL-ERR DATA DATA-ERR 1370000600022 SEC SEC NO-DIM NO-DIM 1370000600023 54.51 0.94 0.038 0.003 1370000600024 21.84 0.54 0.213 0.005 1370000600025 6.0 0.17 0.188 0.016 1370000600026 2.23 0.06 0.407 0.007 1370000600027 0.496 0.029 0.128 0.008 1370000600028 0.179 0.017 0.026 0.003 1370000600029 ENDDATA 8 0 1370000600030 ENDSUBENT 29 0 1370000699999 SUBENT 13700007 20170620 14291370000700001 BIB 7 10 1370000700002 REACTION (92-U-235(N,F),DL/GRP,NU,,FIS) 1370000700003 INC-SOURCE (REAC) 1370000700004 INC-SPECT Slightly degraded fission neutron spectrum. 1370000700005 SAMPLE (92-U-235,ENR=0.999) Sample 99.9% 235U. 1370000700006 METHOD Determination of 4 long-period groups from 40 long 1370000700007 irradiations and determination of 4 shorter-period 1370000700008 groups from 40 burst irradiations. The 2 sets of 1370000700009 yield are normalized at an appropriate point. 1370000700010 ANALYSIS Least squares fit to all data. 1370000700011 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000700012 ENDBIB 10 0 1370000700013 COMMON 1 3 1370000700014 EN-DUMMY 1370000700015 MEV 1370000700016 1.0 1370000700017 ENDCOMMON 3 0 1370000700018 DATA 4 6 1370000700019 HL HL-ERR DATA DATA-ERR 1370000700020 SEC SEC PRT/FIS PRT/FIS 1370000700021 54.51 0.94 0.063E-02 0.005E-02 1370000700022 21.84 0.54 0.351E-02 0.011E-02 1370000700023 6.0 0.17 0.310E-02 0.028E-02 1370000700024 2.23 0.06 0.672E-02 0.023E-02 1370000700025 0.496 0.029 0.211E-02 0.015E-02 1370000700026 0.179 0.017 0.043E-02 0.005E-02 1370000700027 ENDDATA 8 0 1370000700028 ENDSUBENT 27 0 1370000799999 SUBENT 13700008 20170620 14291370000800001 BIB 8 12 1370000800002 REACTION ((92-U-238(N,F),DL/GRP,NU,,FIS)/ 1370000800003 (92-U-238(N,F),DL,NU,,FIS)) 1370000800004 RESULT (DFRCT) 1370000800005 INC-SOURCE (REAC) 1370000800006 INC-SPECT Slightly degraded fission neutron spectrum. 1370000800007 SAMPLE (92-U-238,ENR=0.9998) Sample 99.98% 238U. 1370000800008 METHOD Determination of 4 long-period groups from 40 long 1370000800009 irradiations and determination of 4 shorter-period 1370000800010 groups from 40 burst irradiations. The 2 sets of 1370000800011 yield are normalized at an appropriate point. 1370000800012 ANALYSIS Least squares fit to all data. 1370000800013 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000800014 ENDBIB 12 0 1370000800015 COMMON 1 3 1370000800016 EN-DUMMY 1370000800017 MEV 1370000800018 1.0 1370000800019 ENDCOMMON 3 0 1370000800020 DATA 4 6 1370000800021 HL HL-ERR DATA DATA-ERR 1370000800022 SEC SEC NO-DIM NO-DIM 1370000800023 52.38 1.29 0.013 0.001 1370000800024 21.58 0.39 0.137 0.002 1370000800025 5.00 0.19 0.162 0.020 1370000800026 1.93 0.07 0.388 0.012 1370000800027 0.490 0.023 0.225 0.013 1370000800028 0.172 0.009 0.075 0.005 1370000800029 ENDDATA 8 0 1370000800030 ENDSUBENT 29 0 1370000899999 SUBENT 13700009 20170620 14291370000900001 BIB 7 10 1370000900002 REACTION (92-U-238(N,F),DL/GRP,NU,,FIS) 1370000900003 INC-SOURCE (REAC) 1370000900004 INC-SPECT Slightly degraded fission neutron spectrum. 1370000900005 SAMPLE (92-U-238,ENR=0.9998) Sample 99.98% 238U. 1370000900006 METHOD Determination of 4 long-period groups from 40 long 1370000900007 irradiations and determination of 4 shorter-period 1370000900008 groups from 40 burst irradiations. The 2 sets of 1370000900009 yield are normalized at an appropriate point. 