ENTRY 13270 20201203 14751327000000001 SUBENT 13270001 20201203 14751327000100001 BIB 8 34 1327000100002 TITLE Fission yields of over 40 stable and long-lived 1327000100003 fission products for thermal neutron fissioned 233U, 1327000100004 235U, 239Pu and 241Pu and fast reactor fissioned 235U 1327000100005 and 239Pu 1327000100006 AUTHOR (F.L.Lisman,R.M.Abernathey,W.J.Maeck,J.E.Rein) 1327000100007 REFERENCE (J,NSE,42,191,1970) 1327000100008 #doi:10.13182/NSE70-A19500 1327000100009 (R,IN-1277,1968) Fast fission yields for Pu239 - 1327000100010 the same as in the main ref. 1327000100011 (R,IDO-14660,1965) Data on thermal fission yields for 1327000100012 235U (sample 115.2 mg of U3O8) were included in 1327000100013 R,IDO-14667,1965, averaged with data for the 81.94 mg 1327000100014 sample and these averaged data were included in 13848. 1327000100015 REL-REF (O,13848001,W.J.Maeck+,R,IDO-14676,1966) Data on 1327000100016 thermal fission yields of Ru for 233U (samples 152.4 1327000100017 mg and 126.0 mg of U3O8) and for U235 (samples 115.2 1327000100018 mg and 81.94 mg of U3O8), included in 13848. 1327000100019 (O,13848001,W.J.Maeck+,R,IDO-14681,1967) Data on 1327000100020 thermal fission yields for 233U (samples 58.8 mg and 1327000100021 144.4 mg of U3O8), included in 13848. 1327000100022 INSTITUTE (1USAMTR) 1327000100023 ERR-ANALYS (DATA-ERR) Data uncertainties given are standard 1327000100024 deviations. 1327000100025 CORRECTION Fission products were corrected for buildup and burnout1327000100026 by neutron capture and loss by radioactive decay. 1327000100027 HISTORY (19890815C) VM 1327000100028 (20180411A) BP: Updated to new date formats,lower case.1327000100029 corrections according last EXFOR rules and Dict. 1327000100030 (20201204A) OG. 2-nd - 4-th REFERENCEs added. SAMPLE in1327000100031 Sub002-015, STATUS in Sub002-020 updated. ELEMENT 1327000100032 deleted from DATA in Sub002. ELEM/MASS,CUM replaced by 1327000100033 MASS,CHN in Sub003-004, 007-020. Sub009 was split 1327000100034 and Sub021 was added. Sub022-025 added. Corrected 1327000100035 REACTION in sub.5. Some data replaced in sub.2. 1327000100036 ENDBIB 34 0 1327000100037 NOCOMMON 0 0 1327000100038 ENDSUBENT 37 0 1327000199999 SUBENT 13270002 20201203 14751327000200001 BIB 9 32 1327000200002 REACTION 1(92-U-233(N,F)MASS,CHN,FY,,SPA) 1327000200003 2(92-U-233(N,F)MASS,CHN,FY,,SPA) Calculated by the 1327000200004 normalization technique 1327000200005 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000200006 INC-SPECT Thermal reactor neutron spectrum. 1327000200007 SAMPLE Four standard burnup capsule 1327000200008 CIPP-6-2-4, contained 58.8+-0.2 mg of enriched U3O8, 1327000200009 CIPP-6-4-2, contained 152.4 mg of enriched U3O8, 1327000200010 CIPP-6-4-3, contained 126.0 mg of enriched U3O8, 1327000200011 CIPP-6-5-1, contained 144.4 mg of enriched U3O8. 1327000200012 (92-U-233,ENR=0.99908) 1327000200013 (92-U-234,ENR=0.00026) 1327000200014 (92-U-235,ENR=0.000032) 1327000200015 (92-U-238,ENR=0.00062) 1327000200016 METHOD (ASEP) 1327000200017 (CHSEP) Flag 4. 1327000200018 FLAG 1(4.) Radiometric yield. 1327000200019 ANALYSIS Normalization technique used for DATA 2: Yields 1327000200020 relative to 148Nd were calculated for each mass chain 1327000200021 between mass 116 and 160 for each of the capsules. An 1327000200022 inverse variance weighted average of the relative 1327000200023 yield for each mass chain then was used for the 1327000200024 normalization. Estimated yields of Ferguson and 1327000200025 O'Kelley,ORNL-3305,1962 were assigned a +- 20% 1327000200026 relative uncertainty, and used for the unmeasured 1327000200027 mass chains. 1327000200028 STATUS (TABLE) Tab.VI (p.197)-DATA 1, Tab.VII (p.198)-DATA 2 1327000200029 in Nucl.Sc.Eng.,42,191,1970. 1327000200030 HISTORY (20201203A) OG. SAMPLE, METHOD and STATUS updated. 1327000200031 ELEMENT deleted from DATA. FLAG 4 added. DATA 2 added. 1327000200032 For 5 data points (A=147,149,151,152,154) Walker's 1327000200033 adjusted values replaced by original data from Table VI1327000200034 ENDBIB 32 0 1327000200035 COMMON 1 3 1327000200036 EN-DUMMY 1327000200037 EV 1327000200038 0.0253 1327000200039 ENDCOMMON 3 0 1327000200040 DATA 6 41 1327000200041 MASS DATA 1DATA-ERR 1FLAG 1DATA 2DATA-ERR 21327000200042 NO-DIM PC/FIS PC/FIS NO-DIM PC/FIS PC/FIS 1327000200043 83. 1.03 0.01 1.02 0.02 1327000200044 84. 1.73 0.02 1.71 0.04 1327000200045 85. 2.22 0.02 2.21 0.05 1327000200046 86. 2.90 0.03 2.88 0.07 1327000200047 87. 4.06 0.03 4.04 0.09 1327000200048 88. 5.57 0.04 5.56 0.13 1327000200049 90. 6.96 0.06 6.96 0.16 1327000200050 91. 6.60 0.05 6.64 0.16 1327000200051 92. 6.69 0.05 6.69 0.16 1327000200052 93. 7.09 0.06 7.08 0.17 1327000200053 94. 6.91 0.05 6.92 0.16 1327000200054 95. 6.40 0.05 6.30 0.15 1327000200055 96. 5.84 0.05 5.80 0.14 1327000200056 97. 5.52 0.05 5.43 0.13 1327000200057 98. 5.22 0.04 5.16 0.12 1327000200058 99. 5.16 0.07 5.06 0.13 1327000200059 100. 4.46 0.04 4.41 0.10 1327000200060 101. 3.27 0.02 3.24 0.08 1327000200061 102. 2.48 0.02 2.44 0.06 1327000200062 104. 1.04 0.01 1.01 0.02 1327000200063 106. 0.262 0.002 0.260 0.0061327000200064 125. 0.116 0.013 4. 1327000200065 131. 3.51 0.04 3.50 0.09 1327000200066 132. 4.88 0.06 4.86 0.12 1327000200067 133. 6.06 0.05 6.05 0.14 1327000200068 134. 6.13 0.07 6.10 0.15 1327000200069 137. 6.93 0.06 6.94 0.16 1327000200070 138. 5.97 0.05 6.00 0.14 1327000200071 140. 6.53 0.05 6.48 0.15 1327000200072 142. 6.71 0.05 6.61 0.15 1327000200073 143. 5.85 0.05 5.82 0.13 1327000200074 144. 4.67 0.04 4.66 0.11 1327000200075 145. 3.37 0.03 3.36 0.08 1327000200076 146. 2.53 0.02 2.52 0.06 1327000200077 147. 1.78 0.04 1.74 0.06 1327000200078 148. 1.30 0.01 1.30 0.03 1327000200079 149. 0.773 0.007 0.744 0.0171327000200080 150. 0.500 0.004 0.497 0.0111327000200081 151. 0.365 0.011 0.364 0.0201327000200082 152. 0.186 0.004 0.185 0.0071327000200083 154. 