ENTRY 23574 20200505 22872357400000001 SUBENT 23574001 20200505 22872357400100001 BIB 12 21 2357400100002 TITLE Determination of thermal and epithermal fission yields2357400100003 of Cs-136, Cs-137, Ba-140, Ru-103 and Rn-106 from U-2332357400100004 and U-235 samples 2357400100005 AUTHOR (L.Balcarczyuk, P.Keratschev, E.Lanzel) 2357400100006 REFERENCE (J,NUK,7,169,1965) In German 2357400100007 INSTITUTE (2AUSSGA) 2357400100008 FACILITY (REAC,2AUSSGA) 2357400100009 INC-SOURCE (REAC) 2357400100010 INC-SPECT 5.E+12 n/(cm2*sec) , irradiation time 1 month. 2357400100011 SAMPLE 0.8 - 20 mg of 99% enriched U-233 and U-235 in form 2357400100012 of U(3)O(8) and UO(2). Pressed between two Al foils 2357400100013 of 2 mg/cm2 thickness. For first two runs. 2357400100014 For 3rd run - prepared by chemical procedure from 2357400100015 microgram of metal oxide. 2357400100016 For one run - two U-233 and two U-235 samples, 2357400100017 one of them in Cd sleeve. 2357400100018 Co as neutron flux monitor. 2357400100019 METHOD (CHSEP) 2357400100020 ASSUMED (ASSUM1,27-CO-59(N,G)27-CO-60,,RI) 2357400100021 REL-REF (R,,F.J.Johnston+,J,JNE/A,11,95,1960) ASSUM1 data 2357400100022 HISTORY (20200415C) M.M. 2357400100023 ENDBIB 21 0 2357400100024 COMMON 1 3 2357400100025 ASSUM1 2357400100026 B 2357400100027 75. 2357400100028 ENDCOMMON 3 0 2357400100029 ENDSUBENT 28 0 2357400199999 SUBENT 23574002 20200505 22872357400200001 BIB 6 12 2357400200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 2357400200003 MONITOR ((MONIT)92-U-235(N,F)56-BA-140,CUM,FY,,SPA) 2357400200004 MONIT-REF (,S.Katcoff,J,NUC,18,201,1960) 2357400200005 ASSUMED (ASSUM,92-U-235(N,F),,RI) 2357400200006 From N.P.Baumann, Resonance integrals and 2357400200007 self-shielding factor for detector foils,AEC research 2357400200008 and development report DP-817,1963. 2357400200009 ERR-ANALYS (DATA-ERR) Uncertainty includes contribution from 2357400200010 neutron flux, beta- and gamma measurement, reactor 2357400200011 stability fluctuations. 2357400200012 Literature data (RI) errors are not included. 2357400200013 STATUS (TABLE) Table on page 171 of Nukleonik,v.7,p.169,1965 2357400200014 ENDBIB 12 0 2357400200015 COMMON 5 3 2357400200016 EN-DUMMY MONIT DATA-ERR ASSUM ASSUM-ERR 2357400200017 EV PC/FIS PER-CENT B B 2357400200018 0.0253 6.35 6. 262. 11. 2357400200019 ENDCOMMON 3 0 2357400200020 DATA 3 2 2357400200021 ELEMENT MASS DATA 2357400200022 NO-DIM NO-DIM PC/FIS 2357400200023 55. 136. 0.00856 2357400200024 44. 103. 2.97 2357400200025 ENDDATA 4 0 2357400200026 ENDSUBENT 25 0 2357400299999 SUBENT 23574003 20200505 22872357400300001 BIB 6 14 2357400300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,EPI) 2357400300003 MONITOR ((MONIT)92-U-235(N,F)56-BA-140,CUM,FY,,EPI) 2357400300004 MONIT-REF (,S.Katcoff,J,NUC,18,201,1960) 2357400300005 For epithermal flux the same value as for thermal was 2357400300006 used 2357400300007 ASSUMED (ASSUM,92-U-235(N,F),,RI) 2357400300008 From N.P.Baumann, Resonance integrals and 2357400300009 self-shielding factor for detector foils,AEC research 2357400300010 and development report DP-817,1963. 