ENTRY 20954 20120708 22322095400000001 SUBENT 20954001 20120708 22322095400100001 BIB 15 35 2095400100002 INSTITUTE (2ZZZGEL) A.J.D. 2095400100003 (2BLGMOL) G.W-p. 2095400100004 REFERENCE (C,73ROCH,2,51,197308) 2095400100005 AUTHOR (A.J.Deruytter,G.Wegener-Penning) 2095400100006 TITLE Comparison of the fission characteristics of thermal- 2095400100007 neutron-induced fission of Pu-239 and the spontaneous 2095400100008 fission of Pu-240 2095400100009 FACILITY (REAC,2BLGMOL) BR 1 graphite reactor. 2095400100010 SAMPLE .Plutonium acetate, 0.06 mg/cm2, electrosprayed on a 2095400100011 gold-coated vyns film. About 8.3% Pu-239 and 2095400100012 about 90% Pu-240. Exact isotopic composition 2095400100013 given in table 1 in 73ROCH,2,51,1973. 2095400100014 METHOD (COINC) A two-parameter correlation experiment with 2095400100015 coincident pulse heights were registered event by 2095400100016 event. 2095400100017 DETECTOR (SIBAR) Two large gold-silicon surface barrier 2095400100018 detectors. 2095400100019 ANALYSIS .The post-neutron kinetic energy values were 2095400100020 calculated with a time dependent linear equation and 2095400100021 the law of conservation of impulse was applied, 2095400100022 corrected for neutron emission. 2095400100023 PART-DET (FF ) Fission fragments. 2095400100024 COMMENT Total energy balance calculated and values given in 2095400100025 table 3 in reference. 2095400100026 STATUS (TABLE) .Data taken from Table 2 of 73ROCH,2,51,1973. 2095400100027 CORRECTION .Data corrected for neutron emission using a formula 2095400100028 obtained by Milton and Fraser. 2095400100029 ERR-ANALYS (ERR-S) .Measurements done in such a way that 2095400100030 systematic errors cancel and only statistical errors 2095400100031 have to be taken into account. 2095400100032 HISTORY (19790615C) CN. 2095400100033 (19790626E) 2095400100034 (20120708U) SD: Updated to new date formats,lower case.2095400100035 Corrections according last EXFOR rules and Dict. 2095400100036 INC-SOURCE moved to Subent 2. 2095400100037 ENDBIB 35 0 2095400100038 NOCOMMON 0 0 2095400100039 ENDSUBENT 38 0 2095400199999 SUBENT 20954002 20120708 22322095400200001 BIB 4 13 2095400200002 REACTION 1(94-PU-239(N,F),PRE,AKE,LF+HF,MXW) Pre-neutron total 2095400200003 average kinetic energy. 2095400200004 2(94-PU-239(N,F),PRE,AKE,LF,MXW) Pre-neutron average 2095400200005 kinetic energy of light fragment. 2095400200006 3(94-PU-239(N,F),PRE,AKE,HF,MXW) Pre-neutron average 2095400200007 kinetic energy of heavy fragment. 2095400200008 4(94-PU-239(N,F),PRE,AP,LF) 2095400200009 5(94-PU-239(N,F),PRE,AP,HF) 2095400200010 INC-SPECT Well thermalized neutron spectrum. 2095400200011 INC-SOURCE (THCOL) Thermal column of BR1 reactor 2095400200012 HISTORY (20120708A) SD: MISC1, MISC2 deleted. Two REACTIONs 2095400200013 were added (p.4,5). INC-SOURCE was added. 2095400200014 SF8=FF => LF+HF in REACTION code. 2095400200015 ENDBIB 13 0 2095400200016 COMMON 1 3 2095400200017 EN-DUMMY 2095400200018 EV 2095400200019 2.5300E-02 2095400200020 ENDCOMMON 3 0 2095400200021 DATA 10 1 2095400200022 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32095400200023 DATA 4DATA-ERR 4DATA 5DATA-ERR 5 2095400200024 MEV MEV MEV MEV MEV MEV 2095400200025 NO-DIM NO-DIM NO-DIM NO-DIM 2095400200026 1.7790E+02 4.0000E-02 1.0340E+02 4.0000E-02 7.4500E+01 4.0000E-022095400200027 1.0076E+02 4.0000E-02 1.3924E+02 4.0000E-02 2095400200028 ENDDATA 6 0 2095400200029 ENDSUBENT 28 0 2095400299999 SUBENT 20954003 20120708 22322095400300001 BIB 2 11 2095400300002 REACTION 1(94-PU-240(0,F),PRE,AKE,LF+HF) Pre-neutron total 2095400300003 average kinetic energy. 2095400300004 2(94-PU-240(0,F),PRE,AKE,LF) Pre-neutron average kinetic2095400300005 energy of light fragment. 2095400300006 3(94-PU-240(0,F),PRE,AKE,HF) Pre-neutron average kinetic2095400300007 energy of heavy fragment. 2095400300008 4(94-PU-240(0,F),PRE,AP,LF) 2095400300009 5(94-PU-240(0,F),PRE,AP,HF) 2095400300010 HISTORY (20120708A) SD: MISC1, MISC2 deleted. Two REACTIONs 2095400300011 were added (p.4,5). 2095400300012 SF8=FF => LF+HF in REACTION code. 2095400300013 ENDBIB 11 0 2095400300014 NOCOMMON 0 0 2095400300015 DATA 10 1 2095400300016 DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 3DATA-ERR 32095400300017 DATA 4DATA-ERR 4DATA 5DATA-ERR 5 2095400300018 MEV MEV MEV MEV MEV MEV 2095400300019 NO-DIM NO-DIM NO-DIM NO-DIM 2095400300020 1.7680E+02 1.4000E-01 1.0240E+02 1.4000E-01 7.4300E+01 1.4000E-012095400300021 1.0155E+02 1.4000E-01 1.3845E+02 1.4000E-01 2095400300022 ENDDATA 6 0 2095400300023 ENDSUBENT 22 0 2095400399999 ENDENTRY 3 0 2095499999999