1370000900010 ANALYSIS Least squares fit to all data. 1370000900011 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370000900012 ENDBIB 10 0 1370000900013 COMMON 1 3 1370000900014 EN-DUMMY 1370000900015 MEV 1370000900016 1.0 1370000900017 ENDCOMMON 3 0 1370000900018 DATA 4 6 1370000900019 HL HL-ERR DATA DATA-ERR 1370000900020 SEC SEC PRT/FIS PRT/FIS 1370000900021 52.38 1.29 0.054E-02 0.005E-02 1370000900022 21.58 0.39 0.564E-02 0.025E-02 1370000900023 5.00 0.19 0.667E-02 0.087E-02 1370000900024 1.93 0.07 1.599E-02 0.081E-02 1370000900025 0.490 0.023 0.927E-02 0.060E-02 1370000900026 0.172 0.009 0.309E-02 0.024E-02 1370000900027 ENDDATA 8 0 1370000900028 ENDSUBENT 27 0 1370000999999 SUBENT 13700010 20170620 14291370001000001 BIB 8 12 1370001000002 REACTION ((94-PU-239(N,F),DL/GRP,NU,,FIS)/ 1370001000003 (94-PU-239(N,F),DL,NU,,FIS)) 1370001000004 RESULT (DFRCT) 1370001000005 INC-SOURCE (REAC) 1370001000006 INC-SPECT Slightly degraded fission neutron spectrum. 1370001000007 SAMPLE (94-PU-239,ENR=0.998) Sample 99.8% 239Pu. 1370001000008 METHOD Determination of 4 long-period groups from 40 long 1370001000009 irradiations and determination of 4 shorter-period 1370001000010 groups from 40 burst irradiations. The 2 sets of 1370001000011 yield are normalized at an appropriate point. 1370001000012 ANALYSIS Least squares fit to all data. 1370001000013 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370001000014 ENDBIB 12 0 1370001000015 COMMON 1 3 1370001000016 EN-DUMMY 1370001000017 MEV 1370001000018 1.0 1370001000019 ENDCOMMON 3 0 1370001000020 DATA 4 6 1370001000021 HL HL-ERR DATA DATA-ERR 1370001000022 SEC SEC NO-DIM NO-DIM 1370001000023 53.75 0.95 0.038 0.003 1370001000024 22.29 0.36 0.280 0.004 1370001000025 5.19 0.12 0.216 0.018 1370001000026 2.09 0.08 0.328 0.010 1370001000027 0.549 0.049 0.103 0.009 1370001000028 0.216 0.017 0.375 0.005 1370001000029 ENDDATA 8 0 1370001000030 ENDSUBENT 29 0 1370001099999 SUBENT 13700011 20170620 14291370001100001 BIB 7 10 1370001100002 REACTION (94-PU-239(N,F),DL/GRP,NU,,FIS) 1370001100003 INC-SOURCE (REAC) 1370001100004 INC-SPECT Slightly degraded fission neutron spectrum. 1370001100005 SAMPLE (94-PU-239,ENR=0.998) Sample 99.8% 239Pu. 1370001100006 METHOD Determination of 4 long-period groups from 40 long 1370001100007 irradiations and determination of 4 shorter-period 1370001100008 groups from 40 burst irradiations. The 2 sets of 1370001100009 yield are normalized at an appropriate point. 1370001100010 ANALYSIS Least squares fit to all data. 1370001100011 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370001100012 ENDBIB 10 0 1370001100013 COMMON 1 3 1370001100014 EN-DUMMY 1370001100015 MEV 1370001100016 1.0 1370001100017 ENDCOMMON 3 0 1370001100018 DATA 4 6 1370001100019 HL HL-ERR DATA DATA-ERR 1370001100020 SEC SEC PRT/FIS PRT/FIS 1370001100021 53.75 0.95 0.024E-02 0.002E-02 1370001100022 22.29 0.36 0.176E-02 0.009E-02 1370001100023 5.19 0.12 0.136E-02 0.013E-02 1370001100024 2.09 0.08 0.207E-02 0.012E-02 1370001100025 0.549 0.049 0.065E-02 0.007E-02 1370001100026 0.216 0.017 0.022E-02 0.003E-02 1370001100027 ENDDATA 8 0 1370001100028 ENDSUBENT 27 0 1370001199999 SUBENT 13700012 20170620 14291370001200001 BIB 8 12 1370001200002 REACTION ((94-PU-240(N,F),DL/GRP,NU,,FIS)/ 1370001200003 (94-PU-240(N,F),DL,NU,,FIS)) 1370001200004 RESULT (DFRCT) 1370001200005 INC-SOURCE (REAC) 1370001200006 INC-SPECT Slightly degraded fission neutron spectrum. 