0.0458 0.0006 0.0445 0.00101327000200084 ENDDATA 43 0 1327000200085 ENDSUBENT 84 0 1327000299999 SUBENT 13270003 20201203 14751327000300001 BIB 8 17 1327000300002 REACTION (92-U-235(N,F)MASS,CHN,FY,,SPA) 1327000300003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000300004 INC-SPECT Thermal reactor neutron spectrum. 1327000300005 SAMPLE Four standard burnup capsule 1327000300006 CIPP-6-4-1, contained 115.2+-0.1 mg of enriched U3O8, 1327000300007 CIPP-6-6-2, contained 81.94+-0.10 mg of enriched U3O8, 1327000300008 CIPP-6-2-2, contained 61.2+-0.1 mg of enriched U3O8, 1327000300009 CIPP-6-5-3, contained 122.0 mg of enriched U3O8. 1327000300010 (92-U-234,ENR=0.004677) 1327000300011 (92-U-235,ENR=0.991633) 1327000300012 (92-U-236,ENR=0.000603) 1327000300013 (92-U-238,ENR=0.003087) 1327000300014 METHOD (ASEP) 1327000300015 FLAG (2.) Data in error, Maeck, et al., ICP-1092 (1976) 1327000300016 STATUS (TABLE) Tab. II (p. 194) in Nucl.Sc.Eng.,42,191,1970. 1327000300017 HISTORY (20201203A) OG. SAMPLE and STATUS updated. 1327000300018 ELEM/MASS,CUM replaced by MASS,CHN. 1327000300019 ENDBIB 17 0 1327000300020 COMMON 1 3 1327000300021 EN-DUMMY 1327000300022 EV 1327000300023 0.0253 1327000300024 ENDCOMMON 3 0 1327000300025 DATA 4 31 1327000300026 MASS DATA DATA-ERR FLAG 1327000300027 NO-DIM PC/FIS PC/FIS NO-DIM 1327000300028 87. 2.54 .01 1327000300029 88. 3.61 0.02 1327000300030 90. 5.90 0.04 1327000300031 95. 6.45 0.03 1327000300032 97. 5.86 0.03 1327000300033 98. 5.77 0.03 1327000300034 99. 6.14 0.10 1327000300035 100. 6.24 0.03 1327000300036 101. 5.03 0.04 1327000300037 102. 4.19 0.04 1327000300038 104. 1.82 0.01 1327000300039 106. 0.389 0.004 1327000300040 131. 2.79 0.04 2. 1327000300041 132. 4.16 0.06 2. 1327000300042 133. 6.73 0.04 1327000300043 134. 7.51 0.11 2. 1327000300044 137. 6.28 0.03 1327000300045 138. 6.80 0.03 2. 1327000300046 140. 6.31 0.03 1327000300047 142. 5.88 0.03 1327000300048 143. 5.90 0.03 1327000300049 144. 5.42 0.02 1327000300050 145. 3.86 0.02 1327000300051 146. 2.95 0.01 1327000300052 147. 2.12 0.04 1327000300053 148. 1.69 0.01 2. 1327000300054 149. 1.00 0.01 1327000300055 150. 0.638 0.004 1327000300056 151. 0.408 0.012 1327000300057 152. 0.212 0.006 1327000300058 154. 0.0563 0.0009 1327000300059 ENDDATA 33 0 1327000300060 ENDSUBENT 59 0 1327000399999 SUBENT 13270004 20201203 14751327000400001 BIB 7 16 1327000400002 REACTION (92-U-235(N,F)MASS,CHN,FY,,SPA) 1327000400003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000400004 INC-SPECT Thermal reactor neutron spectrum. 1327000400005 SAMPLE Four standard burnup capsule 1327000400006 CIPP-6-4-1, contained 115.2+-0.1 mg of enriched U3O8, 1327000400007 CIPP-6-6-2, contained 81.94+-0.10 mg of enriched U3O8, 1327000400008 CIPP-6-2-2, contained 61.2+-0.1 mg of enriched U3O8, 1327000400009 CIPP-6-5-3, contained 122.0 mg of enriched U3O8. 1327000400010 (92-U-234,ENR=0.004677) 1327000400011 (92-U-235,ENR=0.991633) 1327000400012 (92-U-236,ENR=0.000603) 1327000400013 (92-U-238,ENR=0.003087) 1327000400014 METHOD (CHSEP) Radiometric yield. 1327000400015 STATUS (TABLE) Tab. II (p. 194) in Nucl.Sc.Eng.,42,191,1970. 1327000400016 HISTORY (20201203A) OG. SAMPLE and STATUS updated. 1327000400017 ELEM/MASS,CUM replaced by MASS,CHN. 1327000400018 ENDBIB 16 0 1327000400019 COMMON 1 3 1327000400020 EN-DUMMY 1327000400021 EV 1327000400022 0.0253 1327000400023 ENDCOMMON 3 0 1327000400024 DATA 3 2 1327000400025 MASS DATA DATA-ERR 1327000400026 NO-DIM PC/FIS PC/FIS 1327000400027 125. 0.0291 0.0033 1327000400028 141. 5.50 0.34 1327000400029 ENDDATA 4 0 1327000400030 ENDSUBENT 29 0 1327000499999 SUBENT 13270005 20201203 14751327000500001 BIB 8 24 1327000500002 REACTION (92-U-235(N,F)MASS,CHN,FY,,SPA) 1327000500003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000500004 INC-SPECT Thermal reactor neutron spectrum. 1327000500005 SAMPLE Four standard burnup capsule 1327000500006 CIPP-6-4-1, contained 115.2+-0.1 mg of enriched U3O8, 1327000500007 CIPP-6-6-2, contained 81.94+-0.10 mg of enriched U3O8, 1327000500008 CIPP-6-2-2, contained 61.2+-0.1 mg of enriched U3O8, 1327000500009 CIPP-6-5-3, contained 122.0 mg of enriched U3O8. 1327000500010 (92-U-234,ENR=0.004677) 1327000500011 (92-U-235,ENR=0.991633) 1327000500012 (92-U-236,ENR=0.000603) 1327000500013 (92-U-238,ENR=0.003087) 1327000500014 METHOD (ASEP) 1327000500015 CRITIQUE By author: large correction for natural Zr 1327000500016 contamination required as a result of firing 1327000500017 quartzware in zirconia lined furnace, Maeck, ENICO- 1327000500018 1065 (1980). 1327000500019 STATUS (TABLE) Tab. II (p. 194) in Nucl.Sc.Eng.,42,191,1970. 1327000500020 Tab. II contains mass chain data that are split here 1327000500021 into ELEM/MASS. 1327000500022 HISTORY (20180411A) Superseded numerical data restored for 1327000500023 archival purposes 1327000500024 (20201203A) OG. SAMPLE and STATUS updated. Deleted 1327000500025 heading ELEMENT, changed RECTION SF5 to CHN. 1327000500026 ENDBIB 24 0 1327000500027 COMMON 1 3 1327000500028 EN-DUMMY 1327000500029 EV 1327000500030 0.0253 1327000500031 ENDCOMMON 3 0 1327000500032 DATA 3 5 1327000500033 MASS DATA DATA-ERR 1327000500034 NO-DIM PC/FIS PC/FIS 1327000500035 91. 5.90 0.03 1327000500036 92. 5.95 0.03 1327000500037 93. 6.34 0.04 1327000500038 94. 6.41 0.04 1327000500039 96. 6.23 0.04 1327000500040 ENDDATA 7 0 1327000500041 ENDSUBENT 40 0 1327000599999 SUBENT 13270006 20201203 14751327000600001 BIB 9 13 1327000600002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1327000600003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000600004 INC-SPECT Thermal reactor neutron spectrum. 1327000600005 SAMPLE Fuel plates 1327000600006 No. 128-26, contained 1.58 g of U235 of U3 08, 1327000600007 No. 129-69, contained 1.59 g of U235 of U Al3, 1327000600008 No. 134-4, contained 1.60 g of U235 of U Al2. 1327000600009 (92-U-235,ENR=0.93) 1327000600010 METHOD (ASEP) 1327000600011 MONITOR (92-U-235(N,F)60-ND-148,CUM,FY,,SPA) 1327000600012 FLAG (1.) Includes 85Rb 1327000600013 STATUS (TABLE) Tab. IV (p. 195) in Nucl.Sc.Eng.,42,191,1970. 1327000600014 HISTORY (20201203U) OG. SAMPLE and STATUS updated. 