ENTRY 12771 20200713 14711277100000001 SUBENT 12771001 20200713 14711277100100001 BIB 10 46 1277100100002 TITLE The yield of short-lived gamma-ray emitting nuclides 1277100100003 from fast- and thermal-neutron fission 1277100100004 AUTHOR (R.P.Larsen,N.D.Dudey,R.R.Heinrich,R.D.Oldham, 1277100100005 R.J.Armani,R.J.Popek,R.Gold) 1277100100006 INSTITUTE (1USAANL) 1277100100007 REFERENCE (J,NSE,54,263,1974) 1277100100008 #doi:10.13182/NSE74-A23417 1277100100009 #NSR: 1974LA17 1277100100010 (J,ANS,15,483,1972) 235U, 238U, and 239Pu fast fission 1277100100011 yields of short-lived gamma-active nuclides 1277100100012 #NSR: 1972LAZL 1277100100013 (P,ANL-7887,32,1971) Data for 235U, 238U, and 239Pu are1277100100014 the same as in the main reference. The 237Np fission 1277100100015 yield of 140Ba included in 13271002. 1277100100016 (P,ANL-7979,7,1973) Data for 235U, and 239Pu are almost1277100100017 the same as in the main reference. 1277100100018 (J,ANS,14,370,1971) 235U, and 239Pu thermal fission 1277100100019 yields of 95Zr, 103Ru, 131I, presented as relative to 1277100100020 140Ba, are very similar to relative data, calculated 1277100100021 using the main ref. 1277100100022 METHOD (CHSEP,GSPEC) 1277100100023 DETECTOR (GELI) 1277100100024 SAMPLE The fissionable materials were all of very high 1277100100025 isotopic (99.999+%); the amounts ranged from 10 to 1277100100026 50 ng for 235U and 239Pu and from 0.2 to 2 mu-g for 1277100100027 238U. 1277100100028 DECAY-DATA ((1.)40-ZR-95,65.0D,DG,724.,0.445,DG,757.,0.55) 1277100100029 ((1.)41-NB-95-G,35.0D,DG,766.,0.98) 1277100100030 ((2.)40-ZR-97,0.701D,DG,745.,0.94) 1277100100031 ((2.)41-NB-97-G,0.050D,DG,658.,0.99) 1277100100032 ((3.)42-MO-99,2.78D,B-) 1277100100033 ((4.)44-RU-103,40.0D,DG,497.,0.88) 1277100100034 ((5.)53-I-131,8.05D,DG,364.,0.82) 1277100100035 ((6.)56-BA-140,12.80D) 1277100100036 ((6.)57-LA-140,1.67D,DG,1597.,0.96) 1277100100037 STATUS (APRVD) R.R.Heinrich, 85/10/14. 1277100100038 HISTORY (19850808C) 1277100100039 (19891106A) Bib, reaction update. 1277100100040 (20181130U) OS. ERR-ANALYS upgraded, minor BIB 1277100100041 correction, converted to lower and upper case 1277100100042 (20190418U) OG. REF. (J,ANS,15,483,1972) was added 1277100100043 #NSR were added 1277100100044 (20200713U) OG. #doi, SAMPLE added. 1277100100045 3-rd REF (P,ANL-7887,32,1971) added. 1277100100046 4-th REF (P,ANL-7979,7,1973) added. 1277100100047 5-th REF (J,ANS,14,370,1971) added. 1277100100048 ENDBIB 46 0 1277100100049 NOCOMMON 0 0 1277100100050 ENDSUBENT 49 0 1277100199999 SUBENT 12771002 20181203 14451277100200001 BIB 6 17 1277100200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FST) 1277100200003 FACILITY (REAC,1USAANL) ZPR-3 1277100200004 INC-SPECT Fast reactor spectrum. 1277100200005 Average of samples at 3 locations with average 1277100200006 fission energies of 446, 442, 293 keV. 1277100200007 MONITOR (92-U-235(N,F)55-CS-137,CUM,FY,,FST) 1277100200008 ERR-ANALYS (DATA-ERR) The following sources of errors are 1277100200009 included: 1277100200010 . the precision of the mean of the gamma counts per 1277100200011 gram of fissionable mateial 1277100200012 . the detector calibration 1277100200013 . the nuclear constants of the fission products 1277100200014 (photon-to disintegration ratios and half-lives) 1277100200015 . the mass absorptions of the gamma rays by the foils 1277100200016 . the weights of the fissionable materials in the 1277100200017 foils 1277100200018 STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table II 1277100200019 ENDBIB 17 0 1277100200020 COMMON 1 3 1277100200021 EN-DUMMY 1277100200022 MEV 1277100200023 0.4 1277100200024 ENDCOMMON 3 0 1277100200025 DATA 5 6 1277100200026 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 1277100200027 NO-DIM NO-DIM PC/FIS PER-CENT NO-DIM 1277100200028 40. 95. 6.41 3.5 1. 1277100200029 40. 97. 5.53 3.0 2. 1277100200030 42. 99. 5.70 3.0 3. 1277100200031 44. 103. 3.29 3.1 4. 1277100200032 53. 131. 3.25 3.1 5. 1277100200033 56. 140. 5.67 2.9 6. 1277100200034 ENDDATA 8 0 1277100200035 ENDSUBENT 34 0 1277100299999 SUBENT 12771003 20181203 14451277100300001 BIB 6 17 1277100300002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,FST) 1277100300003 FACILITY (REAC,1USAANL) ZPR-3 1277100300004 INC-SPECT Fast reactor spectrum. 