ENTRY 21812 19830330 00002181200000001 SUBENT 21812001 19830330 00002181200100001 BIB 16 54 2181200100002 INSTITUTE (2FR GRE) EXPERIMENTAL SITE 2181200100003 (2FR CAD) ALL FOUR AUTHORS. 2181200100004 REFERENCE (C,82ANTWER,,181,8209) 2181200100005 AUTHOR (M.DAROUZET,A.GIACOMETTI,R.GIRIEUD,M.ROBIN) 2181200100006 TITLE -EXPERIMENTAL DETERMINATION OF THE CROSS SECTIONS 2181200100007 OF PU,AM AND CM ISOTOPES IN A LIGHT WATER 2181200100008 REACTOR NEUTRON SPECTRUM. (IN FRENCH). 2181200100009 FACILITY (REAC ) SWIMMING POOL REACTOR 'MELUSINE', 2181200100010 CONTAINING AN ASSEMBLY OF 5 BY 5 FUEL PINS. 2181200100011 THE FUEL WAS URANIUM DIOXIDE ENRICHED TO 2181200100012 2.8 PER CENT AND CLAD IN ALUMINIUM. 2181200100013 INC-SOURCE (REAC ) 2181200100014 INC-SPECT .THERMAL REACTOR SPECTRUM. THE WATER TEMPERATURE WAS 2181200100015 32 DEGREES CELSIUS. 2181200100016 A 4-GROUP REPRESENTATION OF THE SPECTRUM WAS MEASURED 2181200100017 F1 = FLUX BETWEEN 0.9 MEV AND 10 MEV 2181200100018 F2 = FLUX BETWEEN 5 KEV AND 0.9 MEV 2181200100019 F3 = FLUX BETWEEN 0.625 EV AND 5 KEV 2181200100020 F4 = FLUX BETWEEN 0.0 EV AND 0.625 EV 2181200100021 F1/F4 = 1.7 F2/F4 = 2.6 F3/F4 = 1.8 2181200100022 SAMPLE .THE SAMPLE ISOTOPES WERE PRESENT AS TRACE ELEMENTS 2181200100023 (0.1 PER CENT BY MASS) IN CERTAIN FUEL PELLETS IN 2181200100024 THE CENTRAL FUEL PIN. 2181200100025 METHOD (ACTIV) SAMPLES IRRADIATED FOR 1021.5 HOURS AT FULL 2181200100026 POWER. THE CROSS SECTIONS WERE DEDUCED FROM 2181200100027 GAMMA,ALPHA AND MASS SPECTROMETRY OF THE 2181200100028 IRRADIATED AND NON RADIATED PURE AND DOPED 2181200100029 FUEL PELLETS. 2181200100030 DETECTOR .GAMMA,ALPHA AND MASS SPECTROMETERS. NO FURTHER 2181200100031 DETAILS GIVEN IN THE REFERENCE. 2181200100032 ANALYSIS .THE MEASURED CROSS SECTIONS CORRESPONDED TO THE 2181200100033 NEUTRON SPECTRUM AT THE CENTRAL PIN OF A 5 BY 5 2181200100034 LATTICE. THEY WERE CONVERTED INTO CROSS SECTIONS 2181200100035 FOR THE CENTRAL PIN OF A PWR 17 BY 17 LATTICE. 2181200100036 THIS CALCULATION USED A 4-GROUP REPRESENTATION 2181200100037 OF THE NEUTRON SPECTRUM IN THE CENTRE OF A 2181200100038 17 BY 17 LATTICE- 2181200100039 F1/F4 = 1.7 F2/F4 = 2.4 F3/F4 = 1.5 2181200100040 THE GROUP FLUXES F1,F2,F3,F4 ARE DEFINED UNDER 2181200100041 KEYWORD INC-SPECT. 2181200100042 COMMENT .THE REFERENCE CONTAINS A COMPARISON OF THE 2181200100043 MEASURED RESULTS TO AVERAGE CROSS SECTIONS 2181200100044 CALCULATED FROM DATA IN A LIBRARY IN USE AT 2181200100045 CADARACHE. 2181200100046 STATUS .DATA TAKEN FROM REFERENCE. 2181200100047 HISTORY (830127C) A.P.T. 2181200100048 (830210E) 2181200100049 CORRECTION .MODULE 'EVOGENE' OF THE 'KAFKA' SYSTEM WAS USED TO 2181200100050 CALCULATE COORECTION FACTORS FOR THE GAMMA AND ALPHA 2181200100051 ACTIVITIES OF HEAVY ISOTOPES AND CERTAIN FISSION 2181200100052 PODUCTS PRESENT IN THEIRRADIATED SAMPLES. 'EVOGENE' 2181200100053 USES 1-GROUP CROSS SECTIONS BASED ON THE RESULTS 2181200100054 OF THE NEUTRONICS CODE 'APOLLO'. 2181200100055 ERR-ANALYS .NO DETAILS GIVEN. 