ENTRY 14182 20161205 14251418200000001 SUBENT 14182001 20161205 14251418200100001 BIB 9 22 1418200100002 TITLE Burnup Determination of Nuclear Fuels 1418200100003 AUTHOR (F.L.Lisman,W.J.Maeck,J.E.Rein) 1418200100004 REFERENCE (R,IN-1178,1968) 1418200100005 INSTITUTE (1USAMTR) 1418200100006 FACILITY (REAC,1USAMTR) 1418200100007 INC-SPECT Materials Testing Reactor (MTR) at an unperturbed 1418200100008 flux of 6 x 10**13 neutrons/cm2-sec (accumulated 1418200100009 nvt=1.7 x 10**20). 1418200100010 SAMPLE (92-U-235,ENR=0.991633) 1418200100011 (92-U-234,ENR=0.004677) 1418200100012 (92-U-236,ENR=0.000603) 1418200100013 (92-U-238,ENR=0.003087) Standard burnup capsule CPP-6- 1418200100014 5-3, which contained 122.0 mg of highly enriched U3O8 1418200100015 mixed with high-purity aluminum powder and welded in 1418200100016 a high-purity aluminum tube. 1418200100017 METHOD (CHSEP,BURN) The capsule was irradiated for two fuel 1418200100018 cycles (1290 Mwd)in the MTR. The cadmium ratio for 1418200100019 cobalt for this irradiation was 15. The capsule was 1418200100020 discharged from the reactor July 20, 1964, and 1418200100021 allowed to cool for about three years before 1418200100022 dissolution. 1418200100023 HISTORY (20161205C) BP 1418200100024 ENDBIB 22 0 1418200100025 NOCOMMON 0 0 1418200100026 ENDSUBENT 25 0 1418200199999 SUBENT 14182002 20161205 14251418200200001 BIB 4 10 1418200200002 REACTION (92-U-235(N,ABS),,ALF) 1418200200003 ANALYSIS Spectrum average data converted to 2200 m/sec data. 1418200200004 Assumed parameters: Temp = 40 deg-C, gf=0.9735(16), 1418200200005 sf=-0.0316, ga=0.9723(12), sa= 0.1501, r=0.031(6) 1418200200006 ERR-ANALYS (DATA-ERR) The quoted error (standard deviation) 1418200200007 0.0034 includes errors in the measured alpha, 1418200200008 epithermal parameter "r" , and Westcott's quoted 1418200200009 uncertainties for the g values. 1418200200010 STATUS (TABLE) page 7. 1418200200011 (DEP,14182007) 1418200200012 ENDBIB 10 0 1418200200013 COMMON 1 3 1418200200014 EN 1418200200015 EV 1418200200016 0.0253 1418200200017 ENDCOMMON 3 0 1418200200018 DATA 2 1 1418200200019 DATA DATA-ERR 1418200200020 NO-DIM NO-DIM 1418200200021 0.1710 0.0034 1418200200022 ENDDATA 3 0 1418200200023 ENDSUBENT 22 0 1418200299999 SUBENT 14182003 20161205 14251418200300001 BIB 4 8 1418200300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1418200300003 COMMENT Due to a power failure during recycling of the 1418200300004 krypton through the gas chromatograph, no error can 1418200300005 be assigned to the volume of krypton obtained and 1418200300006 hence to the various krypton fission yields. 1418200300007 DECAY-DATA (36-KR-85,10.76YR) 1418200300008 STATUS (TABLE) Table II page 9. 1418200300009 (SPSDD,13270006) 1418200300010 ENDBIB 8 0 1418200300011 COMMON 1 3 1418200300012 EN-DUMMY 1418200300013 EV 1418200300014 0.0253 1418200300015 ENDCOMMON 3 0 1418200300016 DATA 3 4 1418200300017 ELEMENT MASS DATA 1418200300018 NO-DIM NO-DIM PC/FIS 1418200300019 36.0 83.0 0.52900 1418200300020 36.0 84.0 0.98000 1418200300021 36.0 85.0 0.28200 1418200300022 36.0 86.0 1.86000 1418200300023 ENDDATA 6 0 1418200300024 ENDSUBENT 23 0 1418200399999 SUBENT 14182004 20161205 14251418200400001 BIB 4 8 1418200400002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1418200400003 ERR-ANALYS (DATA-ERR) The error associated with each value for 1418200400004 the xenon isotopes is the standard deviation. 1418200400005 COMMENT No attempt was made to distinguish those atoms of Xe- 1418200400006 136 resulting from Xe-135(n,gamma)Xe-136 reactions 1418200400007 and hence no Xe-136 fission yield can be reported. 