ENTRY 21736 19810213 00002173600000001 SUBENT 21736001 19810213 00002173600100001 BIB 13 23 2173600100002 INSTITUTE (2FR GRE) 2173600100003 REFERENCE (P,NEANDC(E)-162U,4,42,7400) SHORT REPORT WITH TABLES. 2173600100004 AUTHOR (J.BLACHOT) 2173600100005 TITLE -FISSION PRODUCT YIELDS FROM FISSION OF TARGETS OF 2173600100006 URANIUM IN A THERMAL NEUTRON SPECTRUM AND IN A FISSIO 2173600100007 NEUTRON SPECTRUM -. 2173600100008 FACILITY (REAC ) MELUSINE REACTOR, CORE OF THE HEAVY WATER 2173600100009 REACTOR AT C.E.N. GRENOBLE. 2173600100010 INC-SOURCE (REAC ) REACTOR NEUTRONS. 2173600100011 SAMPLE .NO DETAILS. 2173600100012 METHOD (CHSEP) MOST DATA ARE OBTAINED BY NON-DESTRUCTIVE 2173600100013 ANALYSIS OF THE SAMPLES, OTHERS AFTER CHEMICAL 2173600100014 SEPERATION OF THE ISOTOPES OF CADMIUM AND SILVER. 2173600100015 DETECTOR (GELI ) GE(LI) DETECTOR, NO DETAILS. 2173600100016 MONITOR (92-U-235(N,F)56-BA-140,CUM,FY) ALL DATA NORMALISED 2173600100017 TO A VALUE OF UNITY FOR THIS YIELD. 2173600100018 STATUS .TABLES IN NEANDC(E)-162U,4, PAGE 45, 46. 2173600100019 HISTORY (810125C) 2173600100020 (810213E) 2173600100021 ERR-ANALYS .WHERE MORE THAN ONE MEASUREMENT WAS MADE AN ERROR 2173600100022 FROM THE SPREAD OF VALUES IS GIVEN AT ONE STANDARD 2173600100023 DEVIATION. NO ERROR IS GIVEN WHEN ONLY A SINGLE 2173600100024 MEASUREMENT WAS DONE. 2173600100025 ENDBIB 23 0 2173600100026 COMMON 1 3 2173600100027 MONIT 2173600100028 PC/FIS 2173600100029 1.0000E+00 2173600100030 ENDCOMMON 3 0 2173600100031 ENDSUBENT 30 0 2173600199999 SUBENT 21736002 19810723 00002173600200001 BIB 4 7 2173600200002 REACTION (92-U-233(N,F)MASS,CHN,FY,,MXW/REL) CHAIN YIELDS IN A 2173600200003 THERMAL NEUTRON FLUX. 2173600200004 VALUES GIVEN RELATIVE TO UNITY FOR THE BA-140 YIELD. 2173600200005 INC-SPECT .THERMAL MAXWELLIAN NEUTRON SPECTRUM. 2173600200006 STATUS .TABLE 1, PAGE 45. 2173600200007 HISTORY (810125C) 2173600200008 (810213E) 2173600200009 ENDBIB 7 0 2173600200010 COMMON 1 3 2173600200011 EN-DUMMY 2173600200012 EV 2173600200013 2.5300E-02 2173600200014 ENDCOMMON 3 0 2173600200015 DATA 3 18 2173600200016 MASS DATA DATA-ERR 2173600200017 NO-DIM ARB-UNITS ARB-UNITS 2173600200018 9.1000E+01 1.0300E+00 6.0000E-02 2173600200019 9.2000E+01 1.0100E+00 9.0000E-02 2173600200020 9.3000E+01 1.0600E+00 1.1000E-01 2173600200021 9.5000E+01 9.5000E-01 6.0000E-02 2173600200022 9.9000E+01 6.8000E-01 9.0000E-02 2173600200023 1.0300E+02 2.6000E-01 3.0000E-02 2173600200024 1.1100E+02 7.5000E-02 2173600200025 1.1500E+02 5.0000E-03 3.0000E-03 2173600200026 1.2700E+02 6.0000E-02 1.0000E-02 