ENTRY 10898 20201028 14741089800000001 SUBENT 10898001 20201028 14741089800100001 BIB 14 41 1089800100002 TITLE Absolute thermal fission yields for Pu-239 1089800100003 AUTHOR (W.J.Maeck,F.A.Duce,R.L.Eggleston,R.L.Tromp, 1089800100004 J.W.Meteer, W.A.Emel) 1089800100005 REFERENCE (R,ENICO-1001,1979) 1089800100006 INSTITUTE (1USAINL) 1089800100007 FACILITY (REAC,1USAINL) Engineering test reactor (etr), 1089800100008 reflector region. 1089800100009 SAMPLE (94-PU-239,ENR=0.991225) Samples of PuO(2) contained 1089800100010 in high-purity aluminum capsules. Capsules filled to 1089800100011 full depth by addition of aluminum powder. Average 1089800100012 isotopic abundance of capsules is 99.1225% Pu-239. 1089800100013 DETECTOR Mass spectrometer 1089800100014 MONITOR Sum of heavy mass peak normalized to 100%. 1089800100015 ASSUMED ENDF/B values for fission yields used in mass regions 1089800100016 119-124 and 125-130. 1089800100017 INC-SPECT Thermal reactor spectrum 1089800100018 METHOD (CHSEP) Two sets of four samples used- low burnup of 1089800100019 650 mg samples and high burnup irradiation of 40 mg 1089800100020 samples. Samples chemically analyzed and gamma-ray 1089800100021 spectrometery used to determine completeness of 1089800100022 sample dissolution. Non-gaseous fission products 1089800100023 determined by isotope dilution mass spectrometry. 1089800100024 Absolute number of fissions determined by summation 1089800100025 techniques. 1089800100026 ERR-ANALYS (DATA-ERR) Six-steps error analysis done. Procedure 1089800100027 included errors due to: 1089800100028 -uncertainty in spike concentrations 1089800100029 -random spectrometer errors 1089800100030 -Kr and Xe spike volume uncertainties 1089800100031 -uncertainty due to extraneous fissions and elemental 1089800100032 fission yields caused by Pu-241 contamination 1089800100033 -systematic uncertainty of spectrometer in isotopic 1089800100034 abundance measurements 1089800100035 STATUS (TABLE) Data were taken from the report. 1089800100036 HISTORY (19800421C) 1089800100037 (19801030U) BIB corrections. 1089800100038 (19840917A) BIB correction. 1089800100039 (20180411A) BP: updated to new date formats,lower 1089800100040 case. corrections according last EXFOR rules and dict. 1089800100041 (20201028A) BP: Corrected 135,136Xe yields in Sub. 3. 1089800100042 Added subentry 4. 1089800100043 ENDBIB 41 0 1089800100044 COMMON 1 3 1089800100045 EN-DUMMY 1089800100046 EV 1089800100047 0.0253 1089800100048 ENDCOMMON 3 0 1089800100049 ENDSUBENT 48 0 1089800199999 SUBENT 10898002 20180411 14401089800200001 BIB 2 3 1089800200002 REACTION (94-PU-239(N,F)ELEM,CUM,FY,,SPA) 1089800200003 METHOD Fission product element yield determined for each 1089800200004 sample and mean value calculated. 1089800200005 ENDBIB 3 0 1089800200006 NOCOMMON 0 0 1089800200007 DATA 3 10 1089800200008 ELEMENT DATA DATA-ERR 1089800200009 NO-DIM PC/FIS PC/FIS 1089800200010 36. 1.536 0.015 1089800200011 37. 1.579 0.018 1089800200012 38. 3.266 0.036 1089800200013 40. 18.215 0.269 1089800200014 54. 32.042 0.291 1089800200015 55. 13.688 0.145 1089800200016 56. 6.124 0.096 1089800200017 58. 