ENTRY 13581 20210915 14911358100000001 SUBENT 13581001 20210915 14911358100100001 BIB 12 56 1358100100002 TITLE Ratio of Asymmetric to Symmetric Fission of U233 as a 1358100100003 Function of Neutron Energy 1358100100004 AUTHOR (R.B.Regier,W.H.Burgus,R.L.Tromp) 1358100100005 REFERENCE (J,PR,113,1589,1959) 1358100100006 #doi:10.1103/PhysRev.113.1589 1358100100007 INSTITUTE (1USAMTR) 1358100100008 FACILITY (REAC,1USAMTR) MTR crystal spectrometer. 1358100100009 INC-SPECT Irradiations were made in the VG-23 facility of the 1358100100010 Materials Testing Reactor (MTR) where the thermal 1358100100011 flux is 2*10**10 n/cm2 sec and the cadmium ratio for 1358100100012 indium is 800. 1358100100013 SAMPLE Two U3O8 samples, isotopic composition. Thermal 1358100100014 irradiations done on 233U as uranyl nitrate. 1358100100015 1) 232U (< 0.002%) 1358100100016 (92-U-233,ENR=0.9835) 1358100100017 (92-U-234,ENR=0.0126) 1358100100018 (92-U-235,ENR=0.0021) 1358100100019 (92-U-238,ENR=0.0018) 1358100100020 2) 232U (<0.02%) 1358100100021 (92-U-233,ENR=0.9790) 1358100100022 (92-U-234,ENR=0.0178) 1358100100023 (92-U-235,ENR=0.0005) 1358100100024 (92-U-238,ENR=0.0028) 1358100100025 METHOD (CHSEP) Two irradiations were made on the crystal 1358100100026 spectrometer with neutrons of 0.0253 ev energy, in 1358100100027 order to compare the fission product yields with 1358100100028 those obtained for thermal irradiations made in the 1358100100029 VG-23 graphite facility. No significant differences 1358100100030 were observed in the mass yield ratios obtained from 1358100100031 these two kinds of irradiations. In addition to the 1358100100032 spectrometer irradiations, a number of in-pile 1358100100033 irradiations were made in positions in the reactor 1358100100034 having appreciable epi-cadmium neutron fluxes. 1358100100035 Samples for these irradiations consisted of 0.08 mg 1358100100036 of uranium, evaporated on aluminum foil as in the 1358100100037 thermal neutron irradiations. However, they were 1358100100038 inserted in 1/8-in. i.d. cadmium tubing having a wall 1358100100039 thickness of 20 mils. In these irradiations, the 1358100100040 fission yields give the effect of all epi-cadmium 1358100100041 resonances, integrated over the flux distribution at 1358100100042 the position of irradiation. The fission products 1358100100043 Mo99, Ag111, Ag113 and Cd115 were separated from the 1358100100044 irradiated U233 to determine the ratio of asymmetric to1358100100045 symmetric fission at the various neutron energies. 1358100100046 DETECTOR (PROPC) End-window flowing methane proportional counter1358100100047 (GEMUC) 1358100100048 CORRECTION Corrected for: 1358100100049 . contributions of thermal neutrons 1358100100050 . contributions from coherently scattered neutrons 1358100100051 . background 1358100100052 ERR-ANALYS (DATA-ERR) Standard error of the mean. Does not include1358100100053 errors associated with background correction factors. 1358100100054 HISTORY (19930322C) 1358100100055 (20210915A) BP: Updated to new date formats, lower 1358100100056 case. Corrections according last EXFOR rules and 1358100100057 Dict. Updated entry, changed author name Trump->Tromp. 1358100100058 ENDBIB 56 0 1358100100059 NOCOMMON 0 0 1358100100060 ENDSUBENT 59 0 1358100199999 SUBENT 13581002 20210915 14911358100200001 BIB 4 10 1358100200002 REACTION (((92-U-233(N,F)42-MO-99,CUM,FY,,EPI)/ 1358100200003 (92-U-233(N,F)ELEM/MASS,CUM,FY,,EPI))// 1358100200004 ((92-U-235(N,F)42-MO-99,CUM,FY,,MXW)/ 1358100200005 (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW))) 1358100200006 Epi-Cd spectrum 1358100200007 RESULT (RVAL) 1358100200008 DECAY-DATA (47-AG-111-G,7.5D,B-) 1358100200009 No information given on decay data for other nuclides. 1358100200010 STATUS (TABLE) Table II, page 1592. Same as Rider reference 1358100200011 62bur1. 1358100200012 ENDBIB 10 0 1358100200013 COMMON 2 3 1358100200014 EN-MIN-NM EN-DUM-DN 1358100200015 EV EV 1358100200016 0.5 0.0253 1358100200017 ENDCOMMON 3 0 1358100200018 DATA 5 2 1358100200019 ELEMENT MASS ISOMER DATA DATA-ERR 1358100200020 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1358100200021 47. 111. 0. 1.088 0.023 1358100200022 48. 115. 0. 1.200 0.052 1358100200023 ENDDATA 4 0 1358100200024 ENDSUBENT 23 0 1358100299999 SUBENT 13581003 20210915 14911358100300001 BIB 3 7 1358100300002 REACTION (((92-U-233(N,F)42-MO-99,CUM,FY)/ 1358100300003 (92-U-233(N,F)ELEM/MASS,CUM,FY))// 1358100300004 ((92-U-235(N,F)42-MO-99,CUM,FY,,MXW)/ 1358100300005 (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW))) 1358100300006 RESULT (RVAL) 1358100300007 STATUS (TABLE) Tables I-II, pages 1591-1592. Same as Rider 1358100300008 reference 62bur1. 1358100300009 ENDBIB 7 0 1358100300010 COMMON 1 3 1358100300011 EN-DUM-DN 1358100300012 EV 1358100300013 0.0253 1358100300014 ENDCOMMON 3 0 1358100300015 DATA 6 5 1358100300016 EN-NM ELEMENT MASS ISOMER DATA DATA-ERR 1358100300017 EV NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1358100300018 1.8 47. 111. 0. 1.217 0.0381358100300019 2.3 47. 111. 0. 1.200 0.0591358100300020 2.3 48. 115. 0. 1.415 0.1031358100300021 4.7 47. 111. 0. 0.957 0.0221358100300022 4.7 48. 115. 0. 1.031 0.1681358100300023 ENDDATA 7 0 1358100300024 ENDSUBENT 23 0 1358100399999 ENDENTRY 3 0 1358199999999