ENTRY 13205 20161205 14251320500000001 SUBENT 13205001 20161205 14251320500100001 BIB 11 26 1320500100002 TITLE Accurate nuclear fuel burnup analysis, sixteenth 1320500100003 quarterly progress report 1320500100004 AUTHOR (B.F.Rider,C.P.Ruiz,J.P.Peterson Jr,F.R.Smith) 1320500100005 REFERENCE (P,GEAP-5060,196512) 1320500100006 INSTITUTE (1USAGEV) 1320500100007 FACILITY (REAC,1USAMTR) 1320500100008 SAMPLE (92-U-234,ENR=0.004677) U(3)O(8) sample. 1320500100009 (92-U-235,ENR=0.991633) 1320500100010 (92-U-236,ENR=0.000603) 1320500100011 (92-U-238,ENR=0.003087) 1320500100012 INC-SPECT Materials Testing Reactor (MTR) at an unperturbed 1320500100013 flux of 6 x 10**13 neutrons/cm2-sec (nvt=2.4 x 10**20).1320500100014 METHOD (ASEP) Am aluminum capsule (CPP-6-6-1) prepared at 1320500100015 Philips Petroleum Company which contain 85.2 mg of 1320500100016 U3O8 irradiated for three cycles in the MTR. The 1320500100017 cadmium ratio for cobalt for the position in which 1320500100018 the capsule was irradiated was 15. The capsule was 1320500100019 dissolved in the acid mixture of 6M HCl - 1.6M HNO3. 1320500100020 The number of fissions in the irradiated capsule was 1320500100021 determined from the difference in the weight of total 1320500100022 uranium before and after irradiation. 1320500100023 ERR-ANALYS (DATA-ERR) Data uncertainty is standard deviation. 1320500100024 STATUS (RIDER) Reference 65RID1 1320500100025 HISTORY (19890519C) VM 1320500100026 (20161205A) BP: Updated to new date formats,lower case.1320500100027 Corrected the entry. Added subentries 3,4. 1320500100028 ENDBIB 26 0 1320500100029 NOCOMMON 0 0 1320500100030 ENDSUBENT 29 0 1320500199999 SUBENT 13205002 20161205 14251320500200001 BIB 4 8 1320500200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1320500200003 HISTORY (20161205A) BP: removed Cs data as not original. 1320500200004 Original MONITOR information was removed and REACTION 1320500200005 SF8 was changed. 1320500200006 CORRECTION Small corrections were applied for neutron capture 1320500200007 effects and, and in the case of Nd-144, for Ce-144 1320500200008 holdup. 1320500200009 STATUS (TABLE) Table 5, page 7. 1320500200010 ENDBIB 8 0 1320500200011 COMMON 1 3 1320500200012 EN-DUMMY 1320500200013 EV 1320500200014 0.0253 1320500200015 ENDCOMMON 3 0 1320500200016 DATA 4 6 1320500200017 ELEMENT MASS DATA DATA-ERR 1320500200018 NO-DIM NO-DIM PC/FIS PC/FIS 1320500200019 60. 143. 5.98 7.5E-02 1320500200020 60. 144. 5.29 6.6E-02 1320500200021 60. 145. 3.91 4.9E-02 1320500200022 60. 146. 2.95 3.7E-02 1320500200023 60. 148. 1.67 2.3E-02 1320500200024 60. 150. 0.633 7.E-03 1320500200025 ENDDATA 8 0 1320500200026 ENDSUBENT 25 0 1320500299999 SUBENT 13205003 20161205 14251320500300001 BIB 3 3 1320500300002 REACTION (92-U-235(N,ABS),,ALF,,SPA) 1320500300003 HISTORY (20161205C) 1320500300004 STATUS (TABLE) Table 2, page 5. 1320500300005 ENDBIB 3 0 1320500300006 COMMON 1 3 1320500300007 EN-DUMMY 1320500300008 EV 1320500300009 0.0253 1320500300010 ENDCOMMON 3 0 1320500300011 DATA 2 1 1320500300012 DATA DATA-ERR 1320500300013 NO-DIM NO-DIM 1320500300014 0.176 0.002 1320500300015 ENDDATA 3 0 1320500300016 ENDSUBENT 15 0 1320500399999 SUBENT 13205004 20161205 14251320500400001 BIB 4 6 1320500400002 REACTION (92-U-235(N,ABS),,ALF) 1320500400003 ANALYSIS Spectrum average data corrected to 2200 m/sec flux 1320500400004 at 20 degC. 1320500400005 HISTORY (20161205C) 1320500400006 STATUS (TABLE) Table 2, page 5. 1320500400007 (DEP,13205003) 1320500400008 ENDBIB 6 0 1320500400009 COMMON 1 3 1320500400010 EN 1320500400011 EV 1320500400012 0.0253 1320500400013 ENDCOMMON 3 0 1320500400014 DATA 2 1 1320500400015 DATA DATA-ERR 1320500400016 NO-DIM NO-DIM 1320500400017 0.171 0.002 1320500400018 ENDDATA 3 0 1320500400019 ENDSUBENT 18 0 1320500499999 ENDENTRY 4 0 1320599999999