2173600200027 1.3100E+02 5.8000E-01 4.0000E-02 2173600200028 1.3200E+02 7.6000E-01 6.0000E-02 2173600200029 1.3700E+02 9.3000E-01 4.0000E-02 2173600200030 1.4100E+02 1.0400E+00 8.0000E-02 2173600200031 1.4200E+02 1.0200E+00 2173600200032 1.4300E+02 8.0000E-01 7.0000E-02 2173600200033 1.4400E+02 8.1000E-01 5.0000E-02 2173600200034 1.4700E+02 2.9000E-01 2.0000E-02 2173600200035 1.5100E+02 3.8000E-02 5.0000E-03 2173600200036 ENDDATA 20 0 2173600200037 ENDSUBENT 36 0 2173600299999 SUBENT 21736003 19810723 00002173600300001 BIB 4 7 2173600300002 REACTION (92-U-235(N,F)MASS,CHN,FY,,MXW/REL) RELATIVE CHAIN YIE 2173600300003 IN A THERMAL NEUTRON SPECTRUM. 2173600300004 DATA ARE GIVEN RELATIVE TO UNITY FOR THE BA-140 YIELD 2173600300005 INC-SPECT .THERMAL MAXWELLIAN NEUTRON SPECTRUM. 2173600300006 STATUS .TABLE 1, PAGE 45. 2173600300007 HISTORY (810125C) 2173600300008 (810213E) 2173600300009 ENDBIB 7 0 2173600300010 COMMON 1 3 2173600300011 EN-DUMMY 2173600300012 EV 2173600300013 2.5300E-02 2173600300014 ENDCOMMON 3 0 2173600300015 DATA 3 16 2173600300016 MASS DATA DATA-ERR 2173600300017 NO-DIM ARB-UNITS ARB-UNITS 2173600300018 9.5000E+01 1.0500E+00 9.0000E-02 2173600300019 9.9000E+01 8.0700E-01 2173600300020 1.0300E+02 4.7000E-01 5.0000E-02 2173600300021 1.1100E+02 5.0000E-03 1.0000E-03 2173600300022 1.1500E+02 3.0000E-03 1.0000E-03 2173600300023 1.2700E+02 2.8000E-02 6.0000E-03 2173600300024 1.3100E+02 4.8000E-01 1.0000E-02 2173600300025 1.3200E+02 6.6000E-01 2.0000E-02 2173600300026 1.3300E+02 1.1150E+00 2173600300027 1.3700E+02 9.4000E-01 1.0000E-02 2173600300028 1.4100E+02 9.5000E-01 6.0000E-02 2173600300029 1.4300E+02 8.6000E-01 7.0000E-02 2173600300030 1.4400E+02 8.6000E-01 2.0000E-02 2173600300031 1.4700E+02 3.5000E-01 3.0000E-02 2173600300032 1.5100E+02 5.0000E-02 8.0000E-03 2173600300033 1.5300E+02 2.2000E-01 6.0000E-03 2173600300034 ENDDATA 18 0 2173600300035 ENDSUBENT 34 0 2173600399999 SUBENT 21736004 19810723 00002173600400001 BIB 4 7 2173600400002 REACTION (92-U-233(N,F)MASS,CHN,FY,,FIS/REL) CHAIN YIELDS 2173600400003 IN A FISSION NEUTRON SPECTRUM. 2173600400004 DATA ARE GIVEN RELATIVE TO UNITY FOR THE BA-140 YIELD 2173600400005 INC-SPECT .FISSION NEUTRON SPECTRUM, CARAMEL IRRADIATION. 2173600400006 STATUS .TABLE 2, PAGE 46. 