ENTRY 14298 20190604 14521429800000001 SUBENT 14298001 20190604 14521429800100001 BIB 11 40 1429800100002 TITLE Fragment Mass and Kinetic Energy Distributions for 1429800100003 Fissioning Systems Ranging from Mass 230 to 256 1429800100004 AUTHOR (J.P.Unik,J.E.Gindler,L.E.Glendenin,K.F.Flynn, 1429800100005 A.Gorski, R.K.Sjoblom) 1429800100006 REFERENCE (C,73ROCH,2,19,1973) 1429800100007 (J,BAP,18,627(EK5),1973) Abstract, no data 1429800100008 #NSR: 1973UNZZ 1429800100009 REL-REF (O,10516001,K.F.Flynn+,J,PR/C,11,1676,1975) 1429800100010 251Cf,255Fm(n,f) data. 1429800100011 (O,10642001,J.E.Gindler+,J,PR/C,16,1483,1977) 1429800100012 254Fm(SF) data. 1429800100013 (O,13340001,K.F.Flynn+,J,JIN,38,661,1976) 1429800100014 254Es(n,f),253Es(SF) data. 1429800100015 (O,13454001,K.F.Flynn+,J,PR/C,5,1725,1972) 1429800100016 256Fm(SF) data. 1429800100017 INSTITUTE (1USAANL) 1429800100018 FACILITY (REAC,1USAANL) Argonne heavy water reactor, CP-5. 1429800100019 INC-SOURCE (REAC) CP-5 reactor neutron flux was ~2*10**13 1429800100020 neutrons cm-2 sec-1. 1429800100021 DETECTOR (GELI,PROPC) 1429800100022 METHOD (CHSEP,BSPEC) Neutron irradiations were made in the 1429800100023 large pneumatic tube (rabbit) of the Argonne heavy 1429800100024 water reactor, CP-5. After an irradiation or 1429800100025 collection period the catcher foils were either 1429800100026 counted in a standard position of a Ge(Li) gamma-ray 1429800100027 spectrometer or dissolved (in HCl or NaOH for 1429800100028 aluminum and in HClO4-HNO3 for polyethylene) in the 1429800100029 presence of carriers for the fission product 1429800100030 elements. The fission products were isolated using 1429800100031 conventional radiochemical techniques and counted in 1429800100032 a beta proportional counter with a low background. 1429800100033 Fission yields were calculated from the measure 1429800100034 activities using the appropriate Bateman equations to 1429800100035 correct for growth and decay. 1429800100036 COMMENT Compiler's comment: This publication contains an 1429800100037 extensive review of many measurements that could be 1429800100038 found in EXFOR entries 10516, 10642, 13340, 13454. 1429800100039 Only 249Cf (n,f) results were not published elsewhere. 1429800100040 HISTORY (20170807C) BP 1429800100041 (20190604U) OG. 2nd reference and #NSR added. 1429800100042 ENDBIB 40 0 1429800100043 NOCOMMON 0 0 1429800100044 ENDSUBENT 43 0 1429800199999 SUBENT 14298002 20170807 14301429800200001 BIB 3 6 1429800200002 REACTION (98-CF-249(N,F),,NU) 1429800200003 ANALYSIS Derived from the mean masses (first moments) of the 1429800200004 light and heavy mass groups (AL and AH) as nubar = 1429800200005 AF-(AL+AH), where AF is the mass of the compound 1429800200006 nucleus for the particular fissioning system. 1429800200007 STATUS (TABLE) Table III, page 31. 1429800200008 ENDBIB 6 0 1429800200009 COMMON 1 3 1429800200010 EN 1429800200011 EV 1429800200012 0.0253 1429800200013 ENDCOMMON 3 0 1429800200014 DATA 1 1 1429800200015 DATA 1429800200016 PRT/FIS 1429800200017 4.4 1429800200018 ENDDATA 3 0 1429800200019 ENDSUBENT 18 0 1429800299999 SUBENT 14298003 20170807 14301429800300001 BIB 3 3 1429800300002 REACTION (98-CF-249(N,F),,AKE,LF+HF) 1429800300003 ERR-ANALYS (DATA-ERR) Estimated relative precision. 1429800300004 STATUS (TABLE) Table I, page 20. 1429800300005 ENDBIB 3 0 1429800300006 COMMON 1 3 1429800300007 EN 1429800300008 EV 1429800300009 0.0253 1429800300010 ENDCOMMON 3 0 1429800300011 DATA 2 1 1429800300012 DATA DATA-ERR 1429800300013 MEV MEV 1429800300014 189.1 0.5 1429800300015 ENDDATA 3 0 1429800300016 ENDSUBENT 15 0 1429800399999 ENDENTRY 3 0 1429899999999