1370001200007 SAMPLE (94-PU-240,ENR=0.815) Sample 81.5% 240Pu. 1370001200008 METHOD Determination of 4 long-period groups from 40 long 1370001200009 irradiations and determination of 4 shorter-period 1370001200010 groups from 40 burst irradiations. The 2 sets of 1370001200011 yield are normalized at an appropriate point. 1370001200012 ANALYSIS Least squares fit to all data. 1370001200013 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370001200014 ENDBIB 12 0 1370001200015 COMMON 1 3 1370001200016 EN-DUMMY 1370001200017 MEV 1370001200018 1.0 1370001200019 ENDCOMMON 3 0 1370001200020 DATA 4 6 1370001200021 HL HL-ERR DATA DATA-ERR 1370001200022 SEC SEC NO-DIM NO-DIM 1370001200023 53.56 1.21 0.028 0.003 1370001200024 22.14 0.38 0.273 0.004 1370001200025 5.14 0.42 0.192 0.053 1370001200026 2.08 0.19 0.350 0.020 1370001200027 0.511 0.077 0.128 0.018 1370001200028 0.172 0.033 0.029 0.006 1370001200029 ENDDATA 8 0 1370001200030 ENDSUBENT 29 0 1370001299999 SUBENT 13700013 20170620 14291370001300001 BIB 7 10 1370001300002 REACTION (94-PU-240(N,F),DL/GRP,NU,,FIS) 1370001300003 INC-SOURCE (REAC) 1370001300004 INC-SPECT Slightly degraded fission neutron spectrum. 1370001300005 SAMPLE (94-PU-240,ENR=0.815) Sample 81.5% 240Pu. 1370001300006 METHOD Determination of 4 long-period groups from 40 long 1370001300007 irradiations and determination of 4 shorter-period 1370001300008 groups from 40 burst irradiations. The 2 sets of 1370001300009 yield are normalized at an appropriate point. 1370001300010 ANALYSIS Least squares fit to all data. 1370001300011 STATUS (TABLE) Table I page 1046 of J,PR,107,1044,1957. 1370001300012 ENDBIB 10 0 1370001300013 COMMON 1 3 1370001300014 EN-DUMMY 1370001300015 MEV 1370001300016 1.0 1370001300017 ENDCOMMON 3 0 1370001300018 DATA 4 6 1370001300019 HL HL-ERR DATA DATA-ERR 1370001300020 SEC SEC PRT/FIS PRT/FIS 1370001300021 53.56 1.21 0.022E-02 0.003E-02 1370001300022 22.14 0.38 0.238E-02 0.016E-02 1370001300023 5.14 0.42 0.162E-02 0.044E-02 1370001300024 2.08 0.19 0.315E-02 0.027E-02 1370001300025 0.511 0.077 0.119E-02 0.018E-02 1370001300026 0.172 0.033 0.024E-02 0.005E-02 1370001300027 ENDDATA 8 0 1370001300028 ENDSUBENT 27 0 1370001399999 SUBENT 13700014 20170620 14291370001400001 BIB 8 13 1370001400002 REACTION ((92-U-233(N,F),DL/GRP,NU,,MXW)/ 1370001400003 (92-U-233(N,F),DL,NU,,MXW)) 1370001400004 RESULT (DFRCT) 1370001400005 INC-SOURCE (REAC) 1370001400006 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370001400007 shields mounted near reactor. 1370001400008 SAMPLE (92-U-233,ENR=1.0) Sample 100% 233U. 1370001400009 METHOD Determination of 4 long-period groups from 40 long 1370001400010 irradiations and determination of 4 shorter-period 1370001400011 groups from 40 burst irradiations. The 2 sets of 1370001400012 yield are normalized at an appropriate point. 1370001400013 ANALYSIS Least squares fit to all data. 1370001400014 STATUS (TABLE) Table II page 1047 of J,PR,107,1044,1957. 