2173600400007 HISTORY (810125C) 2173600400008 (810213E) 2173600400009 ENDBIB 7 0 2173600400010 COMMON 1 3 2173600400011 EN-DUMMY 2173600400012 MEV 2173600400013 1.5000E+00 2173600400014 ENDCOMMON 3 0 2173600400015 DATA 3 21 2173600400016 MASS DATA DATA-ERR 2173600400017 NO-DIM ARB-UNITS ARB-UNITS 2173600400018 8.5000E+01 3.6000E-01 1.0000E-02 2173600400019 9.1000E+01 8.4000E-01 3.0000E-02 2173600400020 9.2000E+01 8.4000E-01 3.0000E-02 2173600400021 9.5000E+01 1.0200E+00 2.0000E-02 2173600400022 9.7000E+01 8.3000E-01 7.0000E-02 2173600400023 9.9000E+01 6.5000E-01 6.0000E-02 2173600400024 1.0300E+02 2.7000E-01 2.0000E-02 2173600400025 1.0600E+02 4.7000E-02 4.0000E-03 2173600400026 1.2500E+02 3.4000E-02 2173600400027 1.2700E+02 7.8000E-02 3.0000E-03 2173600400028 1.3100E+02 6.5000E-01 2.0000E-02 2173600400029 1.3200E+02 7.3000E-01 7.0000E-02 2173600400030 1.3300E+02 9.9000E-01 9.0000E-02 2173600400031 1.3500E+02 8.7000E-01 2173600400032 1.3700E+02 1.0000E+00 8.0000E-02 2173600400033 1.4100E+02 1.1300E+00 6.0000E-02 2173600400034 1.4300E+02 7.7000E-01 7.0000E-02 2173600400035 1.4400E+02 9.8000E-01 1.1000E-01 2173600400036 1.4700E+02 2.9000E-01 1.0000E-02 2173600400037 1.5100E+02 6.0000E-02 1.0000E-02 2173600400038 1.5300E+02 2.6000E-02 2173600400039 ENDDATA 23 0 2173600400040 ENDSUBENT 39 0 2173600499999 SUBENT 21736005 19810723 00002173600500001 BIB 4 8 2173600500002 REACTION (92-U-234(N,F)MASS,CHN,FY,,FIS/REL) CHAIN YIELDS 2173600500003 IN A THERMAL MAXWELLIAN NEUTRON SPECTRUM. 2173600500004 DATA ARE GIVEN RELATIVE TO A YIELD OF UNITY 2173600500005 FOR BA-140. 2173600500006 INC-SPECT .FISSION NEUTRON SPECTRUM, CARAMEL IRRADIATION. 2173600500007 STATUS .TABLE 2, PAGE 46. 2173600500008 HISTORY (810126C) 2173600500009 (810213E) 2173600500010 ENDBIB 8 0 2173600500011 COMMON 1 3 2173600500012 EN-DUMMY 2173600500013 MEV 2173600500014 1.5000E+00 2173600500015 ENDCOMMON 3 0 2173600500016 DATA 3 21 2173600500017 MASS DATA DATA-ERR 2173600500018 NO-DIM ARB-UNITS ARB-UNITS 2173600500019 8.5000E+01 2.4000E-01 1.1000E-01 2173600500020 9.1000E+01 9.0000E-01 6.0000E-02 2173600500021 9.2000E+01 1.0400E+00 5.0000E-02 2173600500022 9.3000E+01 1.1000E+00 2.0000E-02 2173600500023 9.5000E+01 1.1100E+00 6.0000E-02 2173600500024 9.7000E+01 1.0600E+00 7.0000E-02 2173600500025 9.9000E+01 7.4000E-01 7.0000E-02 2173600500026 1.0300E+02 4.3000E-01 2.0000E-02 2173600500027 1.0600E+02 8.0000E-02 1.2000E-02 2173600500028 1.2500E+02 2.1000E-02 5.0000E-03 2173600500029 1.2700E+02 6.7000E-02 6.0000E-03 2173600500030 1.3100E+02 6.5000E-01 4.0000E-02 2173600500031 1.3200E+02 7.5000E-01 5.0000E-02 2173600500032 1.3300E+02 1.1300E+00 7.0000E-02 2173600500033 1.3500E+02 8.1000E-01 2.0000E-02 2173600500034 1.3700E+02 1.0100E+00 2.0000E-02 2173600500035 1.4100E+02 1.1300E+00 9.0000E-02 2173600500036 1.4300E+02 8.3000E-01 6.0000E-02 2173600500037 1.4400E+02 1.0800E+00 5.0000E-02 2173600500038 1.4700E+02 3.5000E-01 2.0000E-02 2173600500039 1.5100E+02 5.0000E-02 1.0000E-02 2173600500040 ENDDATA 23 0 2173600500041 ENDSUBENT 40 0 2173600599999 SUBENT 21736006 19810723 00002173600600001 BIB 4 8 2173600600002 REACTION (92-U-235(N,F)MASS,CHN,FY,,FIS/REL) CHAIN YIELDS 2173600600003 IN A FISSION NEUTRON SPECTRUM. 