ENTRY 21588 20170811 22632158800000001 SUBENT 21588001 20170811 22632158800100001 BIB 11 33 2158800100002 INSTITUTE (2JPNKYU) Department of Nuclear Engineering, 2158800100003 Kyushu University. 2158800100004 REFERENCE (J,NST,11,(12),523,1974) 2158800100005 AUTHOR (T.Akiyoshi,A.Katase,Y.Wakuta,M.Sonoda) 2158800100006 TITLE Inelastic scattering of 14 MeV neutrons by 2158800100007 heavy nuclei 2158800100008 FACILITY (CCW,2JPNKYU) Cockcroft-Walton accelerator. 2158800100009 INC-SOURCE (D-T) Deuteron-tritium reaction with 200 keV 2158800100010 deuterons. 2158800100011 (D-D) The D(d,n)3He reaction also was used as neutron 2158800100012 source to obtain the detector efficiency for low energy2158800100013 neutrons. 2158800100014 SAMPLE .Cylindrical, 2.54 cm diam, 2.54 cm long, at 7.3 cm 2158800100015 from the neutron source, natural elements, isotopic 2158800100016 compositions given in table 1 of NST,11,(12),523,1974 2158800100017 METHOD (TOF) Time-of-flight method to measure the 2158800100018 scattered neutron spectra. 80 cm flight path. 2158800100019 Overall time resolution about 2 ns. 2158800100020 (ASSOP) Associated particle method. 2158800100021 (PSD) Pulse shape discrimination to discriminate 2158800100022 against gammas. 2158800100023 DETECTOR (SCIN ) Liquid organic scintillator, NE-123, 5.08 cm 2158800100024 diam, 5.08 cm long, connected with two 56 AVP 2158800100025 photomultipliers. 2158800100026 CORRECTION .Background. 2158800100027 HISTORY (19800619C) G.C. 2158800100028 (19821124A) Reaction strings corrected. 2158800100029 (19840106U) A.P.T. Japan code changed to jpn 2158800100030 (20170811A) SD:Updated to new date formats,lower case. 2158800100031 REACTION code corrected in Subents 003,005,006. 2158800100032 Meaningless zeros were deleted from the data. 2158800100033 Subents 031-044 deleted (info moved to others). 2158800100034 Subent 013 deleted (REACTION code duplication). 2158800100035 ENDBIB 33 0 2158800100036 COMMON 1 3 2158800100037 EN 2158800100038 MEV 2158800100039 14.1 2158800100040 ENDCOMMON 3 0 2158800100041 ENDSUBENT 40 0 2158800199999 SUBENT 21588002 20170811 22632158800200001 BIB 6 12 2158800200002 REACTION (73-TA-181(N,INL)73-TA-181,,DA,,4PI) 2158800200003 ANALYSIS (INTAD) Integration of the angular distribution 2158800200004 assuming isotropy for it. The value at 100 degr is used2158800200005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800200006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800200007 * background subtraction, 2158800200008 * detector efficiency and 2158800200009 * calculation of total neutron yields. 2158800200010 Total errors are about 20% 2158800200011 of the obtained cross sections. 2158800200012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800200013 HISTORY (19821124A) Reaction string corrected. 2158800200014 ENDBIB 12 0 2158800200015 NOCOMMON 0 0 2158800200016 DATA 4 1 2158800200017 ANG MONIT DATA DATA-ERR 2158800200018 ADEG MB/SR B PER-CENT 2158800200019 100. 50. 1.80 20. 2158800200020 ENDDATA 3 0 2158800200021 ENDSUBENT 20 0 2158800299999 SUBENT 21588003 20170811 22632158800300001 BIB 6 13 2158800300002 REACTION (74-W-0(N,INL)74-W-0,,DA,,4PI) 2158800300003 ANALYSIS (INTAD) Integration of the angular distribution 2158800300004 assuming isotropy for it. The value at 100 degr is used2158800300005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800300006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800300007 * background subtraction, 2158800300008 * detector efficiency and 2158800300009 * calculation of total neutron yields. 2158800300010 Total errors are about 20% 2158800300011 of the obtained cross sections. 2158800300012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800300013 HISTORY (19821124A) Reaction string corrected. 2158800300014 (20170811A) SD: SF4=W-0 was added to REACTION code. 2158800300015 ENDBIB 13 0 2158800300016 NOCOMMON 0 0 2158800300017 DATA 4 1 2158800300018 ANG MONIT DATA DATA-ERR 2158800300019 ADEG MB/SR B PER-CENT 2158800300020 100. 50. 2.11 20. 