ENTRY 12497 20120814 13851249700000001 SUBENT 12497001 20120814 13851249700100001 BIB 11 27 1249700100002 INSTITUTE (1USALRL) 1249700100003 REFERENCE (J,PR,107,1294,195705) 1249700100004 AUTHOR (E.K.Hulet,R.W.Hoff,H.R.Bowman,M.C.Michel) 1249700100005 TITLE Thermal neutron fission cross sections for isotopes 1249700100006 of plutonium,americium and curium. 1249700100007 FACILITY (REAC,1USALRL) The thermal column of the Materials 1249700100008 Testing Reactor 1249700100009 INC-SOURCE Neutron flux of approximately 5 x 10**10 n/cm2/sec 1249700100010 MONITOR (94-PU-239(N,F),,SIG,,MXW) 1249700100011 MONIT-REF (,D.J.Hughes+,R,AECU-2040,1955) 1249700100012 Neutron Cross Sections, Atomic Energy Commission Report1249700100013 AECU-2040 (Technical Information Division, Department 1249700100014 of Commerce, Washington, D.C.,1955), second edition 1249700100015 DETECTOR (FISCH) The fission counter was the double chamber type1249700100016 with one chamber containing a Pu-239 standard acting as1249700100017 a flux monitor. In the second chamber alternate counts 1249700100018 were taken on the sample, blank background plates and 1249700100019 Pu-239 standards. Of the six Pu-239 standards used, 1249700100020 three were nearly isotopically pure Pu-239, while the 1249700100021 others contained a known amount of Pu-240. 1249700100022 STATUS (TABLE) From Table 1 and text of PR,107,1294,1957 1249700100023 HISTORY (19760804T) Translated from SCISRS 1249700100024 (19830809A) converted to reaction formalism 1249700100025 (20120814A) SD:Updated to new date formats,lower case. 1249700100026 Corrected according to last EXFOR rules and Dict. 1249700100027 BIB updated. Author's name corrected. 1249700100028 MONIT moved to COMMON of Subent 1. 1249700100029 ENDBIB 27 0 1249700100030 COMMON 1 3 1249700100031 MONIT 1249700100032 B 1249700100033 806. 1249700100034 ENDCOMMON 3 0 1249700100035 ENDSUBENT 34 0 1249700199999 SUBENT 12497002 20120814 13851249700200001 BIB 5 6 1249700200002 REACTION (94-PU-238(N,F),,SIG,,MXW) 1249700200003 DECAY-DATA (94-PU-238,89.6YR,A,1.) 1249700200004 ANALYSIS Alpha pulse analysis was done. 1249700200005 SAMPLE Isotopic composition: Pu-238 - 99.71+-0.01%; 1249700200006 Pu-239 - 0.092+-0.003; Pu-240 - 0.194+-0.007 1249700200007 ERR-ANALYS (DATA-ERR) No information about source of uncertainties1249700200008 ENDBIB 6 0 1249700200009 NOCOMMON 0 0 1249700200010 DATA 3 1 1249700200011 EN-DUMMY DATA DATA-ERR 1249700200012 EV B B 1249700200013 0.0253 18.4 0.9 1249700200014 ENDDATA 3 0 1249700200015 ENDSUBENT 14 0 1249700299999 SUBENT 12497003 20120814 13851249700300001 BIB 8 30 1249700300002 REACTION (94-PU-238(N,G)94-PU-239,,SIG,,SPA) 1249700300003 METHOD (ACTIV) Activation 1249700300004 The pile-neutron capture cross section of Pu-238 was 1249700300005 measured by inserting three quartz capsules, each 1249700300006 containing about a microgram of the same Pu-238 used 1249700300007 in the fission cross-section measurements, into the 1249700300008 rabbit facility of the Materials Testing Reactor for 1249700300009 approximately two, three, and five days' neutron 1249700300010 irradiation, respectively. 1249700300011 After separation and purification of the plutonium, 1249700300012 plated samples were made, and the amount of Pu-239 1249700300013 produced in each irradiation was determined by 1249700300014 fission-counting. 1249700300015 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 1249700300016 The pile-neutron flux was monitored by the neutron- 1249700300017 capture activation of cobalt wire and the results were 1249700300018 corrected for resonance neutron activation and 1249700300019 self-protection. 1249700300020 CORRECTION It was necessary to make a slight correction in the 1249700300021 fission-counting rate for those fissions contributed 1249700300022 by Pu-238. 1249700300023 ANALYSIS Allowing for the destruction of a small fraction of 1249700300024 the Pu-238 and of Pu-239 during its formation, the 1249700300025 resulting Pu-238/Pu-239 ratio and the known integrated 1249700300026 neutron flux on each sample yield a capture cross 1249700300027 section of 520+-40 barns. 1249700300028 ERR-ANALYS (DATA-ERR) No information about source of uncertainties1249700300029 STATUS (DEP,12497002) Assumed Pu-238 fission = 18.4 b and 1249700300030 Pu-238 HL = 89.6 yr. 1249700300031 HISTORY (20120814A)SD: MONITOR was changed. 1249700300032 ENDBIB 30 0 1249700300033 NOCOMMON 0 0 1249700300034 DATA 3 1 1249700300035 EN-DUMMY DATA DATA-ERR 1249700300036 EV B B 1249700300037 0.0253 520. 