2181200100056 ENDBIB 54 0 2181200100057 COMMON 1 3 2181200100058 EN-DUMMY 2181200100059 EV 2181200100060 2.5000E-02 2181200100061 ENDCOMMON 3 0 2181200100062 ENDSUBENT 61 0 2181200199999 SUBENT 21812002 19830330 00002181200200001 BIB 3 5 2181200200002 REACTION ((94-PU-240(N,G)94-PU-241,,SIG,,MXW)/ 2181200200003 (92-U-235(N,G)92-U-236,,SIG,,MXW)) 2181200200004 STATUS .TABLE 1. 2181200200005 HISTORY (830126C) A.P.T. 2181200200006 (830210E) 2181200200007 ENDBIB 5 0 2181200200008 NOCOMMON 0 0 2181200200009 DATA 2 1 2181200200010 DATA DATA-ERR 2181200200011 NO-DIM NO-DIM 2181200200012 3.3500E+00 7.0000E-02 2181200200013 ENDDATA 3 0 2181200200014 ENDSUBENT 13 0 2181200299999 SUBENT 21812003 19830330 00002181200300001 BIB 3 5 2181200300002 REACTION ((94-PU-241(N,G)94-PU-242,,SIG,,MXW)/ 2181200300003 (92-U-235(N,G)92-U-236,,SIG,,MXW)) 2181200300004 STATUS .TABLE 1. 2181200300005 HISTORY (830126C) A.P.T. 2181200300006 (830210E) 2181200300007 ENDBIB 5 0 2181200300008 NOCOMMON 0 0 2181200300009 DATA 2 1 2181200300010 DATA DATA-ERR 2181200300011 NO-DIM NO-DIM 2181200300012 8.5300E-01 2.9000E-02 2181200300013 ENDDATA 3 0 2181200300014 ENDSUBENT 13 0 2181200399999 SUBENT 21812004 19830330 00002181200400001 BIB 3 5 2181200400002 REACTION ((94-PU-242(N,G)94-PU-243,,SIG,,MXW)/ 2181200400003 (92-U-235(N,G)92-U-236,,SIG,,MXW)) 2181200400004 STATUS .TABLE 1. 2181200400005 HISTORY (830126C) A.P.T. 2181200400006 (830210E) 2181200400007 ENDBIB 5 0 2181200400008 NOCOMMON 0 0 2181200400009 DATA 2 1 2181200400010 DATA DATA-ERR 2181200400011 NO-DIM NO-DIM 2181200400012 4.1600E-01 1.9000E-02 2181200400013 ENDDATA 3 0 2181200400014 ENDSUBENT 13 0 2181200499999 SUBENT 21812005 19830330 00002181200500001 BIB 3 5 2181200500002 REACTION ((95-AM-241(N,G)95-AM-242,,SIG,,MXW)/ 2181200500003 (92-U-235(N,G)92-U-236,,SIG,,MXW)) 2181200500004 STATUS .TABLE 1. 2181200500005 HISTORY (830126C) A.P.T. 2181200500006 (830210E) 2181200500007 ENDBIB 5 0 2181200500008 NOCOMMON 0 0 2181200500009 DATA 2 1 2181200500010 DATA DATA-ERR 2181200500011 NO-DIM NO-DIM 2181200500012 2.2800E+00 6.0000E-02 2181200500013 ENDDATA 3 0 2181200500014 ENDSUBENT 13 0 2181200599999 SUBENT 21812006 19830330 00002181200600001 BIB 3 5 2181200600002 REACTION ((95-AM-243(N,G)95-AM-244,,SIG,,MXW)/ 2181200600003 (92-U-235(N,G)92-U-236,,SIG,,MXW)) 2181200600004 STATUS .TABLE 1. 2181200600005 HISTORY (830126C) A.P.T. 2181200600006 (830210E) 2181200600007 ENDBIB 5 0 2181200600008 NOCOMMON 0 0 2181200600009 DATA 2 1 2181200600010 DATA DATA-ERR 2181200600011 NO-DIM NO-DIM 2181200600012 9.8200E-01 2.5000E-02 2181200600013 ENDDATA 3 0 2181200600014 ENDSUBENT 13 0 2181200699999 SUBENT 21812007 19830330 00002181200700001 BIB 3 5 2181200700002 REACTION ((96-CM-244(N,G)96-CM-245,,SIG,,MXW)/ 2181200700003 (92-U-235(N,G)92-U-236,,SIG,,MXW)) 2181200700004 STATUS .TABLE 1. 2181200700005 HISTORY (830126C) A.P.T. 2181200700006 (830210E) 2181200700007 ENDBIB 5 0 2181200700008 NOCOMMON 0 0 2181200700009 DATA 2 1 2181200700010 DATA DATA-ERR 2181200700011 NO-DIM NO-DIM 2181200700012 2.2700E-01 1.5000E-02 2181200700013 ENDDATA 3 0 2181200700014 ENDSUBENT 13 0 2181200799999 ENDENTRY 7 0 2181299999999