2158800300021 ENDDATA 3 0 2158800300022 ENDSUBENT 21 0 2158800399999 SUBENT 21588004 20170811 22632158800400001 BIB 6 12 2158800400002 REACTION (79-AU-197(N,INL)79-AU-197,,DA,,4PI) 2158800400003 ANALYSIS (INTAD) Integration of the angular distribution 2158800400004 assuming isotropy for it. The value at 100 degr is used2158800400005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800400006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800400007 * background subtraction, 2158800400008 * detector efficiency and 2158800400009 * calculation of total neutron yields. 2158800400010 Total errors are about 20% 2158800400011 of the obtained cross sections. 2158800400012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800400013 HISTORY (19821124A) Reaction string corrected. 2158800400014 ENDBIB 12 0 2158800400015 NOCOMMON 0 0 2158800400016 DATA 4 1 2158800400017 ANG MONIT DATA DATA-ERR 2158800400018 ADEG MB/SR B PER-CENT 2158800400019 100. 50. 1.73 20. 2158800400020 ENDDATA 3 0 2158800400021 ENDSUBENT 20 0 2158800499999 SUBENT 21588005 20170811 22632158800500001 BIB 6 13 2158800500002 REACTION (80-HG-0(N,INL)80-HG-0,,DA,,4PI) 2158800500003 ANALYSIS (INTAD) Integration of the angular distribution 2158800500004 assuming isotropy for it. The value at 100 degr is used2158800500005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800500006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800500007 * background subtraction, 2158800500008 * detector efficiency and 2158800500009 * calculation of total neutron yields. 2158800500010 Total errors are about 20% 2158800500011 of the obtained cross sections. 2158800500012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800500013 HISTORY (19821124A) Reaction string corrected. 2158800500014 (20170811A) SD: SF4=Hg-0 was added to REACTION code. 2158800500015 ENDBIB 13 0 2158800500016 NOCOMMON 0 0 2158800500017 DATA 4 1 2158800500018 ANG MONIT DATA DATA-ERR 2158800500019 ADEG MB/SR B PER-CENT 2158800500020 100. 50. 2.10 20. 2158800500021 ENDDATA 3 0 2158800500022 ENDSUBENT 21 0 2158800599999 SUBENT 21588006 20170811 22632158800600001 BIB 6 13 2158800600002 REACTION (81-TL-0(N,INL)81-TL-0,,DA,,4PI) 2158800600003 ANALYSIS (INTAD) Integration of the angular distribution 2158800600004 assuming isotropy for it. The value at 100 degr is used2158800600005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800600006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800600007 * background subtraction, 2158800600008 * detector efficiency and 2158800600009 * calculation of total neutron yields. 2158800600010 Total errors are about 20% 2158800600011 of the obtained cross sections. 2158800600012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800600013 HISTORY (19821124A) Reaction string corrected. 2158800600014 (20170811A) SD: SF4=Tl-0 was added to REACTION code. 2158800600015 ENDBIB 13 0 2158800600016 NOCOMMON 0 0 2158800600017 DATA 4 1 2158800600018 ANG MONIT DATA DATA-ERR 2158800600019 ADEG MB/SR B PER-CENT 2158800600020 100. 50. 1.96 20. 2158800600021 ENDDATA 3 0 2158800600022 ENDSUBENT 21 0 2158800699999 SUBENT 21588007 20170811 22632158800700001 BIB 6 13 2158800700002 REACTION (82-PB-0(N,INL)82-PB-0,,DA,,4PI) 2158800700003 ANALYSIS (INTAD) Integration of the angular distribution 2158800700004 assuming isotropy for it. The value at 100 degr is used2158800700005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800700006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800700007 * background subtraction, 2158800700008 * detector efficiency and 2158800700009 * calculation of total neutron yields. 2158800700010 Total errors are about 20% 2158800700011 of the obtained cross sections. 2158800700012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800700013 HISTORY (19821124A) Reaction string corrected. 2158800700014 (20170811A) SD: SF4=Pb-0 was added to REACTION code. 2158800700015 ENDBIB 13 0 2158800700016 NOCOMMON 0 0 2158800700017 DATA 4 1 2158800700018 ANG MONIT DATA DATA-ERR 2158800700019 ADEG MB/SR B PER-CENT 2158800700020 100. 50. 2.18 20. 2158800700021 ENDDATA 3 0 2158800700022 ENDSUBENT 21 0 2158800799999 SUBENT 21588008 20170811 22632158800800001 BIB 6 12 2158800800002 REACTION (83-BI-209(N,INL)83-BI-209,,DA,,4PI) 2158800800003 ANALYSIS (INTAD) Integration of the angular distribution 2158800800004 assuming isotropy for it. The value at 100 degr is used2158800800005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800800006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800800007 * background subtraction, 2158800800008 * detector efficiency and 2158800800009 * calculation of total neutron yields. 