ENTRY 23309 20180406 22662330900000001 SUBENT 23309001 20180406 22662330900100001 BIB 11 22 2330900100002 TITLE A measurement of the fission cross sections of 233U, 2330900100003 235U and 239Pu 2330900100004 AUTHOR (R.L.G.Keith, A.McNair, A.L.Rodgers) 2330900100005 INSTITUTE (2UK ALD) 2330900100006 REFERENCE (J,JNE,22,477,1968) 2330900100007 (R,EANDC(UK)-92,1967) Same as J,JNE,22,477,1968 2330900100008 REL-REF (N,,G.C.Hanna+,J,REA,7,(4),3,1969) 2330900100009 Detailed discussion on error propagation of this work 2330900100010 in Appendix B 2330900100011 FACILITY (REAC,2UK ALD) HERALD research reactor 2330900100012 INC-SOURCE (THCOL) Graphite thermal column 2330900100013 INC-SPECT T=35+/-5 deg-C and epithermal index r=0.00085+/-0.000042330900100014 at irradiation position (the latter being measured by 2330900100015 Cd ratio measurements of Au foils inside the fission 2330900100016 chamber) 2330900100017 DETECTOR (FISCH) 2330900100018 (PROPC,NAICR) for 4pi beta-gamma count of 60Co 2330900100019 SAMPLE Co (99.95% pure, 0.2402 g) used for monitor. 2330900100020 Fissile samples were analyzed by mass and alpha 2330900100021 spectrometry. 2330900100022 HISTORY (20160921C) On 2330900100023 (20180406U) On. Minor revision in 007. 2330900100024 ENDBIB 22 0 2330900100025 NOCOMMON 0 0 2330900100026 ENDSUBENT 25 0 2330900199999 SUBENT 23309002 20160921 22562330900200001 BIB 7 29 2330900200002 REACTION (92-U-233(N,F),,SIG) 2330900200003 SAMPLE 2.5 cm2 active area and ~2.0 ug/cm2 2330900200004 (92-U-232,ENR=0.000008) 2330900200005 (92-U-233,ENR=0.99995) 2330900200006 (92-U-234,ENR=0.000005) 2330900200007 (92-U-235,ENR=0.000022) 2330900200008 (92-U-236,ENR=0.000001) 2330900200009 (92-U-238,ENR=0.000014) 2330900200010 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 2330900200011 MONIT-REF (21255002,R.Vaninbroukx,J,NSE,24,87,1966) 2330900200012 DECAY-MON (27-CO-60-G,5.27YR) 2330900200013 ERR-ANALYS Standard deviation: 2330900200014 (ERR-T) Total (1.0%) 2330900200015 (ERR-S) Experimental error on count ratios R (0.35%) 2330900200016 (ERR-1) Alpha purity of fissile material (0.1%) 2330900200017 (ERR-2) 233U half-life (0.7%) 2330900200018 (ERR-4) Weight of Co metal (0.1%) 2330900200019 (ERR-5) Purity of Co metal (0.1%) 2330900200020 (ERR-6) Preparation of Co solution (0.1%) 2330900200021 (ERR-7) 60Co decay correction (0.03%) 2330900200022 (ERR-8) Scaler accuracy (0.1%) 2330900200023 (ERR-9) Low geometry factor (0.25%) 2330900200024 (ERR-11) Neutron flux gradient (0.1%) 2330900200025 (ERR-12) Fission chamber efficiency (0.1%) 2330900200026 (ERR-13) Fission chamber background (0.01%) 2330900200027 (ERR-14) Fission chamber dead-time (0.15%) 2330900200028 (ERR-15) Neutron temperature and Cd ratio (0.01%) 2330900200029 (ERR-16) Systematic error in 60Co counting (0.1%) 2330900200030 STATUS (TABLE) Table 7 of J.Nucl.Energy 22(1968)477 2330900200031 ENDBIB 29 0 2330900200032 COMMON 14 9 2330900200033 ERR-1 ERR-2 ERR-4 ERR-5 ERR-6 ERR-7 2330900200034 ERR-8 ERR-9 ERR-11 ERR-12 ERR-13 ERR-14 2330900200035 ERR-15 ERR-16 2330900200036 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900200037 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900200038 PER-CENT PER-CENT 2330900200039 0.1 0.7 0.1 0.1 0.1 0.03 2330900200040 0.1 0.25 0.1 0.1 0.01 0.15 2330900200041 0.01 0.1 2330900200042 ENDCOMMON 9 0 2330900200043 DATA 6 1 2330900200044 EN DATA ERR-T ERR-S MONIT MONIT-ERR 2330900200045 EV B PER-CENT PER-CENT B B 2330900200046 0.0253 534.6 1.0 0.35 37.4 0.15 2330900200047 ENDDATA 3 0 2330900200048 ENDSUBENT 47 0 2330900299999 SUBENT 23309003 20160921 22562330900300001 BIB 7 29 2330900300002 REACTION (92-U-235(N,F),,SIG) 2330900300003 SAMPLE 2.5 cm2 active area and ~2.6 ug/cm2 2330900300004 (92-U-234,ENR=0.00022) 2330900300005 (92-U-235,ENR=0.9993) 2330900300006 (92-U-236,ENR=0.000001) 2330900300007 (92-U-238,ENR=0.00048) 2330900300008 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 2330900300009 MONIT-REF (21255002,R.Vaninbroukx,J,NSE,24,87,1966) 2330900300010 DECAY-MON (27-CO-60-G,5.27YR) 2330900300011 ERR-ANALYS Standard deviation: 2330900300012 (ERR-T) Total (1.1%) 2330900300013 (ERR-S) Experimental error on count