9.838 0.138 1089800200018 60. 16.310 0.170 1089800200019 62. 4.783 0.057 1089800200020 ENDDATA 12 0 1089800200021 ENDSUBENT 20 0 1089800299999 SUBENT 10898003 20201028 14741089800300001 BIB 4 12 1089800300002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,SPA) 1089800300003 METHOD Data obtained by 1089800300004 -determining the isotopic composition of 1089800300005 each fission product element 1089800300006 -using isotopic composition measurements to apportion 1089800300007 the mean fission element yields 1089800300008 STATUS (DEP,10898002) Fission element yields used to obtain 1089800300009 isotopic yields 1089800300010 HISTORY (19801030A) Data corrections. 1089800300011 (20201028A) BP: Removed 135,136Xe yields because they 1089800300012 were not separated and published as a sum; originally 1089800300013 compiled in subentry 10898003 as individual yields. 1089800300014 ENDBIB 12 0 1089800300015 NOCOMMON 0 0 1089800300016 DATA 4 31 1089800300017 ELEMENT MASS DATA DATA-ERR 1089800300018 NO-DIM NO-DIM PC/FIS PC/FIS 1089800300019 36. 83. 0.296 0.003 1089800300020 36. 84. 0.477 0.005 1089800300021 36. 86. 0.763 0.008 1089800300022 37. 85. 0.575 0.007 1089800300023 37. 87. 1.004 0.012 1089800300024 38. 88. 1.283 0.015 1089800300025 38. 90. 1.983 0.022 1089800300026 40. 91. 2.446 0.038 1089800300027 40. 92. 2.994 0.046 1089800300028 40. 93. 3.761 0.056 1089800300029 40. 94. 4.231 0.063 1089800300030 40. 96. 4.783 0.073 1089800300031 54. 131. 3.938 0.044 1089800300032 54. 132. 5.447 0.053 1089800300033 54. 134. 7.703 0.070 1089800300034 55. 133. 7.059 0.077 1089800300035 55. 134. 6.629 0.072 1089800300036 56. 138. 6.124 0.096 1089800300037 58. 140. 5.079 0.074 1089800300038 58. 142. 4.759 0.070 1089800300039 60. 143. 4.435 0.050 1089800300040 60. 144. 3.774 0.041 1089800300041 60. 145. 3.022 0.033 1089800300042 60. 146. 2.467 0.027 1089800300043 60. 148. 1.647 0.020 1089800300044 60. 150. 0.966 0.013 1089800300045 62. 147. 1.994 0.025 1089800300046 62. 149. 1.217 0.015 1089800300047 62. 151. 0.729 0.015 1089800300048 62. 152. 0.594 0.015 1089800300049 62. 154. 0.250 0.004 1089800300050 ENDDATA 33 0 1089800300051 ENDSUBENT 50 0 1089800399999 SUBENT 10898004 20201028 14741089800400001 BIB 5 12 1089800400002 REACTION ((94-PU-239(N,F)54-XE-135,CUM,FY,,SPA)+ 1089800400003 (94-PU-239(N,F)54-XE-136,CUM,FY,,SPA)) 1089800400004 METHOD Data obtained by 1089800400005 -determining the isotopic composition of 1089800400006 each fission product element 1089800400007 -using isotopic composition measurements to apportion 1089800400008 the mean fission element yields 1089800400009 STATUS (DEP,10898002) Fission element yields used to obtain 1089800400010 isotopic yields 1089800400011 COMMENT Compiler's comment: In the experiment 135Xe and 136Xe 1089800400012 yields were not separated and published as a sum. 1089800400013 HISTORY (20201028A) BP 1089800400014 ENDBIB 12 0 1089800400015 NOCOMMON 0 0 1089800400016 DATA 2 1 1089800400017 DATA DATA-ERR 1089800400018 PC/FIS PC/FIS 1089800400019 14.954 0.143 1089800400020 ENDDATA 3 0 1089800400021 ENDSUBENT 20 0 1089800499999 ENDENTRY 4 0 1089899999999