2158800800010 Total errors are about 20% 2158800800011 of the obtained cross sections. 2158800800012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800800013 HISTORY (19821124A) Reaction string corrected. 2158800800014 ENDBIB 12 0 2158800800015 NOCOMMON 0 0 2158800800016 DATA 4 1 2158800800017 ANG MONIT DATA DATA-ERR 2158800800018 ADEG MB/SR B PER-CENT 2158800800019 100. 50. 2.36 20. 2158800800020 ENDDATA 3 0 2158800800021 ENDSUBENT 20 0 2158800899999 SUBENT 21588009 20170811 22632158800900001 BIB 6 12 2158800900002 REACTION (73-TA-181(N,2N)73-TA-180,,DA,,4PI) 2158800900003 ANALYSIS (INTAD) Integration of the angular distribution 2158800900004 assuming isotropy for it. The value at 100 degr is used2158800900005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158800900006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158800900007 * background subtraction, 2158800900008 * detector efficiency and 2158800900009 * calculation of total neutron yields. 2158800900010 Total errors are about 20% 2158800900011 of the obtained cross sections. 2158800900012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158800900013 HISTORY (19821124A) Reaction string corrected. 2158800900014 ENDBIB 12 0 2158800900015 NOCOMMON 0 0 2158800900016 DATA 4 1 2158800900017 ANG MONIT DATA DATA-ERR 2158800900018 ADEG MB/SR B PER-CENT 2158800900019 100. 50. 1.79 20. 2158800900020 ENDDATA 3 0 2158800900021 ENDSUBENT 20 0 2158800999999 SUBENT 21588010 20170811 22632158801000001 BIB 6 12 2158801000002 REACTION (74-W-0(N,2N),,DA,,4PI) 2158801000003 ANALYSIS (INTAD) Integration of the angular distribution 2158801000004 assuming isotropy for it. The value at 100 degr is used2158801000005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158801000006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158801000007 * background subtraction, 2158801000008 * detector efficiency and 2158801000009 * calculation of total neutron yields. 2158801000010 Total errors are about 20% 2158801000011 of the obtained cross sections. 2158801000012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158801000013 HISTORY (19821124A) Reaction string corrected. 2158801000014 ENDBIB 12 0 2158801000015 NOCOMMON 0 0 2158801000016 DATA 4 1 2158801000017 ANG MONIT DATA DATA-ERR 2158801000018 ADEG MB/SR B PER-CENT 2158801000019 100. 50. 2.09 20. 2158801000020 ENDDATA 3 0 2158801000021 ENDSUBENT 20 0 2158801099999 SUBENT 21588011 20170811 22632158801100001 BIB 6 12 2158801100002 REACTION (79-AU-197(N,2N)79-AU-196,,DA,,4PI) 2158801100003 ANALYSIS (INTAD) Integration of the angular distribution 2158801100004 assuming isotropy for it. The value at 100 degr is used2158801100005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158801100006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158801100007 * background subtraction, 2158801100008 * detector efficiency and 2158801100009 * calculation of total neutron yields. 2158801100010 Total errors are about 20% 2158801100011 of the obtained cross sections. 2158801100012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158801100013 HISTORY (19821124A) Reaction string corrected. 2158801100014 ENDBIB 12 0 2158801100015 NOCOMMON 0 0 2158801100016 DATA 4 1 2158801100017 ANG MONIT DATA DATA-ERR 2158801100018 ADEG MB/SR B PER-CENT 2158801100019 100. 50. 1.71 20. 2158801100020 ENDDATA 3 0 2158801100021 ENDSUBENT 20 0 2158801199999 NOSUBENT 21588012 20170811 22632158801200001 SUBENT 21588013 20170811 22632158801300001 BIB 6 12 2158801300002 REACTION (80-HG-0(N,2N),,DA,,4PI) 2158801300003 ANALYSIS (INTAD) Integration of the angular distribution 2158801300004 assuming isotropy for it. The value at 100 degr is used2158801300005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158801300006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158801300007 * background subtraction, 2158801300008 * detector efficiency and 2158801300009 * calculation of total neutron yields. 2158801300010 Total errors are about 20% 2158801300011 of the obtained cross sections. 2158801300012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158801300013 HISTORY (19821124A) Reaction string corrected. 