1370001400015 ENDBIB 13 0 1370001400016 COMMON 1 3 1370001400017 EN-DUMMY 1370001400018 EV 1370001400019 0.0253 1370001400020 ENDCOMMON 3 0 1370001400021 DATA 4 6 1370001400022 HL HL-ERR DATA DATA-ERR 1370001400023 SEC SEC NO-DIM NO-DIM 1370001400024 55.00 0.54 0.086 0.003 1370001400025 20.57 0.38 0.299 0.004 1370001400026 5.00 0.21 0.252 0.040 1370001400027 2.13 0.20 0.278 0.020 1370001400028 0.615 0.242 0.051 0.024 1370001400029 0.277 0.047 0.034 0.014 1370001400030 ENDDATA 8 0 1370001400031 ENDSUBENT 30 0 1370001499999 SUBENT 13700015 20170620 14291370001500001 BIB 7 11 1370001500002 REACTION (92-U-233(N,F),DL/GRP,NU,,MXW) 1370001500003 INC-SOURCE (REAC) 1370001500004 INC-SPECT Thermalized spectrum, using polyethylene and 1370001500005 cadmium shields mounted near reactor. 1370001500006 SAMPLE (92-U-233,ENR=1.0) Sample 100% 233U. 1370001500007 METHOD Determination of 4 long-period groups from 40 long 1370001500008 irradiations and determination of 4 shorter-period 1370001500009 groups from 40 burst irradiations. The 2 sets of 1370001500010 yield are normalized at an appropriate point. 1370001500011 ANALYSIS Least squares fit to all data. 1370001500012 STATUS (TABLE) Table II page 1047 of J,PR,107,1044,1957. 1370001500013 ENDBIB 11 0 1370001500014 COMMON 1 3 1370001500015 EN-DUMMY 1370001500016 EV 1370001500017 0.0253 1370001500018 ENDCOMMON 3 0 1370001500019 DATA 4 6 1370001500020 HL HL-ERR DATA DATA-ERR 1370001500021 SEC SEC PRT/FIS PRT/FIS 1370001500022 55.00 0.54 0.057E-02 0.003E-02 1370001500023 20.57 0.38 0.197E-02 0.009E-02 1370001500024 5.00 0.21 0.166E-02 0.027E-02 1370001500025 2.13 0.20 0.184E-02 0.016E-02 1370001500026 0.615 0.242 0.034E-02 0.016E-02 1370001500027 0.277 0.047 0.022E-02 0.009E-02 1370001500028 ENDDATA 8 0 1370001500029 ENDSUBENT 28 0 1370001599999 SUBENT 13700016 20170620 14291370001600001 BIB 8 13 1370001600002 REACTION ((92-U-235(N,F),DL/GRP,NU,,MXW)/ 1370001600003 (92-U-235(N,F),DL,NU,,MXW)) 1370001600004 RESULT (DFRCT) 1370001600005 INC-SOURCE (REAC) 1370001600006 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370001600007 shields mounted near reactor. 1370001600008 SAMPLE (92-U-235,ENR=0.999) Sample 99.9% 235U. 1370001600009 METHOD Determination of 4 long-period groups from 40 long 1370001600010 irradiations and determination of 4 shorter-period 1370001600011 groups from 40 burst irradiations. The 2 sets of 1370001600012 yield are normalized at an appropriate point. 1370001600013 ANALYSIS Least squares fit to all data. 1370001600014 STATUS (TABLE) Table II page 1047 of J,PR,107,1044,1957. 1370001600015 ENDBIB 13 0 1370001600016 COMMON 1 3 1370001600017 EN-DUMMY 1370001600018 EV 1370001600019 0.0253 1370001600020 ENDCOMMON 3 0 1370001600021 DATA 4 6 1370001600022 HL HL-ERR DATA DATA-ERR 1370001600023 SEC SEC NO-DIM NO-DIM 1370001600024 55.72 1.28 0.033 0.003 1370001600025 22.72 0.71 0.219 0.009 1370001600026 6.22 0.23 0.196 0.022 1370001600027 2.30 0.09 0.395 0.011 1370001600028 0.610 0.083 0.115 0.009 1370001600029 0.230 0.025 0.042 0.008 1370001600030 ENDDATA 8 0 1370001600031 ENDSUBENT 30 0 1370001699999 SUBENT 13700017 20170620 14291370001700001 BIB 7 11 1370001700002 REACTION (92-U-235(N,F),DL/GRP,NU,,MXW) 1370001700003 INC-SOURCE (REAC) 1370001700004 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370001700005 shields mounted near reactor. 1370001700006 SAMPLE (92-U-235,ENR=0.999) Sample 99.9% 235U. 1370001700007 METHOD Determination of 4 long-period groups from 40 long 1370001700008 irradiations and determination of 4 shorter-period 1370001700009 groups from 40 burst irradiations. The 2 sets of 1370001700010 yield are normalized at an appropriate point. 