ENTRY 13207 20200422 14701320700000001 SUBENT 13207001 20200422 14701320700100001 BIB 10 19 1320700100002 TITLE Fission product nuclear data obtained by use of an 1320700100003 on-line mass spectrometer 1320700100004 AUTHOR (P.L.Reeder,J.F.Wright,R.A.Anderl) 1320700100005 INSTITUTE (1USABNW) 1320700100006 REFERENCE (C,75WASH,1,401,1975) 1320700100007 (A,73ROCH,2,498,1973) Abstract, no data 1320700100008 #NSR: 1974REZS 1320700100009 (R,BNWL-SA-5243,1975) All data are the same as in the 1320700100010 main reference 1320700100011 FACILITY (REAC,1USAWAS) 1320700100012 INC-SOURCE (THCOL) 1320700100013 METHOD (ASEP) 1320700100014 CORRECTION Corrected for diffusion and radioactive decay. 1320700100015 ERR-ANALYS (DATA-ERR) No information 1320700100016 HISTORY (19891019C) 1320700100017 (20190807A) OG. 2nd reference added. Converted to lower1320700100018 case and 4-digit year. REACTION and STATUS updated in 1320700100019 Subs.2-7. #NSR was added. 1320700100020 (20200422U) OG. 3-rd reference added. 1320700100021 ENDBIB 19 0 1320700100022 COMMON 1 3 1320700100023 EN-DUMMY 1320700100024 EV 1320700100025 0.0253 1320700100026 ENDCOMMON 3 0 1320700100027 ENDSUBENT 26 0 1320700199999 SUBENT 13207002 20190422 14511320700200001 BIB 4 8 1320700200002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 1320700200003 (92-U-235(N,F)37-RB-91,CUM,FY,,MXW)) 1320700200004 ANALYSIS Diffusion time chosen such that relative 1320700200005 cumulative yield of 89Rb agrees with recommended 1320700200006 value of Meek and Rider, NEDO-12154-1 (1974) 1320700200007 STATUS (TABLE) Data from the table II in Conf.on Nucl. 1320700200008 Cross-Sect.and Techn.,Washington 1975,vol.1,p.401 1320700200009 HISTORY (20190807A) OG. REACTION ratio formalism introduced 1320700200010 ENDBIB 8 0 1320700200011 COMMON 1 3 1320700200012 ELEMENT 1320700200013 NO-DIM 1320700200014 37. 1320700200015 ENDCOMMON 3 0 1320700200016 DATA 3 7 1320700200017 MASS DATA DATA-ERR 1320700200018 NO-DIM NO-DIM NO-DIM 1320700200019 89. 0.92 0.02 1320700200020 90. 0.83 0.02 1320700200021 91. 1.00 0.02 1320700200022 92. 0.91 0.02 1320700200023 93. 0.70 0.01 1320700200024 94. 0.35 0.01 1320700200025 95. 0.15 0.01 1320700200026 ENDDATA 9 0 1320700200027 ENDSUBENT 26 0 1320700299999 SUBENT 13207003 20190422 14511320700300001 BIB 4 8 1320700300002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 1320700300003 (92-U-235(N,F)55-CS-140,CUM,FY,,MXW)) 1320700300004 ANALYSIS Diffusion time chosen such that relative 1320700300005 cumulative yield of 140Cs/141Cs agrees with recommended1320700300006 value of Meek and Rider, NEDO-12154-1 (1974) 1320700300007 STATUS (TABLE) Data from the table III in Conf.on Nucl. 1320700300008 Cross-Sect.and Techn.,Washington 1975,vol.1,p.401 1320700300009 HISTORY (20190807A) OG. REACTION ratio formalism introduced 1320700300010 ENDBIB 8 0 1320700300011 COMMON 1 3 1320700300012 ELEMENT 1320700300013 NO-DIM 1320700300014 55. 1320700300015 ENDCOMMON 3 0 1320700300016 DATA 3 5 1320700300017 MASS DATA DATA-ERR 1320700300018 NO-DIM NO-DIM NO-DIM 1320700300019 140. 1.00 0.01 1320700300020 141. 0.73 0.01 1320700300021 142. 0.42 0.01 1320700300022 143. 0.25 0.01 1320700300023 144. 0.08 0.01 1320700300024 ENDDATA 7 0 1320700300025 ENDSUBENT 24 0 1320700399999 SUBENT 13207004 20190422 14511320700400001 BIB 5 7 1320700400002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)/ 1320700400003 (92-U-235(N,F)35-BR-88,CUM,FY,,MXW)) 1320700400004 ANALYSIS Values given are average of yields at 4 temperatures 1320700400005 COMMENT Data are less precise due to low count rate 1320700400006 STATUS (TABLE) Data from the table IV in Conf.on Nucl. 1320700400007 Cross-Sect.and Techn.,Washington 1975,vol.1,p.401 1320700400008 HISTORY (20190807A) OG. REACTION ratio formalism introduced 1320700400009 ENDBIB 7 0 1320700400010 COMMON 1 3 1320700400011 ELEMENT 1320700400012 NO-DIM 1320700400013 35. 