1418200400008 STATUS (TABLE) Table III page 10. 1418200400009 (SPSDD,13270003) 1418200400010 ENDBIB 8 0 1418200400011 COMMON 1 3 1418200400012 EN-DUMMY 1418200400013 EV 1418200400014 0.0253 1418200400015 ENDCOMMON 3 0 1418200400016 DATA 4 3 1418200400017 ELEMENT MASS DATA DATA-ERR 1418200400018 NO-DIM NO-DIM PC/FIS PC/FIS 1418200400019 54.0 131.0 2.72 6.E-02 1418200400020 54.0 132.0 4.04 9.E-02 1418200400021 54.0 134.0 7.34 0.17 1418200400022 ENDDATA 5 0 1418200400023 ENDSUBENT 22 0 1418200499999 SUBENT 14182005 20161205 14251418200500001 BIB 6 11 1418200500002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1418200500003 REL-REF (M,,F.L.Lisman+,R,IN-1157,1968) 1418200500004 METHOD To calculate the yield of the 85 mass chain, the 1418200500005 number of determined Rb-85 atoms was added to the 1418200500006 determined atoms of 10.76-yr Kr-85. 1418200500007 ERR-ANALYS (DATA-ERR) The method of calculation and the error 1418200500008 propagation for the determined number of Rb-85 and 1418200500009 Rb-87 atoms have been previously reported. 1418200500010 DECAY-DATA (36-KR-85,10.76YR) 1418200500011 STATUS (TABLE) Table IV page 12. 1418200500012 (SPSDD,13270003) 1418200500013 ENDBIB 11 0 1418200500014 COMMON 1 3 1418200500015 EN-DUMMY 1418200500016 EV 1418200500017 0.0253 1418200500018 ENDCOMMON 3 0 1418200500019 DATA 4 2 1418200500020 ELEMENT MASS DATA DATA-ERR 1418200500021 NO-DIM NO-DIM PC/FIS PC/FIS 1418200500022 37.0 85.0 1.3000 2.E-02 1418200500023 37.0 87.0 2.5200 3.E-02 1418200500024 ENDDATA 4 0 1418200500025 ENDSUBENT 24 0 1418200599999 SUBENT 14182006 20161205 14251418200600001 BIB 5 13 1418200600002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1418200600003 METHOD (CHSEP) The absolute thermal fission yields of four 1418200600004 ruthenium isotopes, Ru-101, -102, -104, and -106, 1418200600005 were determined by isotope dilution mass 1418200600006 spectrometry. The atoms of Ru-106 also were measured 1418200600007 radiometrically. Four 1000-microl aliquots from the 1418200600008 dissolver solution were spiked with known amounts of 1418200600009 Ru-106 and carried through the separation and 1418200600010 analysis procedure. 1418200600011 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1418200600012 FLAG (1.) Radiometric. 1418200600013 STATUS (TABLE) Table V, page 14. 1418200600014 (SPSDD,13270003) 1418200600015 ENDBIB 13 0 1418200600016 COMMON 1 3 1418200600017 EN-DUMMY 1418200600018 EV 1418200600019 0.0253 1418200600020 ENDCOMMON 3 0 1418200600021 DATA 5 5 1418200600022 ELEMENT MASS DATA DATA-ERR FLAG 1418200600023 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 1418200600024 44.0 101.0 5.05 7.E-02 1418200600025 44.0 102.0 4.21 6.E-02 1418200600026 44.0 104.0 1.84 2.E-02 1418200600027 44.0 106.0 0.414 1.E-02 1418200600028 44.0 106.0 0.404 1.5E-02 1. 1418200600029 ENDDATA 7 0 1418200600030 ENDSUBENT 29 0 1418200699999 SUBENT 14182007 20161205 14251418200700001 BIB 3 6 1418200700002 REACTION (92-U-235(N,ABS),,ALF,,SPA) 1418200700003 ERR-ANALYS (DATA-ERR) The quoted error (standard deviation) 1418200700004 0.0034 includes errors in the measured alpha, 1418200700005 epithermal parameter "r" , and Westcott's quoted 1418200700006 uncertainties for the g values. 1418200700007 STATUS (TABLE) page 7. 1418200700008 ENDBIB 6 0 1418200700009 COMMON 1 3 1418200700010 EN-DUMMY 1418200700011 EV 1418200700012 0.0253 1418200700013 ENDCOMMON 3 0 1418200700014 DATA 2 1 1418200700015 DATA DATA-ERR 1418200700016 NO-DIM NO-DIM 1418200700017 0.1763 0.0022 1418200700018 ENDDATA 3 0 1418200700019 ENDSUBENT 18 0 1418200799999 ENDENTRY 7 0 1418299999999