2173600600004 DATA ARE GIVEN RELATIVE TO A YIELD OF UNITY 2173600600005 FOR BA-140. 2173600600006 INC-SPECT .FISSION NEUTRON SPECTRUM, CARAMEL IRRADIATION. 2173600600007 STATUS .TABLE 2, PAGE 46. 2173600600008 HISTORY (810126C) 2173600600009 (810213E) 2173600600010 ENDBIB 8 0 2173600600011 COMMON 1 3 2173600600012 EN-DUMMY 2173600600013 MEV 2173600600014 1.5000E+00 2173600600015 ENDCOMMON 3 0 2173600600016 DATA 3 21 2173600600017 MASS DATA DATA-ERR 2173600600018 NO-DIM ARB-UNITS ARB-UNITS 2173600600019 8.5000E+01 2.2000E-01 2.0000E-02 2173600600020 9.1000E+01 8.9000E-01 3.0000E-02 2173600600021 9.2000E+01 8.4000E-01 7.0000E-02 2173600600022 9.3000E+01 9.4000E-01 3.0000E-02 2173600600023 9.5000E+01 1.0300E+00 5.0000E-02 2173600600024 9.7000E+01 9.2000E-01 7.0000E-02 2173600600025 9.9000E+01 8.2000E-01 5.0000E-02 2173600600026 1.0300E+02 5.1000E-01 2.0000E-02 2173600600027 1.0600E+02 9.4000E-02 2173600600028 1.2500E+02 3.6000E-02 2173600600029 1.2700E+02 3.0000E-02 4.0000E-03 2173600600030 1.3100E+02 5.2000E-01 4.0000E-02 2173600600031 1.3200E+02 7.0000E-01 6.0000E-02 2173600600032 1.3300E+02 1.1200E+00 6.0000E-02 2173600600033 1.3500E+02 8.4000E-01 3.0000E-02 2173600600034 1.3700E+02 1.0000E+00 6.0000E-02 2173600600035 1.4100E+02 1.0300E+00 4.0000E-02 2173600600036 1.4300E+02 8.2000E-01 6.0000E-02 2173600600037 1.4400E+02 9.6000E-01 7.0000E-02 2173600600038 1.4700E+02 3.1000E-01 3.0000E-02 2173600600039 1.5100E+02 6.0000E-02 2.0000E-02 2173600600040 ENDDATA 23 0 2173600600041 ENDSUBENT 40 0 2173600699999 SUBENT 21736007 19810723 00002173600700001 BIB 4 8 2173600700002 REACTION (92-U-236(N,F)MASS,CHN,FY,,FIS/REL) CHAIN YIELDS 2173600700003 IN A FISSION NEUTRON SPECTRUM. 2173600700004 DATA ARE GIVEN RELATIVE TO A YIELD OF UNITY 2173600700005 FOR BA-140. 2173600700006 INC-SPECT .FISSION NEUTRON SPECTRUM,CARAMEL IRRADIATION. 2173600700007 STATUS .TABLE 2, PAGE 46. 