1327000600015 ENDBIB 13 0 1327000600016 COMMON 3 3 1327000600017 EN-DUMMY MONIT MONIT-ERR 1327000600018 EV PC/FIS PC/FIS 1327000600019 0.0253 1.69 0.01 1327000600020 ENDCOMMON 3 0 1327000600021 DATA 5 4 1327000600022 ELEMENT MASS DATA DATA-ERR FLAG 1327000600023 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 1327000600024 36. 83. 0.526 0.008 1327000600025 36. 84. 1.00 0.01 1327000600026 36. 85. 1.32 0.01 1. 1327000600027 36. 86. 1.94 0.02 1327000600028 ENDDATA 6 0 1327000600029 ENDSUBENT 28 0 1327000699999 SUBENT 13270007 20201203 14751327000700001 BIB 9 27 1327000700002 REACTION (94-PU-239(N,F)MASS,CHN,FY,,SPA) Calculated by the 1327000700003 normalization technique 1327000700004 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000700005 INC-SPECT Thermal reactor neutron spectrum. 1327000700006 SAMPLE Three standard burnup capsule 1327000700007 CIPP-6-2-5, contained 48.9 mg of enriched Pu3O8, 1327000700008 CIPP-6-2-6, contained 56.2 mg of enriched Pu3O8, 1327000700009 CIPP-6-5-5, contained 95.0 mg of enriched Pu3O8. 1327000700010 (94-PU-239,ENR=0.99181) 1327000700011 METHOD (ASEP) 1327000700012 MONITOR (94-PU-239(N,F)60-ND-148,CUM,FY,,SPA) 1327000700013 ANALYSIS The fission yields were calculated based on a 100% 1327000700014 normalization of the relative fission yields in the 1327000700015 heavy mass peak. Over 80% of the yields in the heavy 1327000700016 mass peak had been experimentally measured to about 1327000700017 1% relative uncertainty. Relative yields in mass region1327000700018 117-159 were calculated for three capsules and these 1327000700019 values then were weighted as the inverse variance to 1327000700020 obtain the average. The estimated relative yields that 1327000700021 were assigned a relative uncertainty of +-20% were 1327000700022 taken from the compilation of Meek and Rider, 1327000700023 APED-5398-A,General Electric Company (1968). 1327000700024 STATUS (TABLE) Tab. IX (p. 200) in Nucl.Sc.Eng.,42,191,1970. 1327000700025 (DEP,13270022) 1327000700026 HISTORY (20180417A) BP: Updated 84Kr error. 1327000700027 (20201204A) OG. SAMPLE and STATUS updated. 1327000700028 ELEM/MASS,CUM replaced by MASS,CHN. 1327000700029 ENDBIB 27 0 1327000700030 COMMON 3 3 1327000700031 EN-DUMMY MONIT MONIT-ERR 1327000700032 EV PC/FIS PC/FIS 1327000700033 0.0253 1.70 0.03 1327000700034 ENDCOMMON 3 0 1327000700035 DATA 3 12 1327000700036 MASS DATA DATA-ERR 1327000700037 NO-DIM PC/FIS PC/FIS 1327000700038 83. 0.301 0.030 1327000700039 84. 0.487 0.010 1327000700040 85. 0.574 0.011 1327000700041 86. 0.770 0.016 1327000700042 87. 1.00 0.02 1327000700043 88. 1.35 0.03 1327000700044 90. 2.09 0.04 1327000700045 91. 2.52 0.04 1327000700046 92. 3.02 0.05 1327000700047 93. 3.95 0.07 1327000700048 94. 4.50 0.08 1327000700049 96. 5.12 0.09 1327000700050 ENDDATA 14 0 1327000700051 ENDSUBENT 50 0 1327000799999 SUBENT 13270008 20201203 14751327000800001 BIB 9 19 1327000800002 REACTION (94-PU-239(N,F)MASS,CHN,FY,,SPA) Calculated by the 1327000800003 normalization technique 1327000800004 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000800005 INC-SPECT Thermal reactor neutron spectrum. 1327000800006 SAMPLE Three standard burnup capsule 1327000800007 CIPP-6-2-5, contained 48.9 mg of enriched Pu3O8, 1327000800008 CIPP-6-2-6, contained 56.2 mg of enriched Pu3O8, 1327000800009 CIPP-6-5-5, contained 95.0 mg of enriched Pu3O8. 1327000800010 (94-PU-239,ENR=0.99181) 1327000800011 METHOD (ASEP) 1327000800012 ANALYSIS Measured relative to 148Nd. Estimated relative yields 1327000800013 for 118-130 = 3.74+-0.75, 153 = 0.214+-0.043, 1327000800014 155-160 = 0.285+-0.057. Heavy mass peak summed to 1327000800015 equal 100%. 1327000800016 FLAG (2.) Data in error, Mack, et al., ICP-1092 (1976). 1327000800017 STATUS (TABLE) Tab. IX (p. 200) in Nucl.Sc.Eng.,42,191,1970. 1327000800018 (DEP,13270022) 1327000800019 HISTORY (20201204A) OG. SAMPLE and STATUS updated. 1327000800020 ELEM/MASS,CUM replaced by MASS,CHN. 1327000800021 ENDBIB 19 0 1327000800022 COMMON 1 3 1327000800023 EN-DUMMY 1327000800024 EV 1327000800025 0.0253 1327000800026 ENDCOMMON 3 0 1327000800027 DATA 4 19 1327000800028 MASS DATA DATA-ERR FLAG 1327000800029 NO-DIM PC/FIS PC/FIS NO-DIM 1327000800030 131. 3.60 0.09 2. 1327000800031 132. 5.09 0.12 2. 1327000800032 133. 7.18 0.15 1327000800033 134. 7.20 0.17 2. 1327000800034 137. 6.74 0.14 1327000800035 138. 5.40 0.11 2. 1327000800036 140. 5.61 0.12 1327000800037 142. 5.04 0.11 1327000800038 143. 4.48 0.10 1327000800039 144. 3.78 0.08 1327000800040 145. 3.03 0.06 1327000800041 146. 2.49 0.05 1327000800042 147. 2.15 0.08 1327000800043 148. 1.70 .03 2. 1327000800044 149. 1.24 0.03 1327000800045 150. 0.965 0.020 1327000800046 151. 0.811 0.044 1327000800047 152. 0.581 0.031 1327000800048 154. 0.270 0.006 1327000800049 ENDDATA 21 0 1327000800050 ENDSUBENT 49 0 1327000899999 SUBENT 13270009 20201203 14751327000900001 BIB 9 18 1327000900002 REACTION (94-PU-239(N,F)MASS,CHN,FY,,SPA) 1327000900003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327000900004 INC-SPECT Thermal reactor neutron spectrum. 1327000900005 SAMPLE Three standard burnup capsule 1327000900006 CIPP-6-2-5, contained 48.9 mg of enriched Pu3O8, 1327000900007 CIPP-6-2-6, contained 56.2 mg of enriched Pu3O8, 1327000900008 CIPP-6-5-5, contained 95.0 mg of enriched Pu3O8. 1327000900009 (94-PU-239,ENR=0.99181) 1327000900010 METHOD (ASEP,CHSEP) 1327000900011 MONITOR (94-PU-239(N,F)55-CS-137,CUM,FY,,SPA) 1327000900012 ANALYSIS To obtain the fission yields of 101Ru, 102Ru, and 1327000900013 104Ru, the atom ratios of 101Ru/106Ru, 102Ru/106Ru, 1327000900014 and 104Ru/106Ru were multiplied by the previously 1327000900015 determined 106Ru fission yield. 1327000900016 STATUS (TABLE) Tab. IX (p. 200) in Nucl.Sc.Eng.,42,191,1970. 1327000900017 HISTORY (20201204U) OG. SAMPLE and STATUS updated. 1327000900018 ELEM/MASS,CUM replaced by MASS,CHN. Data for A=125 1327000900019 removed into Sub021. ANALYSIS added. 