1370001700011 ANALYSIS Least squares fit to all data. 1370001700012 STATUS (TABLE) Table II page 1047 of J,PR,107,1044,1957. 1370001700013 ENDBIB 11 0 1370001700014 COMMON 1 3 1370001700015 EN-DUMMY 1370001700016 EV 1370001700017 0.0253 1370001700018 ENDCOMMON 3 0 1370001700019 DATA 4 6 1370001700020 HL HL-ERR DATA DATA-ERR 1370001700021 SEC SEC PRT/FIS PRT/FIS 1370001700022 55.72 1.28 0.052E-02 0.005E-02 1370001700023 22.72 0.71 0.346E-02 0.018E-02 1370001700024 6.22 0.23 0.310E-02 0.036E-02 1370001700025 2.30 0.09 0.624E-02 0.026E-02 1370001700026 0.610 0.083 0.182E-02 0.015E-02 1370001700027 0.230 0.025 0.066E-02 0.008E-02 1370001700028 ENDDATA 8 0 1370001700029 ENDSUBENT 28 0 1370001799999 SUBENT 13700018 20170620 14291370001800001 BIB 8 13 1370001800002 REACTION ((94-PU-239(N,F),DL/GRP,NU,,MXW)/ 1370001800003 (94-PU-239(N,F),DL,NU,,MXW)) 1370001800004 RESULT (DFRCT) 1370001800005 INC-SOURCE (REAC) 1370001800006 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370001800007 shields mounted near reactor. 1370001800008 SAMPLE (94-PU-239,ENR=0.998) Sample 99.8% 239Pu. 1370001800009 METHOD Determination of 4 long-period groups from 40 long 1370001800010 irradiations and determination of 4 shorter-period 1370001800011 groups from 40 burst irradiations. The 2 sets of 1370001800012 yield are normalized at an appropriate point. 1370001800013 ANALYSIS Least squares fit to all data. 1370001800014 STATUS (TABLE) Table II page 1047 of J,PR,107,1044,1957. 1370001800015 ENDBIB 13 0 1370001800016 COMMON 1 3 1370001800017 EN-DUMMY 1370001800018 EV 1370001800019 0.0253 1370001800020 ENDCOMMON 3 0 1370001800021 DATA 4 6 1370001800022 HL HL-ERR DATA DATA-ERR 1370001800023 SEC SEC NO-DIM NO-DIM 1370001800024 54.28 2.34 0.035 0.009 1370001800025 23.04 1.67 0.298 0.035 1370001800026 5.60 0.40 0.211 0.048 1370001800027 2.13 0.24 0.326 0.033 1370001800028 0.618 0.213 0.086 0.029 1370001800029 0.257 0.045 0.044 0.016 1370001800030 ENDDATA 8 0 1370001800031 ENDSUBENT 30 0 1370001899999 SUBENT 13700019 20170620 14291370001900001 BIB 7 11 1370001900002 REACTION (94-PU-239(N,F),DL/GRP,NU,,MXW) 1370001900003 INC-SOURCE (REAC) 1370001900004 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370001900005 shields mounted near reactor. 1370001900006 SAMPLE (94-PU-239,ENR=0.998) Sample 99.8% 239Pu. 1370001900007 METHOD Determination of 4 long-period groups from 40 long 1370001900008 irradiations and determination of 4 shorter-period 1370001900009 groups from 40 burst irradiations. The 2 sets of 1370001900010 yield are normalized at an appropriate point. 1370001900011 ANALYSIS Least squares fit to all data. 1370001900012 STATUS (TABLE) Table II page 1047 of J,PR,107,1044,1957. 1370001900013 ENDBIB 11 0 1370001900014 COMMON 1 3 1370001900015 EN-DUMMY 1370001900016 EV 1370001900017 0.0253 1370001900018 ENDCOMMON 3 0 1370001900019 DATA 4 6 1370001900020 HL HL-ERR DATA DATA-ERR 1370001900021 SEC SEC PRT/FIS PRT/FIS 1370001900022 54.28 2.34 0.021E-02 0.006E-02 1370001900023 23.04 1.67 0.182E-02 0.023E-02 1370001900024 5.60 0.40 0.129E-02 0.030E-02 1370001900025 2.13 0.24 0.199E-02 0.022E-02 1370001900026 0.618 0.213 0.052E-02 0.018E-02 1370001900027 0.257 0.045 0.027E-02 0.010E-02 1370001900028 ENDDATA 8 0 1370001900029 ENDSUBENT 28 0 1370001999999 SUBENT 13700020 20170620 14291370002000001 BIB 7 7 1370002000002 REACTION (90-TH-232(N,F),DL,NU,,FIS) 1370002000003 INC-SOURCE (REAC) 1370002000004 INC-SPECT Slightly degraded fission neutron spectrum. 