2357400300011 ERR-ANALYS (DATA-ERR) Uncertainty includes contribution from 2357400300012 neutron flux, beta- and gamma measurement, reactor 2357400300013 stability fluctuations. 2357400300014 Literature data (RI) errors are not included. 2357400300015 STATUS (TABLE) Table on page 171 of Nukleonik,v.7,p.169,1965 2357400300016 ENDBIB 14 0 2357400300017 COMMON 5 3 2357400300018 EN-MIN MONIT DATA-ERR ASSUM ASSUM-ERR 2357400300019 EV PC/FIS PER-CENT B B 2357400300020 0.5 6.35 6. 262. 11. 2357400300021 ENDCOMMON 3 0 2357400300022 DATA 3 3 2357400300023 ELEMENT MASS DATA 2357400300024 NO-DIM NO-DIM PC/FIS 2357400300025 55. 137. 6.13 2357400300026 55. 136. 0.00856 2357400300027 44. 103. 2.97 2357400300028 ENDDATA 5 0 2357400300029 ENDSUBENT 28 0 2357400399999 SUBENT 23574004 20200505 22872357400400001 BIB 6 11 2357400400002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,MXW) 2357400400003 MONITOR ((MONIT)92-U-235(N,F)56-BA-140,CUM,FY,,SPA) 2357400400004 ASSUMED (ASSUM,92-U-233(N,F),,RI) 2357400400005 REL-REF (R,,J.Chernick+,J,NSE,6,537,1959) 2357400400006 C.B.Bigham,Rep.CRRP-1184 (year is not given in article)2357400400007 Two refs. for ASSUM 2357400400008 ERR-ANALYS (DATA-ERR) Uncertainty includes contribution from 2357400400009 neutron flux, beta- and gamma measurement, reactor 2357400400010 stability fluctuations. 2357400400011 Literature data (RI) errors are not included. 2357400400012 STATUS (TABLE) Table on page 171 of Nukleonik,v.7,p.169,1965 2357400400013 ENDBIB 11 0 2357400400014 COMMON 5 3 2357400400015 EN-DUMMY MONIT DATA-ERR ASSUM ASSUM-ERR 2357400400016 EV PC/FIS PER-CENT B B 2357400400017 0.0253 5.4 6. 761. 17. 2357400400018 ENDCOMMON 3 0 2357400400019 DATA 3 4 2357400400020 ELEMENT MASS DATA 2357400400021 NO-DIM NO-DIM PC/FIS 2357400400022 55. 137. 6.82 2357400400023 55. 136. 0.103 2357400400024 44. 106. 0.157 2357400400025 44. 103. 1.4 2357400400026 ENDDATA 6 0 2357400400027 ENDSUBENT 26 0 2357400499999 SUBENT 23574005 20200505 22872357400500001 BIB 6 13 2357400500002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,EPI) 2357400500003 MONITOR ((MONIT)92-U-235(N,F)56-BA-140,CUM,FY,,EPI) 2357400500004 For epithermal flux the same value as for thermal was 2357400500005 used 2357400500006 ASSUMED (ASSUM,92-U-233(N,F),,RI) 2357400500007 REL-REF (R,,J.Chernick+,J,NSE,6,537,1959) 2357400500008 C.B.Bigham,Rep.CRRP-1184 (year is not given in article)2357400500009 Two refs. for ASSUM 2357400500010 ERR-ANALYS (DATA-ERR) Uncertainty includes contribution from 2357400500011 neutron flux, beta- and gamma measurement, reactor 2357400500012 stability fluctuations. 2357400500013 Literature data (RI) errors are not included. 2357400500014 STATUS (TABLE) Table on page 171 of Nukleonik,v.7,p.169,1965 2357400500015 ENDBIB 13 0 2357400500016 COMMON 5 3 2357400500017 EN-MIN MONIT DATA-ERR ASSUM ASSUM-ERR 2357400500018 EV PC/FIS PER-CENT B B 2357400500019 0.5 5.4 6. 761. 17. 2357400500020 ENDCOMMON 3 0 2357400500021 DATA 3 4 2357400500022 ELEMENT MASS DATA 2357400500023 NO-DIM NO-DIM PC/FIS 2357400500024 55. 137. 6.82 2357400500025 55. 136. 0.1018 2357400500026 44. 106. 0.154 2357400500027 44. 103. 1.4 2357400500028 ENDDATA 6 0 2357400500029 ENDSUBENT 28 0 2357400599999 ENDENTRY 5 0 2357499999999