1327000900020 ENDBIB 18 0 1327000900021 COMMON 3 3 1327000900022 EN-DUMMY MONIT MONIT-ERR 1327000900023 EV PC/FIS PC/FIS 1327000900024 0.0253 6.74 0.14 1327000900025 ENDCOMMON 3 0 1327000900026 DATA 3 4 1327000900027 MASS DATA DATA-ERR 1327000900028 NO-DIM PC/FIS PC/FIS 1327000900029 101. 6.50 0.28 1327000900030 102. 6.65 0.29 1327000900031 104. 6.61 0.29 1327000900032 106. 4.55 0.19 1327000900033 ENDDATA 6 0 1327000900034 ENDSUBENT 33 0 1327000999999 SUBENT 13270010 20201203 14751327001000001 BIB 9 19 1327001000002 REACTION (94-PU-239(N,F)MASS,CHN,FY,,SPA) 1327001000003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327001000004 INC-SPECT Thermal reactor neutron spectrum. 1327001000005 SAMPLE Two series of samples. Each series consisted of 1327001000006 individual quartzencapsulated samples of 233U (8 mg 1327001000007 as U3O8) , 235U (4 mg as U3O8), 239Pu (3 mg as PuO2), 1327001000008 and 241Pu (1.5 mg as PuO2) . 1327001000009 METHOD (FPGAM) Activities measured relative to 91(m)Y, 1327001000010 140La, 140Ba, and 143Ce. 1327001000011 ANALYSIS The fission yield of the mass chain was calculated by 1327001000012 ratioing the activity ratio of two selected 1327001000013 photopeaks from the plutonium sample with the 1327001000014 activity ratio of the same two photopeaks from the 1327001000015 233U or 235U sample. 1327001000016 MONITOR (92-U-233(N,F)ELEM/MASS,CUM,FY,,SPA) 1327001000017 (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1327001000018 STATUS (TABLE) Tab. IX (p. 200) in Nucl.Sc.Eng.,42,191,1970. 1327001000019 HISTORY (20201204A) OG. SAMPLE, ANALYSIS and STATUS updated. 1327001000020 ELEM/MASS,CUM replaced by MASS,CHN. 1327001000021 ENDBIB 19 0 1327001000022 COMMON 1 3 1327001000023 EN-DUMMY 1327001000024 EV 1327001000025 0.0253 1327001000026 ENDCOMMON 3 0 1327001000027 DATA 3 2 1327001000028 MASS DATA DATA-ERR 1327001000029 NO-DIM PC/FIS PC/FIS 1327001000030 95. 4.86 0.11 1327001000031 97. 5.64 0.16 1327001000032 ENDDATA 4 0 1327001000033 ENDSUBENT 32 0 1327001099999 SUBENT 13270011 20201203 14751327001100001 BIB 9 21 1327001100002 REACTION (94-PU-241(N,F)MASS,CHN,FY,,SPA) Calculated by the 1327001100003 normalization technique 1327001100004 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327001100005 INC-SPECT Thermal reactor neutron spectrum. 1327001100006 SAMPLE Two standard burnup capsule 1327001100007 CIPP-6-4-6, contained 77.0 mg of enriched Pu3O8, 1327001100008 CIPP-6-5-6, contained 76.0 mg of enriched Pu3O8. 1327001100009 (94-PU-241,ENR=0.95473) 1327001100010 METHOD (ASEP) 1327001100011 MONITOR (94-PU-241(N,F)60-ND-148,CUM,FY,,SPA) 1327001100012 ANALYSIS Measured relative to 148Nd. Relative yields in mass 1327001100013 region 120-130 estimated using data of Farrar, et 1327001100014 al., Can.J.Chem., 42, 2063 (1964); For mass yields 1327001100015 135, 136, 139,141, 151, 153, and 155-164, estimated 1327001100016 by combining data of Farrar with data from this 1327001100017 experiment on adjacent mass chains. Heavy mass peak 1327001100018 summed to equal 100%. 1327001100019 STATUS (TABLE) Tab. XI (p. 201) in Nucl.Sc.Eng.,42,191,1970. 1327001100020 (DEP,13270023) 1327001100021 HISTORY (20201204A) OG. SAMPLE and STATUS updated. 1327001100022 ELEM/MASS,CUM replaced by MASS,CHN. 1327001100023 ENDBIB 21 0 1327001100024 COMMON 3 3 1327001100025 EN-DUMMY MONIT MONIT-ERR 1327001100026 EV PC/FIS PC/FIS 1327001100027 0.0253 1.89 0.05 1327001100028 ENDCOMMON 3 0 1327001100029 DATA 3 30 1327001100030 MASS DATA DATA-ERR 1327001100031 NO-DIM PC/FIS PC/FIS 1327001100032 83. 0.200 0.006 1327001100033 84. 0.353 0.010 1327001100034 85. 0.387 0.010 1327001100035 86. 0.601 0.018 1327001100036 87. 0.741 0.020 1327001100037 88. 0.954 0.025 1327001100038 90. 1.53 0.04 1327001100039 91. 1.82 0.05 1327001100040 92. 2.23 0.06 1327001100041 93. 2.90 0.08 1327001100042 94. 3.33 0.09 1327001100043 96. 4.33 0.12 1327001100044 131. 3.15 0.09 1327001100045 132. 4.64 0.13 1327001100046 133. 6.71 0.18 1327001100047 134. 8.06 0.22 1327001100048 137. 6.60 0.17 1327001100049 138. 6.37 0.17 1327001100050 140. 5.86 0.16 1327001100051 142. 4.80 0.13 1327001100052 143. 4.48 0.12 1327001100053 144. 4.13 0.11 1327001100054 145. 3.19 0.08 1327001100055 146. 2.68 0.07 1327001100056 147. 2.22 0.06 1327001100057 148. 1.89 0.05 1327001100058 149. 1.43 0.04 1327001100059 150. 1.16 0.03 1327001100060 152. 0.725 0.034 1327001100061 154. 0.370 0.010 1327001100062 ENDDATA 32 0 1327001100063 ENDSUBENT 62 0 1327001199999 SUBENT 13270012 20201203 14751327001200001 BIB 9 21 1327001200002 REACTION (94-PU-241(N,F)MASS,CHN,FY,,SPA) Calculated by the 1327001200003 normalization technique 1327001200004 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327001200005 INC-SPECT Thermal reactor neutron spectrum. 1327001200006 SAMPLE Two standard burnup capsule 1327001200007 CIPP-6-4-6, contained 77.0 mg of enriched Pu3O8, 1327001200008 CIPP-6-5-6, contained 76.0 mg of enriched Pu3O8. 1327001200009 (94-PU-241,ENR=0.95473) 1327001200010 METHOD (ASEP) 1327001200011 MONITOR (94-PU-241(N,F)60-ND-148,CUM,FY,,SPA) 1327001200012 ANALYSIS Measured relative to 148Nd. Relative yields in mass 1327001200013 region 120-130 estimated using data of Farrar, et 1327001200014 al., Can.J.Chem., 42, 2063 (1964); For mass yields 1327001200015 135, 136, 139,141, 151, 153, and 155-164, estimated 1327001200016 by combining data of Farrar with data from this 1327001200017 experiment on adjacent mass chains. Heavy mass peak 1327001200018 summed to equal 100%. 1327001200019 STATUS (TABLE) Tab. XI (p. 201) in Nucl.Sc.Eng.,42,191,1970. 1327001200020 (DEP,13270023) 1327001200021 HISTORY (20201204A) OG. SAMPLE and STATUS updated. 1327001200022 ELEM/MASS,CUM replaced by MASS,CHN. 1327001200023 ENDBIB 21 0 1327001200024 COMMON 3 3 1327001200025 EN-DUMMY MONIT MONIT-ERR 1327001200026 EV PC/FIS PC/FIS 1327001200027 0.0253 1.89 0.05 1327001200028 ENDCOMMON 3 0 1327001200029 DATA 3 18 1327001200030 MASS DATA DATA-ERR 1327001200031 NO-DIM PC/FIS PC/FIS 1327001200032 131. 3.15 0.09 1327001200033 132. 4.64 0.13 1327001200034 133. 6.71 0.18 1327001200035 134. 8.06 0.22 1327001200036 137. 6.60 0.17 1327001200037 138. 6.37 0.17 1327001200038 140. 