ENTRY 13204 881102 1320400000001 SUBENT 13204001 881102 1320400100001 BIB 10 13 1320400100002 INSTITUTE (1USAGEV) 1320400100003 REFERENCE (R,GEAP-4716,6409) 1320400100004 AUTHOR (B.F.RIDER,J.P.PETERSON JR,C.P.RUIZ,F.R.SMITH) 1320400100005 TITLE ACCURATE NUCLEAR FUEL BURNUP ANALYSIS, ELEVENTH 1320400100006 QUARTERLY PROGRESS REPORT 1320400100007 FACILITY (REAC,1USAMTR) 1320400100008 EXPERIMENTAL CAPSULE GEV-1, NV=2.0E13 AND NVT= 1.0E20. 1320400100009 METHOD (ASEP) 1320400100010 ASSUMED ASSUMING 300 BARNS AS A SPECTRUM AVERAGED NEUTRON 1320400100011 CROSS SECTION FOR ND-147 1320400100012 ERR-ANALYS NO INFORMATION 1320400100013 STATUS (RIDER) REFERENCE 64RID1 1320400100014 HISTORY (890519C) VM 1320400100015 ENDBIB 13 0 1320400100016 COMMON 1 3 1320400100017 EN-DUMMY 1320400100018 EV 1320400100019 0.0253 1320400100020 ENDCOMMON 3 0 1320400100021 ENDSUBENT 20 0 1320400199999 SUBENT 13204002 881102 1320400200001 BIB 1 3 1320400200002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,MXW/REL) 1320400200003 RELATIVE TO ND-148, ONLY 0.9928 OF ND-148 IS FROM 1320400200004 FISSION 1320400200005 ENDBIB 3 0 1320400200006 COMMON 2 3 1320400200007 ELEMENT MASS-NRM 1320400200008 NO-DIM NO-DIM 1320400200009 60. 148. 1320400200010 ENDCOMMON 3 0 1320400200011 DATA 3 6 1320400200012 MASS DATA DATA-ERR 1320400200013 NO-DIM NO-DIM NO-DIM 1320400200014 143. 4.631 .037 1320400200015 144. 3.710 .041 1320400200016 145. 2.660 .021 1320400200017 146. 1.977 .016 1320400200018 148. 0.9928 1320400200019 150. 0.386 .008 1320400200020 ENDDATA 8 0 1320400200021 ENDSUBENT 20 0 1320400299999 SUBENT 13204003 881102 1320400300001 BIB 2 4 1320400300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW/REL) 1320400300003 RELATIVE TO ND-148, ONLY 0.9928 OF ND-148 IS FROM 1320400300004 FISSION 1320400300005 STATUS (COREL,13205002) 1320400300006 ENDBIB 4 0 1320400300007 COMMON 2 3 1320400300008 ELEMENT MASS-NRM 1320400300009 NO-DIM NO-DIM 1320400300010 60. 148. 1320400300011 ENDCOMMON 3 0 1320400300012 DATA 3 6 1320400300013 MASS DATA DATA-ERR 1320400300014 NO-DIM NO-DIM NO-DIM 1320400300015 143. 3.571 .029 1320400300016 144. 3.194 .029 1320400300017 145. 2.330 .019 1320400300018 146. 1.758 .014 1320400300019 148. 0.9928 1320400300020 150. 0.382 .006 1320400300021 ENDDATA 8 0 1320400300022 ENDSUBENT 21 0 1320400399999 SUBENT 13204004 881102 1320400400001 BIB 1 3 1320400400002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,MXW/REL) 1320400400003 RELATIVE TO ND-148, ONLY 0.9928 OF ND-148 IS FROM 1320400400004 FISSION 1320400400005 ENDBIB 3 0 1320400400006 COMMON 2 3 1320400400007 ELEMENT MASS-NRM 1320400400008 NO-DIM NO-DIM 1320400400009 60. 148. 1320400400010 ENDCOMMON 3 0 1320400400011 DATA 3 6 1320400400012 MASS DATA DATA-ERR 1320400400013 NO-DIM NO-DIM NO-DIM 1320400400014 143. 2.713 .022 1320400400015 144. 2.282 .020 1320400400016 145. 1.834 .015 1320400400017 146. 1.492 .012 1320400400018 148. 0.9928 1320400400019 150. 0.580 .009 1320400400020 ENDDATA 8 0 1320400400021 ENDSUBENT 20 0 1320400499999 ENDENTRY 4 0 1320499999999