ENTRY 21484 19800429 00002148400000001 SUBENT 21484001 19800429 00002148400100001 BIB 13 21 2148400100002 INSTITUTE (2FR SAC) 2148400100003 REFERENCE (R,CEA-652,17,58) CHAPTER III. 2148400100004 (C,55GENEVA,8,592,55) ARTICLE BY LEACHMAN. 2148400100005 AUTHOR (M.JACOB) 2148400100006 TITLE -VARIATION IN THE AVERAGE NUMBER OF NEUTRONS EMITTED 2148400100007 BY FISSION OF PU-239 FROM A THERMAL SPECTRUM TO A 2148400100008 FISSION SPECTRUM OF INCIDENT NEUTRONS -. 2148400100009 FACILITY (REAC ) THERMAL PILE, SACLAY. 2148400100010 INC-SOURCE (REAC ) THERMAL NEUTRON BEAM. 2148400100011 SAMPLE .PLUTONIUM 239, NO DETAILS. 2148400100012 METHOD .COINCIDENCE OF FISSION NEUTRONS WITH FISSION 2148400100013 FRAGMENTS. 2148400100014 DETECTOR (BF3 ) BF3 COUNTERS ENRICHED IN B-10 FOR NEUTRONS. 2148400100015 (FISCH) FISSION CHAMBER FOR FRAGMENT MONITOR. 2148400100016 PART-DET (N ) NEUTRONS. 2148400100017 (FF ) FISSION FRAGMENTS. 2148400100018 STATUS .TEXT, PAGE 19. ALSO PUBLISHED IN THE AMSTERDAM 2148400100019 CONFERENCE. 2148400100020 HISTORY (800402C) 2148400100021 (800429E) 2148400100022 ERR-ANALYS .ONE STANDARD DEVIATION, PRIMARILLY STATISTICAL. 2148400100023 ENDBIB 21 0 2148400100024 NOCOMMON 0 0 2148400100025 ENDSUBENT 24 0 2148400199999 SUBENT 21484002 19810204 00002148400200001 BIB 5 15 2148400200002 REACTION ((94-PU-239(N,F),,NU,,MXW)/(94-PU-239(N,F),,NU,,FIS)) 2148400200003 RATIO OF FISSION SPECTRUM AVERAGE TO THERMAL 2148400200004 SPECTRUM AVERAGE NU. 2148400200005 INC-SPECT WELL THERMALIZED NEUTRON BEAM IN THERMAL 2148400200006 COLUMN. 2148400200007 FISSION SPECTRUM. SAMPLE INSIDE A NATURAL 2148400200008 URANIUM CYLINDER, 3 CM THICK, ACTING AS A THERMAL 2148400200009 TO FAST SPECTRUM CONVERTER WITH A TRANSFORMATION 2148400200010 FACTOR OF 0.6. 2148400200011 STATUS .TEXT, PAGE 19. 2148400200012 HISTORY (800402C) 2148400200013 (800429E) 2148400200014 ERR-ANALYS .STATISTICAL ERROR LESS THAN 2 PERCENT, QUOTED ERROR 2148400200015 IS A STATISTICAL UNCERTAINTY WITH 85 PERCENT 2148400200016 CONFIDENCE LIMITS. 2148400200017 ENDBIB 15 0 2148400200018 NOCOMMON 0 0 2148400200019 DATA 4 1 2148400200020 EN-DUMMY EN-DUMMY RATIO RATIO-ERR 2148400200021 EV EV NO-DIM NO-DIM 2148400200022 2.5300E-02 1.5000E+00 1.0650E+00 2.0000E-02 2148400200023 ENDDATA 3 0 2148400200024 ENDSUBENT 23 0 2148400299999 SUBENT 21484003 19810204 00002148400300001 BIB 6 11 2148400300002 REACTION (94-PU-239(N,F),,NU,,FIS) FISSION SPECTRUM AVERAGE NU. 2148400300003 INC-SPECT FISSION SPECTRUM. SAMPLE INSIDE A CYLINDER OF 2148400300004 NATURAL URANIUM, 3 CM THICK, ACTING AS A THERMAL TO 2148400300005 FISSION SPECTRUM CONVERTER. 2148400300006 ANALYSIS .DERIVED FROM MEASURED RATIO OF THE FISSION TO 2148400300007 THERMAL SPECTRUM AVERAGE VALUES. 2148400300008 MONITOR (94-PU-239(N,F),,NU,,MXW) MAXWELLIAN AVERAGE NU. 2148400300009 STATUS .TEXT, PAGE 19. 2148400300010 (DEP,21484002) 2148400300011 HISTORY (800402C) 2148400300012 (800429E) 2148400300013 ENDBIB 11 0 2148400300014 NOCOMMON 0 0 2148400300015 DATA 6 1 2148400300016 EN-DUMMY EN-NRM MONIT MONIT-ERR DATA DATA-ERR 2148400300017 MEV EV NO-DIM NO-DIM NO-DIM NO-DIM 2148400300018 1.5000E+00 2.5300E-02 2.9200E+00 2.0000E-02 3.1000E+00 7.0000E-022148400300019 ENDDATA 3 0 2148400300020 ENDSUBENT 19 0 2148400399999 ENDENTRY 3 0 2148499999999