5.86 0.16 1327001200039 142. 4.80 0.13 1327001200040 143. 4.48 0.12 1327001200041 144. 4.13 0.11 1327001200042 145. 3.19 0.08 1327001200043 146. 2.68 0.07 1327001200044 147. 2.22 0.06 1327001200045 148. 1.89 0.05 1327001200046 149. 1.43 0.04 1327001200047 150. 1.16 0.03 1327001200048 152. 0.725 0.034 1327001200049 154. 0.370 0.010 1327001200050 ENDDATA 20 0 1327001200051 ENDSUBENT 50 0 1327001299999 SUBENT 13270013 20201203 14751327001300001 BIB 9 16 1327001300002 REACTION (94-PU-241(N,F)MASS,CHN,FY,,SPA) 1327001300003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327001300004 INC-SPECT Thermal reactor neutron spectrum. 1327001300005 SAMPLE Two standard burnup capsule 1327001300006 CIPP-6-4-6, contained 77.0 mg of enriched Pu3O8, 1327001300007 CIPP-6-5-6, contained 76.0 mg of enriched Pu3O8. 1327001300008 (94-PU-241,ENR=0.95473) 1327001300009 METHOD (ASEP,CHSEP) 1327001300010 MONITOR (94-PU-241(N,F)55-CS-137,CUM,FY,,SPA) 1327001300011 ANALYSIS To obtain the fission yields of 101Ru, 102Ru, and 1327001300012 104Ru, the atom ratios of 101Ru/106Ru, 102Ru/106Ru, 1327001300013 and 104Ru/106Ru were multiplied by the previously 1327001300014 determined 106Ru fission yield. 1327001300015 STATUS (TABLE) Tab. XI (p. 201) in Nucl.Sc.Eng.,42,191,1970. 1327001300016 HISTORY (20201204A) OG. SAMPLE and STATUS updated. ANALYSIS 1327001300017 added. ELEM/MASS,CUM replaced by MASS,CHN. 1327001300018 ENDBIB 16 0 1327001300019 COMMON 3 3 1327001300020 EN-DUMMY MONIT MONIT-ERR 1327001300021 EV PC/FIS PC/FIS 1327001300022 0.0253 6.60 0.17 1327001300023 ENDCOMMON 3 0 1327001300024 DATA 3 4 1327001300025 MASS DATA DATA-ERR 1327001300026 NO-DIM PC/FIS PC/FIS 1327001300027 101. 5.94 0.26 1327001300028 102. 6.32 0.28 1327001300029 104. 6.80 0.30 1327001300030 106. 6.08 0.25 1327001300031 ENDDATA 6 0 1327001300032 ENDSUBENT 31 0 1327001399999 SUBENT 13270014 20201203 14751327001400001 BIB 9 20 1327001400002 REACTION (94-PU-241(N,F)MASS,CHN,FY,,SPA) 1327001400003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327001400004 INC-SPECT Thermal reactor neutron spectrum. 1327001400005 SAMPLE Two standard burnup capsule 1327001400006 CIPP-6-4-6, contained 77.0 mg of enriched Pu3O8, 1327001400007 CIPP-6-5-6, contained 76.0 mg of enriched Pu3O8. 1327001400008 (94-PU-241,ENR=0.95473) 1327001400009 METHOD (FPGAM) Activities measured relative to 91(m)Y, 1327001400010 140La, 140Ba, and 143Ce. 1327001400011 ANALYSIS The fission yield of the mass chain was calculated by 1327001400012 ratioing the activity ratio of two selected 1327001400013 photopeaks from the plutonium sample with the 1327001400014 activity ratio of the same two photopeaks from the 1327001400015 233U or 235U sample. 1327001400016 MONITOR (92-U-233(N,F)ELEM/MASS,CUM,FY,,SPA) 1327001400017 (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1327001400018 STATUS (TABLE) Tab. XI (p. 201) in Nucl.Sc.Eng.,42,191,1970. 1327001400019 (DEP,13270023) 1327001400020 HISTORY (20201204A) OG. SAMPLE, ANALYSIS and STATUS updated. 1327001400021 ELEM/MASS,CUM replaced by MASS,CHN. 1327001400022 ENDBIB 20 0 1327001400023 COMMON 1 3 1327001400024 EN-DUMMY 1327001400025 EV 1327001400026 0.0253 1327001400027 ENDCOMMON 3 0 1327001400028 DATA 3 3 1327001400029 MASS DATA DATA-ERR 1327001400030 NO-DIM PC/FIS PC/FIS 1327001400031 95. 3.92 0.09 1327001400032 97. 4.76 0.14 1327001400033 99. 6.17 0.16 1327001400034 ENDDATA 5 0 1327001400035 ENDSUBENT 34 0 1327001499999 SUBENT 13270015 20201203 14751327001500001 BIB 8 12 1327001500002 REACTION (94-PU-241(N,F)MASS,CHN,FY,,SPA) 1327001500003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327001500004 INC-SPECT Thermal reactor neutron spectrum. 1327001500005 SAMPLE Two standard burnup capsule 1327001500006 CIPP-6-4-6, contained 77.0 mg of enriched Pu3O8, 1327001500007 CIPP-6-5-6, contained 76.0 mg of enriched Pu3O8. 1327001500008 (94-PU-241,ENR=0.95473) 1327001500009 METHOD (CHSEP) 1327001500010 MONITOR (94-PU-241(N,F)55-CS-137,CUM,FY,,SPA) 1327001500011 STATUS (TABLE) Tab. XI (p. 201) in Nucl.Sc.Eng.,42,191,1970. 1327001500012 HISTORY (20201204A) OG. SAMPLE and STATUS updated. 1327001500013 ELEM/MASS,CUM replaced by MASS,CHN. 1327001500014 ENDBIB 12 0 1327001500015 COMMON 3 3 1327001500016 EN-DUMMY MONIT MONIT-ERR 1327001500017 EV PC/FIS PC/FIS 1327001500018 0.0253 6.60 0.17 1327001500019 ENDCOMMON 3 0 1327001500020 DATA 3 1 1327001500021 MASS DATA DATA-ERR 1327001500022 NO-DIM PC/FIS PC/FIS 1327001500023 125. 0.0416 0.0050 1327001500024 ENDDATA 3 0 1327001500025 ENDSUBENT 24 0 1327001599999 SUBENT 13270016 20201203 14751327001600001 BIB 9 12 1327001600002 REACTION (92-U-235(N,F)MASS,CHN,FY,,FST) 1327001600003 FACILITY (REAC,1USAINL) Experimental Breeder Reactor I (EBR-I). 1327001600004 INC-SPECT Fast reactor neutron spectrum. 1327001600005 SAMPLE Irradiated fuel pins 1327001600006 METHOD (ASEP) 1327001600007 MONITOR (92-U-235(N,F)60-ND-148,CUM,FY,,FST) 1327001600008 CORRECTION 85Rb yield corrected by authors from 1.49 to 1.38 1327001600009 upon recalculation of Kr-85 decay. 1327001600010 STATUS (TABLE) Tab. XIII (p. 202) in Nucl.Sc.Eng.,42,191,1970.1327001600011 (DEP,13270024) 1327001600012 HISTORY (20201203A) OG. STATUS updated. ELEM/MASS,CUM replaced 1327001600013 by MASS,CHN. 1327001600014 ENDBIB 12 0 1327001600015 COMMON 3 3 1327001600016 EN-MEAN MONIT MONIT-ERR 1327001600017 MEV PC/FIS PC/FIS 1327001600018 0.5 1.75 0.03 1327001600019 ENDCOMMON 3 0 1327001600020 DATA 3 19 1327001600021 MASS DATA DATA-ERR 1327001600022 NO-DIM PC/FIS PC/FIS 1327001600023 83. 0.614 0.018 1327001600024 84. 1.07 0.01 1327001600025 85. 1.38 0.03 1327001600026 86. 1.93 0.05 1327001600027 87. 2.66 0.06 1327001600028 88. 3.63 0.08 1327001600029 90. 5.48 0.16 1327001600030 95. 6.47 0.13 1327001600031 97. 6.13 0.12 1327001600032 98. 6.04 0.12 1327001600033 100. 6.35 0.13 1327001600034 101. 5.46 0.11 1327001600035 102. 4.65 0.10 1327001600036 104. 2.35 0.05 1327001600037 111. 0.0456 0.0009 1327001600038 112. 0.0391 0.0008 1327001600039 113. 0.0342 0.0007 1327001600040 114. 0.0342 0.0007 1327001600041 116. 