40. 1249700300038 ENDDATA 3 0 1249700300039 ENDSUBENT 38 0 1249700399999 SUBENT 12497004 20120814 13851249700400001 BIB 6 6 1249700400002 REACTION (95-AM-241(N,F),,SIG,,MXW) 1249700400003 SAMPLE Am-241 1249700400004 DECAY-DATA (95-AM-241,461.3YR,A,1.) 1249700400005 ANALYSIS Alpha pulse analysis was done. 1249700400006 INC-SPECT Thermal spectrum 1249700400007 ERR-ANALYS (DATA-ERR) No information about source of uncertainties1249700400008 ENDBIB 6 0 1249700400009 NOCOMMON 0 0 1249700400010 DATA 3 1 1249700400011 EN-DUMMY DATA DATA-ERR 1249700400012 EV B B 1249700400013 0.0253 3.13 0.15 1249700400014 ENDDATA 3 0 1249700400015 ENDSUBENT 14 0 1249700499999 SUBENT 12497005 20120814 13851249700500001 BIB 7 14 1249700500002 REACTION (95-AM-242-M(N,F),,SIG,,MXW) 1249700500003 Averaged from purified and non-purified samples. 1249700500004 SAMPLE Isotopic composition: Am-241 - 37.49+-0.29%; 1249700500005 Am-242 - 0.413+-0.01%; Am-243 - 62.10+-0.28% 1249700500006 ANALYSIS The following alpha-decay half-lives were used in 1249700500007 calculating specific activities: 1249700500008 Am-241 half-life=461.3yr, Am-243 half-life=8200yr and 1249700500009 Cm-242 half-life=0.4455yr. 1249700500010 INC-SPECT Thermal spectrum 1249700500011 COMMENT It is not quite clear from the article what isotope 1249700500012 was measured. From half-lives that authors used in 1249700500013 calculations one can made conclude that it is Am-242-m.1249700500014 ERR-ANALYS (DATA-ERR) No information about source of uncertainties1249700500015 HISTORY (20120814A) SD: SF1=Am-242 => SF1=Am-242m. See COMMENT.1249700500016 ENDBIB 14 0 1249700500017 NOCOMMON 0 0 1249700500018 DATA 3 1 1249700500019 EN-DUMMY DATA DATA-ERR 1249700500020 EV B B 1249700500021 0.0253 6390. 500. 1249700500022 ENDDATA 3 0 1249700500023 ENDSUBENT 22 0 1249700599999 SUBENT 12497006 20120814 13851249700600001 BIB 4 10 1249700600002 REACTION (95-AM-243(N,F),,SIG,,MXW) 1249700600003 Average from purified and non-purified samples. 1249700600004 SAMPLE Isotopic composition: Am-241 - 0.083+-0.002%; 1249700600005 Am-242 - 0.00092% (calculated); Am-243 - 99.91+-0.004% 1249700600006 ANALYSIS The following alpha-decay half-lives were used in 1249700600007 calculating specific activities: 1249700600008 Am-241 half-life=461.3yr, Am-243 half-life=8200yr, 1249700600009 Cm-242 half-life=0.4455yr, Cm-244 half-life 19.yr, 1249700600010 Pu-238 half-life 89.6yr. 1249700600011 INC-SPECT Thermal spectrum 1249700600012 ENDBIB 10 0 1249700600013 NOCOMMON 0 0 1249700600014 DATA 2 1 1249700600015 EN-DUMMY DATA-MAX 1249700600016 EV B 1249700600017 0.0253 0.072 1249700600018 ENDDATA 3 0 1249700600019 ENDSUBENT 18 0 1249700699999 SUBENT 12497007 20120814 13851249700700001 BIB 6 12 1249700700002 REACTION (96-CM-243(N,F),,SIG,,MXW) 1249700700003 DECAY-DATA (96-CM-243,19.YR) 1249700700004 SAMPLE Isotopic composition: Cm-242 - 23.16+-0.35%; 1249700700005 Cm-243 - 32.06+-0.43; Cm-244 - 44.78+-0.37%; 1249700700006 Cm-245 <0.17%. 1249700700007 ANALYSIS The following alpha-decay half-lives were used in 1249700700008 calculating specific activities: 1249700700009 Am-241 half-life=461.3yr, Am-243 half-life=8200yr, 1249700700010 Cm-242 half-life=0.4455yr, Cm-244 half-life 19.yr, 1249700700011 Pu-238 half-life 89.6yr. 1249700700012 ERR-ANALYS (DATA-ERR) No information about source of uncertainties1249700700013 INC-SPECT Thermal spectrum 1249700700014 ENDBIB 12 0 1249700700015 NOCOMMON 0 0 1249700700016 DATA 3 1 1249700700017 EN-DUMMY DATA DATA-ERR 1249700700018 EV B B 1249700700019 0.0253 690. 50. 1249700700020 ENDDATA 3 0 1249700700021 ENDSUBENT 20 0 1249700799999 SUBENT 12497008 20120814 13851249700800001 BIB 5 8 1249700800002 REACTION (96-CM-245(N,F),,SIG,,MXW) 1249700800003 SAMPLE Isotopic composition: Cm-242 - < 0.03%; 1249700800004 Cm-244 - 95.50+-0.07%; Cm-245 - 1.62+-0.1%; 1249700800005 Cm-246 - 2.88+-0.2%. 1249700800006 ANALYSIS The following alpha-decay half-live was used in 1249700800007 calculating specific activities: Cm-244 half-life 19.yr1249700800008 INC-SPECT Thermal spectrum 1249700800009 ERR-ANALYS (DATA-ERR) No information about source of uncertainties1249700800010 ENDBIB 8 0 1249700800011 NOCOMMON 0 0 1249700800012 DATA 3 1 1249700800013 EN-DUMMY DATA DATA-ERR 1249700800014 EV B B 1249700800015 0.0253 1880. 150. 1249700800016 ENDDATA 3 0 1249700800017 ENDSUBENT 16 0 1249700899999 ENDENTRY 8 0 1249799999999