1277100300005 Average of samples at 2 locations with average 1277100300006 fission energies of 446, 442 keV. 1277100300007 MONITOR (92-U-238(N,F)55-CS-137,CUM,FY,,FST) 1277100300008 ERR-ANALYS (DATA-ERR) The following sources of errors are 1277100300009 included: 1277100300010 . the precision of the mean of the gamma counts per 1277100300011 gram of fissionable mateial 1277100300012 . the detector calibration 1277100300013 . the nuclear constants of the fission products 1277100300014 (photon-to disintegration ratios and half-lives) 1277100300015 . the mass absorptions of the gamma rays by the foils 1277100300016 . the weights of the fissionable materials in the 1277100300017 foils 1277100300018 STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table IV 1277100300019 ENDBIB 17 0 1277100300020 COMMON 1 3 1277100300021 EN-DUMMY 1277100300022 MEV 1277100300023 0.4 1277100300024 ENDCOMMON 3 0 1277100300025 DATA 5 6 1277100300026 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 1277100300027 NO-DIM NO-DIM PC/FIS PER-CENT NO-DIM 1277100300028 40. 95. 5.44 3.0 1. 1277100300029 40. 97. 5.32 3.0 2. 1277100300030 42. 99. 6.03 2.0 3. 1277100300031 44. 103. 6.29 3.5 4. 1277100300032 53. 131. 3.05 4.0 5. 1277100300033 56. 140. 5.92 3.0 6. 1277100300034 ENDDATA 8 0 1277100300035 ENDSUBENT 34 0 1277100399999 SUBENT 12771004 20181203 14451277100400001 BIB 7 20 1277100400002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,FST) 1277100400003 FACILITY (REAC,1USAANL) ZPR-3 1277100400004 INC-SPECT Fast reactor spectrum. 1277100400005 Average of samples at 2 locations with average 1277100400006 fission energies of 446, 442, 293 keV. 1277100400007 MONITOR (94-PU-239(N,F)55-CS-137,CUM,FY,,FST) 1277100400008 ERR-ANALYS (DATA-ERR) The following sources of errors are 1277100400009 included: 1277100400010 . the precision of the mean of the gamma counts per 1277100400011 gram of fissionable mateial 1277100400012 . the detector calibration 1277100400013 . the nuclear constants of the fission products 1277100400014 (photon-to disintegration ratios and half-lives) 1277100400015 . the mass absorptions of the gamma rays by the foils 1277100400016 . the weights of the fissionable materials in the 1277100400017 foils 1277100400018 FLAG (1.) Calculated from 95Zr yield and measured 97Zr/95Zr 1277100400019 thermal-neutron fission-yield ratio. The 97Zr gamma 1277100400020 was subject of interference from a 239Pu gamma 1277100400021 STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table III 1277100400022 ENDBIB 20 0 1277100400023 COMMON 1 3 1277100400024 EN-DUMMY 1277100400025 MEV 1277100400026 0.4 1277100400027 ENDCOMMON 3 0 1277100400028 DATA 6 5 1277100400029 ELEMENT MASS DATA DATA-ERR DECAY-FLAG FLAG 1277100400030 NO-DIM NO-DIM PC/FIS PER-CENT NO-DIM NO-DIM 1277100400031 40. 95. 4.77 3.5 1. 1277100400032 40. 97. 4.86 3.0 1. 1277100400033 44. 103. 7.05 3.1 4. 1277100400034 53. 131. 4.08 3.1 5. 1277100400035 56. 140. 5.25 2.9 6. 1277100400036 ENDDATA 7 0 1277100400037 ENDSUBENT 36 0 1277100499999 SUBENT 12771005 20181203 14451277100500001 BIB 5 5 1277100500002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1277100500003 FACILITY (REAC,1USAANL) Argonne thermal source reactor. 1277100500004 INC-SPECT Thermal reactor spectrum 1277100500005 MONITOR (92-U-235(N,F)55-CS-137,CUM,FY,,SPA) 1277100500006 STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table V 1277100500007 ENDBIB 5 0 1277100500008 COMMON 1 3 1277100500009 EN-DUMMY 1277100500010 EV 1277100500011 0.0253 1277100500012 ENDCOMMON 3 0 1277100500013 DATA 4 5 1277100500014 ELEMENT MASS DATA DECAY-FLAG 1277100500015 NO-DIM NO-DIM PC/FIS NO-DIM 1277100500016 40. 95. 6.53 1. 1277100500017 40. 97. 5.28 2. 1277100500018 44. 103. 2.95 4. 1277100500019 53. 131. 2.66 5. 1277100500020 56. 140. 5.81 6. 1277100500021 ENDDATA 7 0 1277100500022 ENDSUBENT 21 0 1277100599999 SUBENT 12771006 20181203 14451277100600001 BIB 5 5 1277100600002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,SPA) 1277100600003 FACILITY (REAC,1USAANL) Argonne thermal source reactor. 1277100600004 INC-SPECT Thermal reactor spectrum 1277100600005 MONITOR (94-PU-239(N,F)55-CS-137,CUM,FY,,SPA) 1277100600006 STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table V 1277100600007 ENDBIB 5 0 1277100600008 COMMON 1 3 1277100600009 EN-DUMMY 1277100600010 EV 1277100600011 0.0253 1277100600012 ENDCOMMON 3 0 1277100600013 DATA 4 5 1277100600014 ELEMENT MASS DATA DECAY-FLAG 1277100600015 NO-DIM NO-DIM PC/FIS NO-DIM 1277100600016 40. 95. 4.83 1. 1277100600017 40. 97. 4.98 2. 1277100600018 44. 103. 7.04 4. 1277100600019 53. 131. 3.95 5. 1277100600020 56. 140. 5.24 6. 1277100600021 ENDDATA 7 0 1277100600022 ENDSUBENT 21 0 1277100699999 ENDENTRY 6 0 1277199999999