1370002000005 SAMPLE 232Th sample. 1370002000006 METHOD 40 prompt-burst irradiations. 1370002000007 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002000008 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002000009 ENDBIB 7 0 1370002000010 NOCOMMON 0 0 1370002000011 DATA 3 1 1370002000012 EN-DUMMY DATA DATA-ERR 1370002000013 MEV PRT/FIS PRT/FIS 1370002000014 1.0 0.0496 0.0020 1370002000015 ENDDATA 3 0 1370002000016 ENDSUBENT 15 0 1370002099999 SUBENT 13700021 20170620 14291370002100001 BIB 7 7 1370002100002 REACTION (92-U-233(N,F),DL,NU,,FIS) 1370002100003 INC-SOURCE (REAC) 1370002100004 INC-SPECT Slightly degraded fission neutron spectrum. 1370002100005 SAMPLE (92-U-233,ENR=1.0) Sample 100% 233U. 1370002100006 METHOD 40 prompt-burst irradiations. 1370002100007 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002100008 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002100009 ENDBIB 7 0 1370002100010 NOCOMMON 0 0 1370002100011 DATA 3 1 1370002100012 EN-DUMMY DATA DATA-ERR 1370002100013 MEV PRT/FIS PRT/FIS 1370002100014 1.0 0.0070 0.0004 1370002100015 ENDDATA 3 0 1370002100016 ENDSUBENT 15 0 1370002199999 SUBENT 13700022 20170620 14291370002200001 BIB 7 7 1370002200002 REACTION (92-U-235(N,F),DL,NU,,FIS) 1370002200003 INC-SOURCE (REAC) 1370002200004 INC-SPECT Slightly degraded fission neutron spectrum. 1370002200005 SAMPLE (92-U-235,ENR=0.999) Sample 99.9% 235U. 1370002200006 METHOD 80 prompt-burst irradiations. 1370002200007 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002200008 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002200009 ENDBIB 7 0 1370002200010 NOCOMMON 0 0 1370002200011 DATA 3 1 1370002200012 EN-DUMMY DATA DATA-ERR 1370002200013 MEV PRT/FIS PRT/FIS 1370002200014 1.0 0.0165 0.0005 1370002200015 ENDDATA 3 0 1370002200016 ENDSUBENT 15 0 1370002299999 SUBENT 13700023 20170620 14291370002300001 BIB 7 7 1370002300002 REACTION (92-U-238(N,F),DL,NU,,FIS) 1370002300003 INC-SOURCE (REAC) 1370002300004 INC-SPECT Slightly degraded fission neutron spectrum. 1370002300005 SAMPLE (92-U-238,ENR=0.9998) Sample 99.98% 238U. 1370002300006 METHOD 40 prompt-burst irradiations. 1370002300007 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002300008 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002300009 ENDBIB 7 0 1370002300010 NOCOMMON 0 0 1370002300011 DATA 3 1 1370002300012 EN-DUMMY DATA DATA-ERR 1370002300013 MEV PRT/FIS PRT/FIS 1370002300014 1.0 0.0412 0.0017 1370002300015 ENDDATA 3 0 1370002300016 ENDSUBENT 15 0 1370002399999 SUBENT 13700024 20170620 14291370002400001 BIB 7 7 1370002400002 REACTION (94-PU-240(N,F),DL,NU,,FIS) 1370002400003 INC-SOURCE (REAC) 1370002400004 INC-SPECT Slightly degraded fission neutron spectrum. 1370002400005 SAMPLE (94-PU-240,ENR=0.815) Sample 81.5% 240Pu. 1370002400006 METHOD 40 prompt-burst irradiations. 