2158801300014 ENDBIB 12 0 2158801300015 NOCOMMON 0 0 2158801300016 DATA 4 1 2158801300017 ANG MONIT DATA DATA-ERR 2158801300018 ADEG MB/SR B PER-CENT 2158801300019 100. 50. 2.03 20. 2158801300020 ENDDATA 3 0 2158801300021 ENDSUBENT 20 0 2158801399999 SUBENT 21588014 20170811 22632158801400001 BIB 6 13 2158801400002 REACTION (81-TL-0(N,2N),,DA,,4PI) 2158801400003 ANALYSIS (INTAD) Integration of the angular distribution 2158801400004 assuming isotropy for it. The value at 100 degr is used2158801400005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158801400006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158801400007 * background subtraction, 2158801400008 * detector efficiency and 2158801400009 * calculation of total neutron yields. 2158801400010 Total errors are about 20% 2158801400011 of the obtained cross sections. 2158801400012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158801400013 HISTORY (19821124A) Reaction string corrected. 2158801400014 (20170811A) SD: SF4=Tl-0 was added to REACTION code. 2158801400015 ENDBIB 13 0 2158801400016 NOCOMMON 0 0 2158801400017 DATA 4 1 2158801400018 ANG MONIT DATA DATA-ERR 2158801400019 ADEG MB/SR B PER-CENT 2158801400020 100. 50. 1.92 20. 2158801400021 ENDDATA 3 0 2158801400022 ENDSUBENT 21 0 2158801499999 SUBENT 21588015 20170811 22632158801500001 BIB 6 12 2158801500002 REACTION (82-PB-0(N,2N),,DA,,4PI) 2158801500003 ANALYSIS (INTAD) Integration of the angular distribution 2158801500004 assuming isotropy for it. The value at 100 degr is used2158801500005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158801500006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158801500007 * background subtraction, 2158801500008 * detector efficiency and 2158801500009 * calculation of total neutron yields. 2158801500010 Total errors are about 20% 2158801500011 of the obtained cross sections. 2158801500012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158801500013 HISTORY (19821124A) Reaction string corrected. 2158801500014 ENDBIB 12 0 2158801500015 NOCOMMON 0 0 2158801500016 DATA 4 1 2158801500017 ANG MONIT DATA DATA-ERR 2158801500018 ADEG MB/SR B PER-CENT 2158801500019 100. 50. 2.13 20. 2158801500020 ENDDATA 3 0 2158801500021 ENDSUBENT 20 0 2158801599999 SUBENT 21588016 20170811 22632158801600001 BIB 6 12 2158801600002 REACTION (83-BI-209(N,2N)83-BI-208,,DA,,4PI) 2158801600003 ANALYSIS (INTAD) Integration of the angular distribution 2158801600004 assuming isotropy for it. The value at 100 degr is used2158801600005 MONITOR (83-BI-209(N,EL)83-BI-209,,DA) 2158801600006 ERR-ANALYS (DATA-ERR) Sources of error are: 2158801600007 * background subtraction, 2158801600008 * detector efficiency and 2158801600009 * calculation of total neutron yields. 2158801600010 Total errors are about 20% 2158801600011 of the obtained cross sections. 2158801600012 STATUS (TABLE) Table 6 from NST,11,(12),523,1974 2158801600013 HISTORY (19821124A) Reaction string corrected. 2158801600014 ENDBIB 12 0 2158801600015 NOCOMMON 0 0 2158801600016 DATA 4 1 2158801600017 ANG MONIT DATA DATA-ERR 2158801600018 ADEG MB/SR B PER-CENT 2158801600019 100. 50. 2.34 20. 2158801600020 ENDDATA 3 0 2158801600021 ENDSUBENT 20 0 2158801699999 SUBENT 21588017 20170811 22632158801700001 BIB 6 18 2158801700002 REACTION 1(73-TA-181(0,0),,TEM) 2158801700003 2(73-TA-181(0,0),,TEM) 2158801700004 ANALYSIS 1 Nuclear temperature obtained from statistical plot of 2158801700005 inelastically scattered neutrons, neglecting the 2158801700006 contribution of the (n,2n) process(from Ta-181(n,inl))2158801700007 (So-called effective nuclear temperature). 2158801700008 2 Nuclear temperature obtained from statistical plot of 2158801700009 the inelastically scattered neutrons, including the 2158801700010 contribution of the (n,2n) process. (Using the 2158801700011 formula of Le Couteur and Lang, see REL-REF). 2158801700012 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158801700013 ERR-ANALYS (DATA-ERR) The indicated errors represent only those 2158801700014 due to the root-mean-square values of the deviations 2158801700015 from the least-squares fit. 2158801700016 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158801700017 (DEP,21588002) Ta-181(n,inl) 2158801700018 2(DEP,21588009) Ta-181(n,2n) 2158801700019 HISTORY (20170811A) SD: Subents 017 and 038 were merged. 