ENTRY 21483 19900312 00002148300000001 SUBENT 21483001 19900312 00002148300100001 BIB 12 22 2148300100002 REFERENCE (J,EN,15,272,6804) 2148300100003 TITLE -THE BA-140 YIELDS FOR THERMAL AND FAST FISSION 2148300100004 OF U-235 AND U-238 -. 2148300100005 AUTHOR (L.CIUFFOLOTTI) 2148300100006 INSTITUTE (2ITYMIL) SORIN, SALUGGIA (VERCELLI). 2148300100007 EXPERIMENT AT MILAN. 2148300100008 FACILITY (REAC ) L-54 REACTOR AT CENTRO DI STUDI NUCLEARI 2148300100009 ENRICO FERMI, MILAN. 2148300100010 INC-SOURCE (REAC ) REACTOR NEUTRONS. 2148300100011 METHOD .FISSION PRODUCT ACTIVITY MEASUREMENT. 2148300100012 DETECTOR (NAICR) TWO NAI(TL) CRYSTALS. 2148300100013 (FISCH) FISSION CHAMBER FOR FISSION MONITORING. 2148300100014 CORRECTION .CORRECTED FOR COUNTER EFFICIENCY. 2148300100015 ERR-ANALYS .ERRORS ARE PRIMARILLY STATISTICAL, ONE STANDARD 2148300100016 DEVIATION, BUT DO INCLUDE ERROS FROM IMPERFECT 2148300100017 OXIDE REMOVAL FROM THE SAMPLE SURFACE. 2148300100018 STATUS .TABLES IN EN,15,272. 2148300100019 HISTORY (800402C) 2148300100020 (800429E) 2148300100021 (890911A) CUM NOT IND YIELDS IN SUBENTS 2 AND 3 2148300100022 AND REFERENCE DATE CORRECTED 2148300100023 (890919E) 2148300100024 ENDBIB 22 0 2148300100025 NOCOMMON 0 0 2148300100026 ENDSUBENT 25 0 2148300199999 SUBENT 21483002 19900312 00002148300200001 BIB 7 13 2148300200002 REACTION (92-U-235(N,F)56-BA-140,CUM,FY,,MXW) THERMAL 2148300200003 AVERAGE WHOLE CHAIN CUMULATIVE FISSION YIELD. 2148300200004 SAMPLE .NATURAL URANIUM SAMPLE OF 350.2 MG. 2148300200005 COMMENT .ABSOLUTE MEASUREMENT. 2148300200006 DECAY-DATA (57-LA-140,40.2HR,DG,1600.) 1.6 MEV GAMMAS. 2148300200007 INC-SPECT MAXWELLIAN THERMAL NEUTRON SPECTRUM IN IN 2148300200008 THE THERMAL COLUMN. IRRADIATION FOR 5.5 HOURS 2148300200009 IN A FLUX OF 10*8 N/CM*2/SEC. 2148300200010 STATUS .TEXT, PAGE 276. 2148300200011 HISTORY (800402C) 2148300200012 (800429E) 2148300200013 (890911A) CUM NOT IND YIELD 2148300200014 (890919E) 2148300200015 ENDBIB 13 0 2148300200016 NOCOMMON 0 0 2148300200017 DATA 3 1 2148300200018 EN-DUMMY DATA DATA-ERR 2148300200019 EV PC/FIS PC/FIS 2148300200020 2.5300E-02 6.3600E+00 2.5000E-01 2148300200021 ENDDATA 3 0 2148300200022 ENDSUBENT 21 0 2148300299999 SUBENT 21483003 19900312 00002148300300001 BIB 8 19 2148300300002 REACTION (92-U-238(N,F)56-BA-140,CUM,FY,,FIS) FISSION SPECTRUM 2148300300003 AVERAGE WHOLE CHAIN CUMULATIVE FISSION YIELD. 2148300300004 MONITOR (92-U-235(N,F)56-BA-140,CUM,FY,,MXW) MAXWELLIAN 2148300300005 AVERAGE WHOLE CHAIN CUMULATIVE FISSION YIELD. 2148300300006 SAMPLE .DEPLETED URANIUM, 916.6 MG. 2148300300007 ANALYSIS .DEVIRED FROM MEASURED RATIO TO U 235 THERMAL FISSION 2148300300008 YIELD. 2148300300009 DECAY-DATA (57-LA-140,40.2HR,DG,1600.) 1.6 MEV GAMMAS. 2148300300010 INC-SPECT FISSION NEUTRON SPECTRUM. IRRADIATION NEAR 2148300300011 THE REACTOR CORE FOR 7.5 HR. THE SAMPLE AND FISSION 2148300300012 CHAMBER WERE COVERED WITH 2 MM CADMIUM CLADDING 2148300300013 TO ELIMINATE U-235 THERMAL FISSION, AND SURROUNDED 2148300300014 BY 1MM THICK NATURAL URANIUM SHEET AS A THERMAL 2148300300015 TO FAST FLUX CONVERTER. 2148300300016 STATUS .TEXT, PAGE 276. 2148300300017 HISTORY (800402C) 2148300300018 (800429E) 2148300300019 (890911A) CUM NOT IND YIELDS 2148300300020 (890919E) 2148300300021 ENDBIB 19 0 2148300300022 NOCOMMON 0 0 2148300300023 DATA 6 1 2148300300024 EN-DUMMY EN-NRM MONIT MONIT-ERR DATA DATA-ERR 2148300300025 EV EV PC/FIS PC/FIS PC/FIS PC/FIS 2148300300026 1.5000E+00 2.5300E-02 6.3600E+00 1.2000E-01 6.0300E+00 2.2000E-012148300300027 ENDDATA 3 0 2148300300028 ENDSUBENT 27 0 2148300399999 ENDENTRY 3 0 2148399999999