0.0359 0.0007 1327001600042 ENDDATA 21 0 1327001600043 ENDSUBENT 42 0 1327001699999 SUBENT 13270017 20201203 14751327001700001 BIB 9 16 1327001700002 REACTION (92-U-235(N,F)MASS,CHN,FY,,FST) 1327001700003 FACILITY (REAC,1USAINL) Experimental Breeder Reactor I (EBR-I). 1327001700004 INC-SPECT Fast reactor neutron spectrum. 1327001700005 SAMPLE Irradiated fuel pins 1327001700006 METHOD (ASEP) 1327001700007 ANALYSIS Absolute yields for heavy mass peak calculated by 1327001700008 normalizing the sum of 118-157 yields to 100%. 1327001700009 estimated yields assumed for 118-124 = 0.273+-0.055, 1327001700010 126-130 = 4.066+-0.813, 139 = 6.38+-1.28, 1327001700011 141 = 5.69+-1.14, 147 = 2.19+-0.44, 1327001700012 153 = 0.175+-0.035, 155-157 = 0.118+-0.027. 1327001700013 COMMENT 150Nd reduced from 0.832 to 0.767 upon reanalysis 1327001700014 by authors. 1327001700015 STATUS (TABLE) Tab. XIII (p. 202) in Nucl.Sc.Eng.,42,191,1970.1327001700016 HISTORY (20201203A) OG. STATUS updated. ELEM/MASS,CUM replaced 1327001700017 by MASS,CHN. 1327001700018 ENDBIB 16 0 1327001700019 COMMON 1 3 1327001700020 EN-MEAN 1327001700021 MEV 1327001700022 0.5 1327001700023 ENDCOMMON 3 0 1327001700024 DATA 3 20 1327001700025 MASS DATA DATA-ERR 1327001700026 NO-DIM PC/FIS PC/FIS 1327001700027 131. 3.15 0.08 1327001700028 132. 4.45 0.12 1327001700029 133. 6.69 0.13 1327001700030 134. 7.09 0.43 1327001700031 135. 6.54 0.13 1327001700032 136. 5.93 0.16 1327001700033 137. 6.20 0.16 1327001700034 138. 6.60 0.12 1327001700035 140. 6.21 0.11 1327001700036 142. 5.82 0.11 1327001700037 143. 5.80 0.12 1327001700038 144. 5.26 0.11 1327001700039 145. 3.85 0.08 1327001700040 146. 3.00 0.06 1327001700041 148. 1.75 0.03 1327001700042 149. 1.09 0.02 1327001700043 150. 0.767 0.030 1327001700044 151. 0.438 0.009 1327001700045 152. 0.309 0.006 1327001700046 154. 0.098 0.003 1327001700047 ENDDATA 22 0 1327001700048 ENDSUBENT 47 0 1327001799999 SUBENT 13270018 20201203 14751327001800001 BIB 8 9 1327001800002 REACTION (92-U-235(N,F)MASS,CHN,FY,,FST) 1327001800003 FACILITY (REAC,1USAINL) Experimental Breeder Reactor I (EBR-I). 1327001800004 INC-SPECT Fast reactor neutron spectrum. 1327001800005 SAMPLE Irradiated fuel pins 1327001800006 METHOD (CHSEP,GSPEC) 1327001800007 MONITOR (92-U-235(N,F)60-ND-148,CUM,FY,,FST) 1327001800008 STATUS (TABLE) Tab. XIII (p. 202) in Nucl.Sc.Eng.,42,191,1970.1327001800009 HISTORY (20201203A) OG. STATUS updated. ELEM/MASS,CUM replaced 1327001800010 by MASS,CHN. 1327001800011 ENDBIB 9 0 1327001800012 COMMON 3 3 1327001800013 EN-MEAN MONIT MONIT-ERR 1327001800014 MEV PC/FIS PC/FIS 1327001800015 0.5 1.75 0.03 1327001800016 ENDCOMMON 3 0 1327001800017 DATA 3 1 1327001800018 MASS DATA DATA-ERR 1327001800019 NO-DIM PC/FIS PC/FIS 1327001800020 125. 0.0727 0.0090 1327001800021 ENDDATA 3 0 1327001800022 ENDSUBENT 21 0 1327001899999 SUBENT 13270019 20201203 14751327001900001 BIB 8 9 1327001900002 REACTION (94-PU-239(N,F)MASS,CHN,FY,,FST) 1327001900003 FACILITY (REAC,1USAINL) Experimental Breeder Reactor I (EBR-I). 1327001900004 INC-SPECT Fast reactor neutron spectrum. 1327001900005 SAMPLE Irradiated fuel pins 1327001900006 METHOD (ASEP) 1327001900007 MONITOR (94-PU-239(N,F)60-ND-148,CUM,FY,,FST) 1327001900008 STATUS (TABLE) Tab. XV (p. 203) in Nucl.Sc.Eng.,42,191,1970. 1327001900009 HISTORY (20201203A) OG. STATUS updated. ELEM/MASS,CUM replaced 1327001900010 by MASS,CHN. 1327001900011 ENDBIB 9 0 1327001900012 COMMON 3 3 1327001900013 EN-MEAN MONIT MONIT-ERR 1327001900014 MEV PC/FIS PC/FIS 1327001900015 0.5 1.73 0.03 1327001900016 ENDCOMMON 3 0 1327001900017 DATA 3 24 1327001900018 MASS DATA DATA-ERR 1327001900019 NO-DIM PC/FIS PC/FIS 1327001900020 83. 0.366 .008 1327001900021 84. 0.559 .013 1327001900022 85. 0.672 0.012 1327001900023 86. 0.882 .020 1327001900024 87. 1.16 0.02 1327001900025 88. 1.44 0.03 1327001900026 90. 2.24 0.05 1327001900027 91. 2.58 0.05 1327001900028 92. 3.13 0.06 1327001900029 93. 3.91 0.07 1327001900030 94. 4.39 0.08 1327001900031 95. 4.78 0.09 1327001900032 96. 5.11 0.10 1327001900033 97. 5.47 0.10 1327001900034 98. 5.81 0.11 1327001900035 100. 6.76 0.13 1327001900036 101. 6.88 0.13 1327001900037 102. 6.97 0.13 1327001900038 104. 6.77 0.12 1327001900039 111. 0.376 0.007 1327001900040 112. 0.207 0.004 1327001900041 113. 0.133 0.002 1327001900042 114. 0.0987 0.0019 1327001900043 116. 0.0636 0.0013 1327001900044 ENDDATA 26 0 1327001900045 ENDSUBENT 44 0 1327001999999 SUBENT 13270020 20201203 14751327002000001 BIB 8 14 1327002000002 REACTION (94-PU-239(N,F)MASS,CHN,FY,,FST) 1327002000003 FACILITY (REAC,1USAINL) Experimental Breeder Reactor I (EBR-I). 1327002000004 INC-SPECT Fast reactor neutron spectrum. 1327002000005 SAMPLE Irradiated fuel pins 1327002000006 METHOD (ASEP) 1327002000007 ANALYSIS Absolute yields for heavy mass peak calculated by 1327002000008 normalizing the sum of 119-160 yields to 100%. 1327002000009 estimated yields assumed for 119-124 = 0.470+-0.094, 1327002000010 126-130 = 4.49+-1.00, 139 = 5.88+-1.18, 1327002000011 141 = 5.28+-1.06, 147 = 2.18+-0.44, 1327002000012 153 = 0.484+-0.097, 155-160 = 0.695+-0.139. 1327002000013 STATUS (TABLE) Tab. XV (p. 203) in Nucl.Sc.Eng.,42,191,1970. 1327002000014 HISTORY (20201203A) OG. STATUS updated. ELEM/MASS,CUM replaced 1327002000015 by MASS,CHN. 1327002000016 ENDBIB 14 0 1327002000017 COMMON 1 3 1327002000018 EN-MEAN 1327002000019 MEV 1327002000020 0.5 1327002000021 ENDCOMMON 3 0 1327002000022 DATA 3 21 1327002000023 MASS DATA DATA-ERR 1327002000024 NO-DIM PC/FIS PC/FIS 1327002000025 125. 0.194 0.023 1327002000026 131. 4.06 .08 1327002000027 132. 5.42 0.11 1327002000028 133. 6.91 0.12 1327002000029 134. 7.35 .15 1327002000030 135. 7.54 0.13 1327002000031 136. 6.92 .14 1327002000032 137. 6.58 0.11 1327002000033 138. 4.97 0.09 1327002000034 140. 5.59 0.10 1327002000035 142. 4.95 0.09 1327002000036 143. 4.30 0.08 1327002000037 144. 3.68 0.07 1327002000038 145. 3.04 0.05 1327002000039 146. 2.52 0.04 1327002000040 148. 1.73 0.03 1327002000041 149. 1.36 0.02 1327002000042 150. 1.06 0.02 1327002000043 151. 