1370002400007 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002400008 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002400009 ENDBIB 7 0 1370002400010 NOCOMMON 0 0 1370002400011 DATA 3 1 1370002400012 EN-DUMMY DATA DATA-ERR 1370002400013 MEV PRT/FIS PRT/FIS 1370002400014 1.0 0.0088 0.0006 1370002400015 ENDDATA 3 0 1370002400016 ENDSUBENT 15 0 1370002499999 SUBENT 13700025 20170620 14291370002500001 BIB 8 9 1370002500002 REACTION (92-U-233(N,F),DL,NU,,MXW) 1370002500003 INC-SOURCE (REAC) 1370002500004 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370002500005 shields mounted near reactor. 1370002500006 SAMPLE (92-U-233,ENR=1.0) Sample 100% 233U. 1370002500007 METHOD 40 prompt-burst irradiations. 1370002500008 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002500009 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002500010 HISTORY (19990810A) Energy units corrected. 1370002500011 ENDBIB 9 0 1370002500012 NOCOMMON 0 0 1370002500013 DATA 3 1 1370002500014 EN-DUMMY DATA DATA-ERR 1370002500015 EV PRT/FIS PRT/FIS 1370002500016 0.0253 0.0066 0.0003 1370002500017 ENDDATA 3 0 1370002500018 ENDSUBENT 17 0 1370002599999 SUBENT 13700026 20170620 14291370002600001 BIB 8 9 1370002600002 REACTION (92-U-235(N,F),DL,NU,,MXW) 1370002600003 INC-SOURCE (REAC) 1370002600004 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370002600005 shields mounted near reactor. 1370002600006 SAMPLE (92-U-235,ENR=0.999) Sample 99.9% 235U. 1370002600007 METHOD 80 prompt-burst irradiations. 1370002600008 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002600009 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002600010 HISTORY (19990810A) Energy units corrected. 1370002600011 ENDBIB 9 0 1370002600012 NOCOMMON 0 0 1370002600013 DATA 3 1 1370002600014 EN-DUMMY DATA DATA-ERR 1370002600015 EV PRT/FIS PRT/FIS 1370002600016 0.0253 0.0158 0.0005 1370002600017 ENDDATA 3 0 1370002600018 ENDSUBENT 17 0 1370002699999 SUBENT 13700027 20170620 14291370002700001 BIB 8 9 1370002700002 REACTION (94-PU-239(N,F),DL,NU,,MXW) 1370002700003 INC-SOURCE (REAC) 1370002700004 INC-SPECT Thermalized spectrum, using polyethylene and cadmium 1370002700005 shields mounted near reactor. 1370002700006 SAMPLE (94-PU-239,ENR=0.998) Sample 99.8% 239Pu. 1370002700007 METHOD 40 prompt-burst irradiations. 1370002700008 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002700009 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002700010 HISTORY (19990810A) Energy units corrected. 1370002700011 ENDBIB 9 0 1370002700012 NOCOMMON 0 0 1370002700013 DATA 3 1 1370002700014 EN-DUMMY DATA DATA-ERR 1370002700015 EV PRT/FIS PRT/FIS 1370002700016 0.0253 0.0061 0.0003 1370002700017 ENDDATA 3 0 1370002700018 ENDSUBENT 17 0 1370002799999 SUBENT 13700028 20170620 14291370002800001 BIB 8 8 1370002800002 REACTION (94-PU-239(N,F),DL,NU,,FIS) 1370002800003 INC-SOURCE (REAC) 1370002800004 INC-SPECT Slightly degraded fission neutron spectrum. 1370002800005 SAMPLE (94-PU-239,ENR=0.998) Sample 99.8% 239Pu. 1370002800006 METHOD 40 prompt-burst irradiations. 1370002800007 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1370002800008 STATUS (TABLE) Table III page 1047 of J,PR,107,1044,1957. 1370002800009 HISTORY (20170620A) BP: Corrected value from 0.0061 -> 0.0063. 1370002800010 ENDBIB 8 0 1370002800011 NOCOMMON 0 0 1370002800012 DATA 3 1 1370002800013 EN-DUMMY DATA DATA-ERR 1370002800014 MEV PRT/FIS PRT/FIS 1370002800015 1.0 0.0063 0.0003 1370002800016 ENDDATA 3 0 1370002800017 ENDSUBENT 16 0 1370002899999 ENDENTRY 28 0 1370099999999