2158801700020 ENDBIB 18 0 2158801700021 NOCOMMON 0 0 2158801700022 DATA 4 1 2158801700023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2158801700024 MEV MEV MEV MEV 2158801700025 0.67 0.06 0.85 0.06 2158801700026 ENDDATA 3 0 2158801700027 ENDSUBENT 26 0 2158801799999 SUBENT 21588018 20170811 22632158801800001 BIB 6 18 2158801800002 REACTION 1(74-W-0(0,0),,TEM) 2158801800003 2(74-W-0(0,0),,TEM) 2158801800004 ANALYSIS 1 Nuclear temperature obtained from statistical plot of 2158801800005 inelastically scattered neutrons, neglecting the 2158801800006 contribution of the (n,2n) process(from W-0(n,inl)). 2158801800007 (So-called effective nuclear temperature). 2158801800008 2 Nuclear temperature obtained from statistical plot of 2158801800009 the inelastically scattered neutrons, including the 2158801800010 contribution of the (n,2n) process. (Using the 2158801800011 formula of Le Couteur and Lang, see REL-REF). 2158801800012 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158801800013 ERR-ANALYS (DATA-ERR) The indicated errors represent only those 2158801800014 due to the root-mean-square values of the deviations 2158801800015 from the least-squares fit. 2158801800016 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158801800017 (DEP,21588003) W-0(n,inl) 2158801800018 2(DEP,21588010) W-0(n,2n) 2158801800019 HISTORY (20170811A) SD: Subents 018 and 039 were merged. 2158801800020 ENDBIB 18 0 2158801800021 NOCOMMON 0 0 2158801800022 DATA 4 1 2158801800023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2158801800024 MEV MEV MEV MEV 2158801800025 0.67 0.07 0.85 0.08 2158801800026 ENDDATA 3 0 2158801800027 ENDSUBENT 26 0 2158801899999 SUBENT 21588019 20170811 22632158801900001 BIB 6 18 2158801900002 REACTION 1(79-AU-197(0,0),,TEM) 2158801900003 2(79-AU-197(0,0),,TEM) 2158801900004 ANALYSIS 1 Nuclear temperature obtained from statistical plot of 2158801900005 inelastically scattered neutrons, neglecting the 2158801900006 contribution of the (n,2n) process(from Au-197(n,inl))2158801900007 (So-called effective nuclear temperature). 2158801900008 2 Nuclear temperature obtained from statistical plot of 2158801900009 the inelastically scattered neutrons, including the 2158801900010 contribution of the (n,2n) process. (Using the 2158801900011 formula of Le Couteur and Lang, see REL-REF). 2158801900012 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158801900013 ERR-ANALYS (DATA-ERR) The indicated errors represent only those 2158801900014 due to the root-mean-square values of the deviations 2158801900015 from the least-squares fit. 2158801900016 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158801900017 (DEP,21588004) Au-197(n,inl) 2158801900018 2(DEP,21588011) Au-197(n,2n) 2158801900019 HISTORY (20170811A) SD: Subents 019 and 040 were merged. 2158801900020 ENDBIB 18 0 2158801900021 NOCOMMON 0 0 2158801900022 DATA 4 1 2158801900023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2158801900024 MEV MEV MEV MEV 2158801900025 0.73 0.04 0.93 0.03 2158801900026 ENDDATA 3 0 2158801900027 ENDSUBENT 26 0 2158801999999 SUBENT 21588020 20170811 22632158802000001 BIB 6 18 2158802000002 REACTION 1(80-HG-0(0,0),,TEM) 2158802000003 2(80-HG-0(0,0),,TEM) 2158802000004 ANALYSIS 1 Nuclear temperature obtained from statistical plot of 2158802000005 inelastically scattered neutrons, neglecting the 2158802000006 contribution of the (n,2n) process(from Hg-0(n,inl)). 2158802000007 (So-called effective nuclear temperature). 2158802000008 2 Nuclear temperature obtained from statistical plot of 2158802000009 the inelastically scattered neutrons, including the 2158802000010 contribution of the (n,2n) process. (Using the 2158802000011 formula of Le Couteur and Lang, see REL-REF). 2158802000012 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802000013 ERR-ANALYS (DATA-ERR) The indicated errors represent only those 2158802000014 due to the root-mean-square values of the deviations 2158802000015 from the least-squares fit. 2158802000016 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802000017 (DEP,21588005) Hg-0(n,inl) 2158802000018 2(DEP,21588013) Hg-0(n,2n) 2158802000019 HISTORY (20170811A) SD: Subents 020 and 041 were merged. 