2173600700008 HISTORY (810126C) 2173600700009 (810213E) 2173600700010 ENDBIB 8 0 2173600700011 COMMON 1 3 2173600700012 EN-DUMMY 2173600700013 MEV 2173600700014 1.5000E+00 2173600700015 ENDCOMMON 3 0 2173600700016 DATA 3 20 2173600700017 MASS DATA DATA-ERR 2173600700018 NO-DIM ARB-UNITS ARB-UNITS 2173600700019 8.5000E+01 2.7000E-01 2.0000E-02 2173600700020 9.1000E+01 9.3000E-01 4.0000E-02 2173600700021 9.2000E+01 1.0600E+00 6.0000E-02 2173600700022 9.5000E+01 1.0900E+00 5.0000E-02 2173600700023 9.7000E+01 8.5000E-01 3.0000E-02 2173600700024 9.9000E+01 8.6000E-01 7.0000E-02 2173600700025 1.0300E+02 7.1000E-01 5.0000E-02 2173600700026 1.0600E+02 1.7000E-01 2173600700027 1.2500E+02 3.3000E-02 2173600700028 1.2700E+02 3.5000E-02 6.0000E-03 2173600700029 1.3100E+02 5.3000E-01 6.0000E-02 2173600700030 1.3200E+02 7.5000E-01 2.0000E-02 2173600700031 1.3300E+02 1.3300E+00 1.2000E-01 2173600700032 1.3500E+02 1.0100E+00 6.0000E-02 2173600700033 1.3700E+02 1.0670E+00 2173600700034 1.4100E+02 9.7000E-01 1.0000E-01 2173600700035 1.4300E+02 6.9000E-01 5.0000E-02 2173600700036 1.4400E+02 9.1000E-01 5.0000E-02 2173600700037 1.4700E+02 4.1000E-01 2.0000E-02 2173600700038 1.5100E+02 3.8000E-02 7.0000E-03 2173600700039 ENDDATA 22 0 2173600700040 ENDSUBENT 39 0 2173600799999 SUBENT 21736008 19810723 00002173600800001 BIB 4 8 2173600800002 REACTION (92-U-238(N,F)MASS,CHN,FY,,FIS/REL) CHAIN YIELDS 2173600800003 IN A FISSION NEUTRON SPECTRUM. 2173600800004 DATA ARE GIVEN RELATIVE TO A YIELD OF UNITY 2173600800005 FOR BA-140. 2173600800006 INC-SPECT .FISSION NEUTRON SPECTRUM, CARAMEL IRRADIATION. 2173600800007 STATUS .TABLE 2, PAGE 46. 2173600800008 HISTORY (810126C) 2173600800009 (810213E) 2173600800010 ENDBIB 8 0 2173600800011 COMMON 1 3 2173600800012 EN-DUMMY 2173600800013 MEV 2173600800014 1.5000E+00 2173600800015 ENDCOMMON 3 0 2173600800016 DATA 3 20 2173600800017 MASS DATA DATA-ERR 2173600800018 NO-DIM ARB-UNITS ARB-UNITS 2173600800019 8.5000E+01 1.7000E-01 1.0000E-02 2173600800020 9.1000E+01 6.5000E-01 2173600800021 9.2000E+01 6.4000E-01 2.0000E-02 2173600800022 9.5000E+01 8.4000E-01 4.0000E-02 2173600800023 9.7000E+01 9.2000E-01 1.0000E-01 2173600800024 9.9000E+01 8.6000E-01 7.0000E-02 2173600800025 1.0300E+02 1.0100E+00 2.0000E-02 2173600800026 1.0600E+02 3.8000E-01 6.0000E-02 2173600800027 1.2500E+02 5.0000E-03 2.0000E-03 2173600800028 1.2700E+02 2.2000E-02 5.0000E-03 2173600800029 1.3100E+02 5.3000E-01 1.0000E-02 2173600800030 1.3200E+02 7.5000E-01 6.0000E-02 2173600800031 1.3300E+02 1.1800E+00 1.4000E-01 2173600800032 1.3500E+02 9.2000E-01 6.0000E-02 2173600800033 1.3700E+02 1.0600E+00 2.0000E-02 2173600800034 1.4100E+02 9.5000E-01 5.0000E-02 2173600800035 1.4300E+02 6.9000E-01 5.0000E-02 2173600800036 1.4400E+02 9.8000E-01 8.0000E-02 2173600800037 1.4700E+02 4.6000E-01 1.0000E-02 2173600800038 1.5100E+02 1.3400E-01 1.0000E-03 2173600800039 ENDDATA 22 0 2173600800040 ENDSUBENT 39 0 2173600899999 ENDENTRY 8 0 2173699999999