0.839 0.015 1327002000044 152. 0.683 0.012 1327002000045 154. 0.324 0.006 1327002000046 ENDDATA 23 0 1327002000047 ENDSUBENT 46 0 1327002099999 SUBENT 13270021 20210205 14751327002100001 BIB 8 8 1327002100002 REACTION (94-PU-239(N,F)MASS,CHN,FY,,SPA) 1327002100003 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR) 1327002100004 INC-SPECT Thermal reactor neutron spectrum 1327002100005 SAMPLE Two 239Pu samples 1327002100006 METHOD (CHSEP) 1327002100007 MONITOR (94-PU-239(N,F)55-CS-137,CUM,FY,,SPA) 1327002100008 STATUS (TABLE) Tab. IX (p. 200) in Nucl.Sc.Eng.,42,191,1970. 1327002100009 HISTORY (20210205C) OG. Data for A=125 removed from Sub009. 1327002100010 ENDBIB 8 0 1327002100011 COMMON 3 3 1327002100012 EN-DUMMY MONIT MONIT-ERR 1327002100013 EV PC/FIS PC/FIS 1327002100014 0.0253 6.74 0.14 1327002100015 ENDCOMMON 3 0 1327002100016 DATA 3 1 1327002100017 MASS DATA DATA-ERR 1327002100018 NO-DIM PC/FIS PC/FIS 1327002100019 125. 0.116 0.014 1327002100020 ENDDATA 3 0 1327002100021 ENDSUBENT 20 0 1327002199999 SUBENT 13270022 20210205 14751327002200001 BIB 9 19 1327002200002 REACTION ((94-PU-239(N,F)ELEM/MASS,CUM,FY,,SPA)/ 1327002200003 (94-PU-239(N,F)60-ND-148,CUM,FY,,SPA)) 1327002200004 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327002200005 INC-SPECT Thermal reactor neutron spectrum. 1327002200006 SAMPLE Three standard burnup capsule 1327002200007 CIPP-6-2-5, contained 48.9 mg of enriched Pu3O8, 1327002200008 CIPP-6-2-6, contained 56.2 mg of enriched Pu3O8, 1327002200009 CIPP-6-5-5, contained 95.0 mg of enriched Pu3O8. 1327002200010 (94-PU-239,ENR=0.99181) 1327002200011 METHOD (ASEP) 1327002200012 ANALYSIS Measured relative to 148Nd. Estimated relative yields 1327002200013 for 118-130 = 3.74+-0.75, for 139 = 3.37+-0.67, 1327002200014 for 141 = 3.42+-0.68, for 153 = 0.214+-0.043, 1327002200015 for 155-160 = 0.285+-0.057. 1327002200016 FLAG (1.) Includes 85Rb 1327002200017 (2.) Includes 144Nd 1327002200018 (3.) Includes 136Xe 1327002200019 STATUS (TABLE) Tab. VII (p. 199) in Nucl.Sc.Eng.,42,191,1970. 1327002200020 HISTORY (20210205C) OG. 1327002200021 ENDBIB 19 0 1327002200022 COMMON 1 3 1327002200023 EN-DUMMY 1327002200024 EV 1327002200025 0.0253 1327002200026 ENDCOMMON 3 0 1327002200027 DATA 5 31 1327002200028 ELEMENT MASS DATA DATA-ERR FLAG 1327002200029 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1327002200030 36. 83. 0.1772 0.0021 1327002200031 36. 84. 0.2870 0.0034 1327002200032 36. 85. 0.3383 0.0020 1. 1327002200033 36. 86. 0.4532 0.0054 1327002200034 37. 87. 0.5885 0.0030 1327002200035 38. 88. 0.7935 0.0069 1327002200036 38. 90. 1.233 0.007 1327002200037 40. 91. 1.482 0.005 1327002200038 40. 92. 1.777 0.006 1327002200039 40. 93. 2.324 0.008 1327002200040 40. 94. 2.651 0.010 1327002200041 40. 96. 3.015 0.011 1327002200042 54. 131. 2.122 0.025 1327002200043 54. 132. 3.002 0.036 1327002200044 54. 134. 4.239 0.050 1327002200045 54. 135. 8.190 0.097 3. 1327002200046 55. 133. 4.229 0.016 1327002200047 55. 137. 3.970 0.014 1327002200048 56. 138. 3.181 0.012 1327002200049 58. 140. 3.305 0.013 1327002200050 58. 142. 2.971 0.010 1327002200051 58. 144. 2.226 0.012 2. 1327002200052 60. 143. 2.642 0.014 1327002200053 60. 145. 1.787 0.007 1327002200054 60. 146. 1.469 0.006 1327002200055 60. 150. 0.5686 0.0021 1327002200056 62. 147. 1.264 0.038 1327002200057 62. 149. 0.7306 0.0030 1327002200058 62. 151. 0.4776 0.0240 1327002200059 62. 152. 0.3423 0.0172 1327002200060 62. 154. 0.1591 0.0010 1327002200061 ENDDATA 33 0 1327002200062 ENDSUBENT 61 0 1327002299999 SUBENT 13270023 20210205 14751327002300001 BIB 9 20 1327002300002 REACTION ((94-PU-241(N,F)ELEM/MASS,CUM,FY,,SPA)/ 1327002300003 (94-PU-241(N,F)60-ND-148,CUM,FY,,SPA)) 1327002300004 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327002300005 INC-SPECT Thermal reactor neutron spectrum. 1327002300006 SAMPLE Two standard burnup capsule 1327002300007 CIPP-6-4-6, contained 77.0 mg of enriched Pu3O8, 1327002300008 CIPP-6-5-6, contained 76.0 mg of enriched Pu3O8. 1327002300009 (94-PU-241,ENR=0.95473) 1327002300010 METHOD (ASEP) 1327002300011 ANALYSIS Measured relative to 148Nd. Relative yields in mass 1327002300012 region 120-130 estimated using data of Farrar, et 1327002300013 al., Can.J.Chem., 42, 2063 (1964); For mass yields 1327002300014 135, 136, 139,141, 151, 153, and 155-164, estimated 1327002300015 by combining data of Farrar with data from this 1327002300016 experiment on adjacent mass chains. Heavy mass peak 1327002300017 summed to equal 100%. 1327002300018 FLAG (1.) Includes 85Rb 1327002300019 (2.) Includes 144Nd 1327002300020 STATUS (TABLE) Tab. X (p. 200) in Nucl.Sc.Eng.,42,191,1970. 1327002300021 HISTORY (20210205C) OG. 1327002300022 ENDBIB 20 0 1327002300023 COMMON 1 3 1327002300024 EN-DUMMY 1327002300025 EV 1327002300026 0.0253 1327002300027 ENDCOMMON 3 0 1327002300028 DATA 5 29 1327002300029 ELEMENT MASS DATA DATA-ERR FLAG 1327002300030 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1327002300031 36. 83. 0.106 0.002 1327002300032 36. 84. 0.187 0.003 1327002300033 36. 85. 0.205 0.001 1. 1327002300034 36. 86. 0.318 0.005 1327002300035 37. 87. 0.392 0.002 1327002300036 38. 88. 0.505 0.003 1327002300037 38. 90. 0.810 0.003 1327002300038 40. 91. 0.962 0.005 1327002300039 40. 92. 1.180 0.005 1327002300040 40. 93. 1.535 0.007 1327002300041 40. 94. 1.764 0.008 1327002300042 40. 96. 2.293 0.010 1327002300043 54. 131. 1.670 0.015 1327002300044 54. 132. 2.640 0.022 1327002300045 54. 134. 4.272 0.038 1327002300046 55. 133. 3.555 0.014 1327002300047 55. 137. 3.496 0.014 1327002300048 56. 138. 3.378 0.013 1327002300049 58. 140. 3.106 0.013 1327002300050 58. 142. 2.542 0.009 1327002300051 58. 144. 2.187 0.010 2. 1327002300052 60. 143. 2.374 0.011 1327002300053 60. 145. 1.689 0.007 1327002300054 60. 146. 1.418 0.006 1327002300055 60. 150. 0.614 0.003 1327002300056 62. 147. 1.174 0.006 1327002300057 62. 149. 0.760 0.003 1327002300058 62. 152. 0.384 0.015 1327002300059 62. 154. 