2158802000020 ENDBIB 18 0 2158802000021 NOCOMMON 0 0 2158802000022 DATA 4 1 2158802000023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2158802000024 MEV MEV MEV MEV 2158802000025 0.81 0.03 1.05 0.02 2158802000026 ENDDATA 3 0 2158802000027 ENDSUBENT 26 0 2158802099999 SUBENT 21588021 20170811 22632158802100001 BIB 6 18 2158802100002 REACTION 1(81-TL-0(0,0),,TEM) 2158802100003 2(81-TL-0(0,0),,TEM) 2158802100004 ANALYSIS 1 Nuclear temperature obtained from statistical plot of 2158802100005 inelastically scattered neutrons, neglecting the 2158802100006 contribution of the (n,2n) process(from Tl-0(n,inl)). 2158802100007 (So-called effective nuclear temperature). 2158802100008 2 Nuclear temperature obtained from statistical plot of 2158802100009 the inelastically scattered neutrons, including the 2158802100010 contribution of the (n,2n) process. (Using the 2158802100011 formula of Le Couteur and Lang, see REL-REF). 2158802100012 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802100013 ERR-ANALYS (DATA-ERR) The indicated errors represent only those 2158802100014 due to the root-mean-square values of the deviations 2158802100015 from the least-squares fit. 2158802100016 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802100017 (DEP,21588006) Tl-0(n,inl) 2158802100018 2(DEP,21588014) Tl-0(n,2n) 2158802100019 HISTORY (20170811A) SD: Subents 021 and 042 were merged. 2158802100020 ENDBIB 18 0 2158802100021 NOCOMMON 0 0 2158802100022 DATA 4 1 2158802100023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2158802100024 MEV MEV MEV MEV 2158802100025 0.89 0.05 1.18 0.05 2158802100026 ENDDATA 3 0 2158802100027 ENDSUBENT 26 0 2158802199999 SUBENT 21588022 20170811 22632158802200001 BIB 6 18 2158802200002 REACTION 1(82-PB-0(0,0),,TEM) 2158802200003 2(82-PB-0(0,0),,TEM) 2158802200004 ANALYSIS 1 Nuclear temperature obtained from statistical plot of 2158802200005 inelastically scattered neutrons, neglecting the 2158802200006 contribution of the (n,2n) process(from Pb-0(n,inl)). 2158802200007 (So-called effective nuclear temperature). 2158802200008 2 Nuclear temperature obtained from statistical plot of 2158802200009 the inelastically scattered neutrons, including the 2158802200010 contribution of the (n,2n) process. (Using the 2158802200011 formula of Le couteur and Lang, see REL-REF). 2158802200012 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802200013 ERR-ANALYS (DATA-ERR) The indicated errors represent only those 2158802200014 due to the root-mean-square values of the deviations 2158802200015 from the least-squares fit. 2158802200016 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802200017 (DEP,21588007) Pb-0(n,inl) 2158802200018 2(DEP,21588015) Pb-0(n,2n) 2158802200019 HISTORY (20170811A) SD: Subents 022 and 043 were merged. 2158802200020 ENDBIB 18 0 2158802200021 NOCOMMON 0 0 2158802200022 DATA 4 1 2158802200023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2158802200024 MEV MEV MEV MEV 2158802200025 0.77 0.04 1.00 0.05 2158802200026 ENDDATA 3 0 2158802200027 ENDSUBENT 26 0 2158802299999 SUBENT 21588023 20170811 22632158802300001 BIB 6 18 2158802300002 REACTION 1(83-BI-209(0,0),,TEM) 2158802300003 2(83-BI-209(0,0),,TEM) 2158802300004 ANALYSIS 1 Nuclear temperature obtained from statistical plot of 2158802300005 inelastically scattered neutrons, neglecting the 2158802300006 contribution of the (n,2n) process(from Bi-209(n,inl))2158802300007 (So-called effective nuclear temperature). 2158802300008 2 Nuclear temperature obtained from statistical plot of 2158802300009 the inelastically scattered neutrons, including the 2158802300010 contribution of the (n,2n) process. (Using the 2158802300011 formula of Le Couteur and Lang, see REL-REF). 2158802300012 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802300013 ERR-ANALYS (DATA-ERR) The indicated errors represent only those 2158802300014 due to the root-mean-square values of the deviations 2158802300015 from the least-squares fit. 2158802300016 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802300017 (DEP,21588007) Bi-209(n,inl) 2158802300018 2(DEP,21588015) Bi-209(n,2n) 2158802300019 HISTORY (20170811A) SD: Subents 023 and 044 were merged. 