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