0.196 0.002 1327002300060 ENDDATA 31 0 1327002300061 ENDSUBENT 60 0 1327002399999 SUBENT 13270024 20210426 14751327002400001 BIB 8 14 1327002400002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,FST)/ 1327002400003 (92-U-235(N,F)60-ND-148,CUM,FY,,FST)) 1327002400004 FACILITY (REAC,1USAINL) Experimental Breeder Reactor I (EBR-I). 1327002400005 INC-SPECT Fast reactor neutron spectrum. 1327002400006 SAMPLE Irradiated fuel pins 1327002400007 METHOD (ASEP) Deternination for isotopes of the elements of 1327002400008 Ba, Cd, Ce, Cs, Mo, Nd, Rb, Ru, Sm, Sr, Zr. 1327002400009 Kr and Xe were determined by a combination of vapor 1327002400010 phase chromatography and mass spectromrtry. 1327002400011 (GSPEC) Deternination for Sb-125 1327002400012 FLAG (1.) Includes 85Rb. 1327002400013 (2.) Includes 144Nd 1327002400014 STATUS (TABLE) Tab. XII (p. 201) in Nucl.Sc.Eng.,42,191,1970. 1327002400015 HISTORY (20210206C) OG. 1327002400016 ENDBIB 14 0 1327002400017 COMMON 1 3 1327002400018 EN-MEAN 1327002400019 MEV 1327002400020 0.5 1327002400021 ENDCOMMON 3 0 1327002400022 DATA 5 39 1327002400023 ELEMENT MASS DATA DATA-ERR FLAG 1327002400024 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1327002400025 36. 83. 0.3510 0.0077 1327002400026 36. 84. 0.6114 0.0134 1327002400027 36. 85. 0.8522 0.0120 1. 1327002400028 36. 86. 1.101 0.024 1327002400029 37. 87. 1.516 0.015 1327002400030 38. 88. 2.070 0.022 1327002400031 38. 90. 3.126 0.067 1327002400032 42. 95. 3.697 0.035 1327002400033 42. 97. 3.503 0.033 1327002400034 42. 98. 3.451 0.034 1327002400035 42. 100. 3.631 0.037 1327002400036 44. 101. 3.114 0.030 1327002400037 44. 102. 2.655 0.026 1327002400038 44. 104. 1.341 0.014 1327002400039 48. 111. 0.0260 0.0002 1327002400040 48. 112. 0.0223 0.0002 1327002400041 48. 113. 0.0195 0.0002 1327002400042 48. 114. 0.0195 0.0002 1327002400043 48. 116. 0.0205 0.0002 1327002400044 51. 125. 0.0415 0.0050 1327002400045 54. 131. 1.796 0.039 1327002400046 54. 132. 2.540 0.056 1327002400047 54. 134. 4.047 0.089 1327002400048 54. 136. 3.382 0.074 1327002400049 55. 133. 3.815 0.044 1327002400050 55. 135. 3.735 0.043 1327002400051 55. 137. 3.536 0.074 1327002400052 56. 138. 3.769 0.036 1327002400053 58. 140. 3.544 0.032 1327002400054 58. 142. 3.320 0.030 1327002400055 58. 144. 3.002 0.042 2. 1327002400056 60. 143. 3.313 0.047 1327002400057 60. 145. 2.199 0.030 1327002400058 60. 146. 1.713 0.023 1327002400059 60. 150. 0.4748 0.0139 1327002400060 62. 149. 0.6235 0.0066 1327002400061 62. 151. 0.2502 0.0029 1327002400062 62. 152. 0.1765 0.0016 1327002400063 62. 154. 0.0560 0.0005 1327002400064 ENDDATA 41 0 1327002400065 ENDSUBENT 64 0 1327002499999 SUBENT 13270025 20210426 14751327002500001 BIB 9 33 1327002500002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) Calculated by the 1327002500003 normalization technique 1327002500004 FACILITY (REAC,1USAINL) Materials Test Reactor (MTR). 1327002500005 INC-SPECT Thermal reactor neutron spectrum. 1327002500006 SAMPLE Four standard burnup capsule 1327002500007 CIPP-6-4-1, contained 115.2+-0.1 mg of enriched U3O8, 1327002500008 CIPP-6-6-2, contained 81.94+-0.10 mg of enriched U3O8, 1327002500009 CIPP-6-2-2, contained 61.2+-0.1 mg of enriched U3O8, 1327002500010 CIPP-6-5-3, contained 122.0 mg of enriched U3O8. 1327002500011 (92-U-234,ENR=0.004677) 1327002500012 (92-U-235,ENR=0.991633) 1327002500013 (92-U-236,ENR=0.000603) 1327002500014 (92-U-238,ENR=0.003087) 1327002500015 MONITOR (92-U-235(N,F)60-ND-148,CUM,FY,,SPA) 1327002500016 ANALYSIS The fission yields were calculated based on a 100% 1327002500017 normalization of the relative fission yields in the 1327002500018 heavy mass peak. Over 80% of the yields in the heavy 1327002500019 mass peak had been experimentally measured to about 1327002500020 1% relative uncertainty. Relative yields in mass region1327002500021 117-159 were calculated for three capsules and these 1327002500022 values then were weighted as the inverse variance to 1327002500023 obtain the average. The estimated relative yields that 1327002500024 were assigned a relative uncertainty of +-20% were 1327002500025 taken from the compilation of Meek and Rider, 1327002500026 APED-5398-A,General Electric Company (1968). 1327002500027 FLAG (1.) Includes 85Rb 1327002500028 (2.) Includes 144Nd 1327002500029 STATUS (TABLE) Tab. V (p. 196) in Nucl.Sc.Eng.,42,191,1970. 1327002500030 (COREL,13270003) 1327002500031 (COREL,13270004) 1327002500032 (COREL,13270005) 1327002500033 (COREL,13270006) 1327002500034 HISTORY (20210207C) OG. 1327002500035 ENDBIB 33 0 1327002500036 COMMON 3 3 1327002500037 EN-DUMMY MONIT MONIT-ERR 1327002500038 EV PC/FIS PC/FIS 1327002500039 0.0253 1.69 0.01 1327002500040 ENDCOMMON 3 0 1327002500041 DATA 5 36 1327002500042 ELEMENT MASS DATA DATA-ERR FLAG 1327002500043 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 1327002500044 36. 83. 0.529 0.012 1327002500045 36. 84. 1.01 0.022 1327002500046 36. 85. 1.33 0.02 1. 1327002500047 36. 86. 1.95 0.04 1327002500048 37. 87. 2.57 0.05 1327002500049 38. 88. 3.61 0.06 1327002500050 38. 90. 5.93 0.11 1327002500051 42. 95. 6.51 0.12 1327002500052 42. 97. 5.92 0.11 1327002500053 42. 98. 5.83 0.10 1327002500054 42. 100. 6.30 0.11 1327002500055 43. 99. 6.24 0.12 1327002500056 44. 101. 5.08 0.09 1327002500057 44. 102. 4.21 0.08 1327002500058 44. 104. 1.83 0.03 1327002500059 44. 106. 0.389 0.008 1327002500060 54. 131. 2.86 0.07 1327002500061 54. 132. 4.27 0.10 1327002500062 54. 134. 7.73 0.18 1327002500063 55. 133. 6.76 0.12 1327002500064 55. 137. 6.32 0.11 1327002500065 56. 138. 6.83 0.12 1327002500066 58. 140. 6.35 0.11 1327002500067 58. 141. 5.53 0.35 1327002500068 58. 142. 5.90 0.11 1327002500069 58. 144. 5.45 0.10 2. 1327002500070 60. 143. 5.92 0.11 1327002500071 60. 145. 3.89 0.07 1327002500072 60. 146. 2.97 0.05 1327002500073 60. 148. 1.70 0.03 1327002500074 60. 150. 0.640 0.012 1327002500075 62. 147. 2.14 0.05 1327002500076 62. 149. 1.01 0.02 1327002500077 62. 151. 0.409 0.014 1327002500078 62. 152. 0.213 0.007 1327002500079 62. 154. 0.0564 0.0011 1327002500080 ENDDATA 38 0 1327002500081 ENDSUBENT 80 0 1327002599999 ENDENTRY 25 0 1327099999999