2158802300020 ENDBIB 18 0 2158802300021 NOCOMMON 0 0 2158802300022 DATA 4 1 2158802300023 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2158802300024 MEV MEV MEV MEV 2158802300025 0.79 0.03 1.03 0.03 2158802300026 ENDDATA 3 0 2158802300027 ENDSUBENT 26 0 2158802399999 SUBENT 21588024 20170811 22632158802400001 BIB 6 15 2158802400002 REACTION 1(73-TA-181(0,0),,LDP) 2158802400003 2(73-TA-181(0,0),,LDP) 2158802400004 ANALYSIS 1 Nuclear level density obtained from statistical plot 2158802400005 of inelastically scattered neutrons, neglecting the 2158802400006 contribution of the (n,2n) process 2158802400007 2 Nuclear level density obtained from statistical plot 2158802400008 of inelastically scattered neutrons, neglecting the 2158802400009 contribution of the (n,2n) process. (Using the 2158802400010 formula of Le Couteur and Lang, see REL-REF). 2158802400011 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802400012 ERR-ANALYS .No error given. 2158802400013 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802400014 (DEP,21588002) Ta-181(n,inl) 2158802400015 2(DEP,21588009) Ta-181(n,2n) 2158802400016 HISTORY (20170811A) SD: Subents 024 and 031 were merged. 2158802400017 ENDBIB 15 0 2158802400018 NOCOMMON 0 0 2158802400019 DATA 2 1 2158802400020 DATA 1DATA 2 2158802400021 1/MEV 1/MEV 2158802400022 30.0 23.3 2158802400023 ENDDATA 3 0 2158802400024 ENDSUBENT 23 0 2158802499999 SUBENT 21588025 20170811 22632158802500001 BIB 6 15 2158802500002 REACTION 1(74-W-0(0,0),,LDP) 2158802500003 2(74-W-0(0,0),,LDP) 2158802500004 ANALYSIS 1 Nuclear level density obtained from statistical plot 2158802500005 of inelastically scattered neutrons, neglecting the 2158802500006 contribution of the (n,2n) process 2158802500007 2 Nuclear level density obtained from statistical plot 2158802500008 of inelastically scattered neutrons, neglecting the 2158802500009 contribution of the (n,2n) process. (Using the 2158802500010 formula of Le Couteur and Lang, see REL-REF). 2158802500011 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802500012 ERR-ANALYS .No error given. 2158802500013 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802500014 (DEP,21588003) W-0(n,inl) 2158802500015 2(DEP,21588010) W-0(n,2n) 2158802500016 HISTORY (20170811A) SD: Subents 025 and 032 were merged. 2158802500017 ENDBIB 15 0 2158802500018 NOCOMMON 0 0 2158802500019 DATA 2 1 2158802500020 DATA 1DATA 2 2158802500021 1/MEV 1/MEV 2158802500022 31.2 24.9 2158802500023 ENDDATA 3 0 2158802500024 ENDSUBENT 23 0 2158802599999 SUBENT 21588026 20170811 22632158802600001 BIB 6 15 2158802600002 REACTION 1(79-AU-197(0,0),,LDP) 2158802600003 2(79-AU-197(0,0),,LDP) 2158802600004 ANALYSIS 1 Nuclear level density obtained from statistical plot 2158802600005 of inelastically scattered neutrons, neglecting the 2158802600006 contribution of the (n,2n) process 2158802600007 2 Nuclear level density obtained from statistical plot 2158802600008 of inelastically scattered neutrons, neglecting the 2158802600009 contribution of the (n,2n) process. (Using the 2158802600010 formula of Le Couteur and Lang, see REL-REF). 2158802600011 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802600012 ERR-ANALYS .No error given. 2158802600013 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802600014 (DEP,21588004) Au-197(n,inl) 2158802600015 2(DEP,21588011) Au-197(n,2n) 2158802600016 HISTORY (20170811A) SD: Subents 026 and 033 were merged. 2158802600017 ENDBIB 15 0 2158802600018 NOCOMMON 0 0 2158802600019 DATA 2 1 2158802600020 DATA 1DATA 2 2158802600021 1/MEV 1/MEV 2158802600022 25.5 18.9 2158802600023 ENDDATA 3 0 2158802600024 ENDSUBENT 23 0 2158802699999 SUBENT 21588027 20170811 22632158802700001 BIB 6 15 2158802700002 REACTION 1(80-HG-0(0,0),,LDP) 2158802700003 2(80-HG-0(0,0),,LDP) 2158802700004 ANALYSIS 1 Nuclear level density obtained from statistical plot 2158802700005 of inelastically scattered neutrons, neglecting the 2158802700006 contribution of the (n,2n) process 2158802700007 2 Nuclear level density obtained from statistical plot 2158802700008 of inelastically scattered neutrons, neglecting the 2158802700009 contribution of the (n,2n) process. (Using the 2158802700010 formula of Le Couteur and Lang, see REL-REF). 2158802700011 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802700012 ERR-ANALYS .No error given. 2158802700013 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802700014 (DEP,21588005) Hg-0(n,inl) 2158802700015 2(DEP,21588013) Hg-0(n,2n) 2158802700016 HISTORY (20170811A) SD: Subents 027 and 034 were merged. 