1320700400014 ENDCOMMON 3 0 1320700400015 DATA 3 8 1320700400016 MASS DATA DATA-ERR 1320700400017 NO-DIM NO-DIM NO-DIM 1320700400018 83. 0.21 0.01 1320700400019 84. 0.43 0.01 1320700400020 85. 0.62 0.01 1320700400021 86. 0.83 0.02 1320700400022 87. 0.95 0.02 1320700400023 88. 1.00 0.02 1320700400024 89. 0.72 0.04 1320700400025 90. 0.45 0.20 1320700400026 ENDDATA 10 0 1320700400027 ENDSUBENT 26 0 1320700499999 SUBENT 13207005 20190422 14511320700500001 BIB 4 6 1320700500002 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY,,MXW)/ 1320700500003 (92-U-235(N,F)37-RB-93,IND,FY,,MXW)) 1320700500004 ANALYSIS Values given are average of yields at 2 temperatures 1320700500005 STATUS (TABLE) Data from the table V in Conf.on Nucl. 1320700500006 Cross-Sect.and Techn.,Washington 1975,vol.1,p.401 1320700500007 HISTORY (20190807A) OG. REACTION ratio formalism introduced 1320700500008 ENDBIB 6 0 1320700500009 COMMON 1 3 1320700500010 ELEMENT 1320700500011 NO-DIM 1320700500012 37. 1320700500013 ENDCOMMON 3 0 1320700500014 DATA 3 11 1320700500015 MASS DATA DATA-ERR 1320700500016 NO-DIM NO-DIM NO-DIM 1320700500017 88. 0.002 0.002 1320700500018 89. 0.012 0.001 1320700500019 90. 0.10 0.01 1320700500020 91. 0.50 0.01 1320700500021 92. 0.88 0.01 1320700500022 93. 1.00 0.01 1320700500023 94. 0.56 0.01 1320700500024 95. 0.27 0.01 1320700500025 96. 0.060 0.003 1320700500026 97. 0.015 0.002 1320700500027 98. 0.001 0.002 1320700500028 ENDDATA 13 0 1320700500029 ENDSUBENT 28 0 1320700599999 SUBENT 13207006 20190422 14511320700600001 BIB 4 6 1320700600002 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY,,MXW)/ 1320700600003 (92-U-235(N,F)55-CS-141,IND,FY,,MXW)) 1320700600004 ANALYSIS Values given are average of yields for 2 measurements 1320700600005 STATUS (TABLE) Data from the table VI in Conf.on Nucl. 1320700600006 Cross-Sect.and Techn.,Washington 1975,vol.1,p.401 1320700600007 HISTORY (20190807A) OG. REACTION ratio formalism introduced 1320700600008 ENDBIB 6 0 1320700600009 COMMON 1 3 1320700600010 ELEMENT 1320700600011 NO-DIM 1320700600012 55. 1320700600013 ENDCOMMON 3 0 1320700600014 DATA 3 8 1320700600015 MASS DATA DATA-ERR 1320700600016 NO-DIM NO-DIM NO-DIM 1320700600017 139. 0.18 0.02 1320700600018 140. 0.54 0.02 1320700600019 141. 1.00 0.02 1320700600020 142. 0.77 0.02 1320700600021 143. 0.43 0.01 1320700600022 144. 0.081 0.01 1320700600023 145. 0.018 0.003 1320700600024 146. 0.006 0.002 1320700600025 ENDDATA 10 0 1320700600026 ENDSUBENT 25 0 1320700699999 SUBENT 13207007 20190422 14511320700700001 BIB 4 8 1320700700002 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY,,MXW)/ 1320700700003 (92-U-235(N,F)35-BR-88,IND,FY,,MXW)) 1320700700004 ANALYSIS Diffusion time = 61.2 sec. 1320700700005 STATUS (TABLE,PRELM) Data from the table VII in Conf.on 1320700700006 Nucl.Cross-Sect.and Techn.,Washington 1975,vol.1,p.401.1320700700007 Data are less precise due to low count rate and long 1320700700008 diffusion time. 1320700700009 HISTORY (20190807A) OG. REACTION ratio formalism introduced 1320700700010 ENDBIB 8 0 1320700700011 COMMON 1 3 1320700700012 ELEMENT 1320700700013 NO-DIM 1320700700014 35. 1320700700015 ENDCOMMON 3 0 1320700700016 DATA 3 5 1320700700017 MASS DATA DATA-ERR 1320700700018 NO-DIM NO-DIM NO-DIM 1320700700019 85. 0.001 0.040 1320700700020 86. 0.34 0.16 1320700700021 87. 1.10 0.26 1320700700022 88. 1.00 0.21 1320700700023 89. 0.79 0.21 1320700700024 ENDDATA 7 0 1320700700025 ENDSUBENT 24 0 1320700799999 ENDENTRY 7 0 1320799999999