2158802700017 ENDBIB 15 0 2158802700018 NOCOMMON 0 0 2158802700019 DATA 2 1 2158802700020 DATA 1DATA 2 2158802700021 1/MEV 1/MEV 2158802700022 21.6 14.5 2158802700023 ENDDATA 3 0 2158802700024 ENDSUBENT 23 0 2158802799999 SUBENT 21588028 20170811 22632158802800001 BIB 6 15 2158802800002 REACTION 1(81-TL-0(0,0),,LDP) 2158802800003 2(81-TL-0(0,0),,LDP) 2158802800004 ANALYSIS 1 Nuclear level density obtained from statistical plot 2158802800005 of inelastically scattered neutrons, neglecting the 2158802800006 contribution of the (n,2n) process 2158802800007 2 Nuclear level density obtained from statistical plot 2158802800008 of inelastically scattered neutrons, neglecting the 2158802800009 contribution of the (n,2n) process. (Using the 2158802800010 formula of Le Couteur and Lang, see REL-REF). 2158802800011 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802800012 ERR-ANALYS .No error given. 2158802800013 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802800014 (DEP,21588006) Tl-0(n,inl) 2158802800015 2(DEP,21588014) Tl-0(n,2n) 2158802800016 HISTORY (20170811A) SD: Subents 028 and 035 were merged. 2158802800017 ENDBIB 15 0 2158802800018 NOCOMMON 0 0 2158802800019 DATA 2 1 2158802800020 DATA 1DATA 2 2158802800021 1/MEV 1/MEV 2158802800022 16.6 11.2 2158802800023 ENDDATA 3 0 2158802800024 ENDSUBENT 23 0 2158802899999 SUBENT 21588029 20170811 22632158802900001 BIB 6 15 2158802900002 REACTION 1(82-PB-0(0,0),,LDP) 2158802900003 2(82-PB-0(0,0),,LDP) 2158802900004 ANALYSIS 1 Nuclear level density obtained from statistical plot 2158802900005 of inelastically scattered neutrons, neglecting the 2158802900006 contribution of the (n,2n) process 2158802900007 2 Nuclear level density obtained from statistical plot 2158802900008 of inelastically scattered neutrons, neglecting the 2158802900009 contribution of the (n,2n) process. (Using the 2158802900010 formula of Le Couteur and Lang, see REL-REF). 2158802900011 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158802900012 ERR-ANALYS .No error given. 2158802900013 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158802900014 (DEP,21588007) Pb-0(n,inl) 2158802900015 2(DEP,21588015) Pb-0(n,2n) 2158802900016 HISTORY (20170811A) SD: Subents 029 and 036 were merged. 2158802900017 ENDBIB 15 0 2158802900018 NOCOMMON 0 0 2158802900019 DATA 2 1 2158802900020 DATA 1DATA 2 2158802900021 1/MEV 1/MEV 2158802900022 20.8 15.1 2158802900023 ENDDATA 3 0 2158802900024 ENDSUBENT 23 0 2158802999999 SUBENT 21588030 20170811 22632158803000001 BIB 6 15 2158803000002 REACTION 1(83-BI-209(0,0),,LDP) 2158803000003 2(83-BI-209(0,0),,LDP) 2158803000004 ANALYSIS 1 Nuclear level density obtained from statistical plot 2158803000005 of inelastically scattered neutrons, neglecting the 2158803000006 contribution of the (n,2n) process 2158803000007 2 Nuclear level density obtained from statistical plot 2158803000008 of inelastically scattered neutrons, neglecting the 2158803000009 contribution of the (n,2n) process. (Using the 2158803000010 formula of Le Couteur and Lang, see REL-REF). 2158803000011 REL-REF (M,,K.J.Le Couteur+,J,NP,13,32,1959) 2158803000012 ERR-ANALYS .No error given. 2158803000013 STATUS (TABLE) Table 2 from NST,11,(12),523,1974 2158803000014 (DEP,21588008) Bi-209(n,inl) 2158803000015 2(DEP,21588016) Bi-209(n,2n) 2158803000016 HISTORY (20170811A) SD: Subents 030 and 037 were merged. 2158803000017 ENDBIB 15 0 2158803000018 NOCOMMON 0 0 2158803000019 DATA 2 1 2158803000020 DATA 1DATA 2 2158803000021 1/MEV 1/MEV 2158803000022 23.0 16.7 2158803000023 ENDDATA 3 0 2158803000024 ENDSUBENT 23 0 2158803099999 NOSUBENT 21588031 20170811 22632158803100001 NOSUBENT 21588032 20170811 22632158803200001 NOSUBENT 21588033 20170811 22632158803300001 NOSUBENT 21588034 20170811 22632158803400001 NOSUBENT 21588035 20170811 22632158803500001 NOSUBENT 21588036 20170811 22632158803600001 NOSUBENT 21588037 20170811 22632158803700001 NOSUBENT 21588038 20170811 22632158803800001 NOSUBENT 21588039 20170811 22632158803900001 NOSUBENT 21588040 20170811 22632158804000001 NOSUBENT 21588041 20170811 22632158804100001 NOSUBENT 21588042 20170811 22632158804200001 NOSUBENT 21588043 20170811 22632158804300001 NOSUBENT 21588044 20170811 22632158804400001 ENDENTRY 44 0 2158899999999