ratios R (0.20%) 2330900300014 (ERR-1) Alpha purity of fissile material (0.1%) 2330900300015 (ERR-2) 233U half-lives (0.7%) 2330900300016 (ERR-3) Mass analysis 235U/233U (0.5%) 2330900300017 (ERR-4) Weight of Co metal (0.1%) 2330900300018 (ERR-5) Purity of Co metal (0.1%) 2330900300019 (ERR-6) Preparation of Co solution (0.1%) 2330900300020 (ERR-7) 60Co decay correction (0.03%) 2330900300021 (ERR-8) Scaler accuracy (0.1%) 2330900300022 (ERR-9) Low geometry factor (0.25%) 2330900300023 (ERR-10) Alpha scintillation counting (0.2%) 2330900300024 (ERR-11) Neutron flux gradient (0.1%) 2330900300025 (ERR-12) Fission chamber efficiency (0.1%) 2330900300026 (ERR-13) Fission chamber background (0.01%) 2330900300027 (ERR-14) Fission chamber dead-time (0.15%) 2330900300028 (ERR-15) Neutron temperature and Cd ratio (0.1%) 2330900300029 (ERR-16) Systematic error in 60Co counting (0.1%) 2330900300030 STATUS (TABLE) Table 7 of J.Nucl.Energy 22(1968)477 2330900300031 ENDBIB 29 0 2330900300032 COMMON 16 9 2330900300033 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2330900300034 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2330900300035 ERR-13 ERR-14 ERR-15 ERR-16 2330900300036 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900300037 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900300038 PER-CENT PER-CENT PER-CENT PER-CENT 2330900300039 0.1 0.7 0.5 0.1 0.1 0.1 2330900300040 0.03 0.1 0.25 0.2 0.1 0.1 2330900300041 0.01 0.15 0.1 0.1 2330900300042 ENDCOMMON 9 0 2330900300043 DATA 6 1 2330900300044 EN DATA ERR-T ERR-S MONIT MONIT-ERR 2330900300045 EV B PER-CENT PER-CENT B B 2330900300046 0.0253 582.9 1.1 0.20 37.4 0.15 2330900300047 ENDDATA 3 0 2330900300048 ENDSUBENT 47 0 2330900399999 SUBENT 23309004 20160921 22562330900400001 BIB 7 25 2330900400002 REACTION (94-PU-239(N,F),,SIG) 2330900400003 SAMPLE 2.5 cm2 active area and ~0.7 ug/cm2 2330900400004 (94-PU-239,ENR=0.99996) 2330900400005 (94-PU-240,ENR=0.00003) 2330900400006 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 2330900400007 MONIT-REF (21255002,R.Vaninbroukx,J,NSE,24,87,1966) 2330900400008 DECAY-MON (27-CO-60-G,5.27YR) 2330900400009 ERR-ANALYS Standard deviation: 2330900400010 (ERR-T) Total (0.9%) 2330900400011 (ERR-S) Experimental error on count ratios R (0.40%) 2330900400012 (ERR-1) Alpha purity of fissile material (0.1%) 2330900400013 (ERR-2) 233U half-lives (0.2%) 2330900400014 (ERR-4) Weight of Co metal (0.1%) 2330900400015 (ERR-5) Purity of Co metal (0.1%) 2330900400016 (ERR-6) Preparation of Co solution (0.1%) 2330900400017 (ERR-7) 60Co decay correction (0.03%) 2330900400018 (ERR-8) Scaler accuracy (0.1%) 2330900400019 (ERR-9) Low geometry factor (0.25%) 2330900400020 (ERR-11) Neutron flux gradient (0.1%) 2330900400021 (ERR-12) Fission chamber efficiency (0.1%) 2330900400022 (ERR-13) Fission chamber background (0.01%) 2330900400023 (ERR-14) Fission chamber dead-time (0.15%) 2330900400024 (ERR-15) Neutron temperature and Cd ratio (0.4%) 2330900400025 (ERR-16) Systematic error in 60Co counting (0.1%) 2330900400026 STATUS (TABLE) Table 7 of J.Nucl.Energy 22(1968)477 2330900400027 ENDBIB 25 0 2330900400028 COMMON 14 9 2330900400029 ERR-1 ERR-2 ERR-4 ERR-5 ERR-6 ERR-7 2330900400030 ERR-8 ERR-9 ERR-11 ERR-12 ERR-13 ERR-14 2330900400031 ERR-15 ERR-16 2330900400032 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900400033 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900400034 PER-CENT PER-CENT 2330900400035 0.1 0.2 0.1 0.1 0.1 0.03 2330900400036 0.1 0.25 0.1 0.1 0.01 0.15 2330900400037 0.4 0.1 2330900400038 ENDCOMMON 9 0 2330900400039 DATA 6 1 2330900400040 EN DATA ERR-T ERR-S MONIT MONIT-ERR 2330900400041 EV B PER-CENT PER-CENT B B 2330900400042 0.0253 742.0 0.9 0.40 37.4 0.15 2330900400043 ENDDATA 3 0 2330900400044 ENDSUBENT 43 0 2330900499999 SUBENT 23309005 20160921 22562330900500001 BIB 3 12 2330900500002 REACTION ((92-U-233(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2330900500003 ERR-ANALYS Standard deviation: 2330900500004 (ERR-T) Total (0.7%) 2330900500005 (ERR-S) Experimental error on count ratios R (0.4%) 2330900500006 (ERR-1) Mass analysis 235U/233U (0.5%) 2330900500007 (ERR-2) Purity of fissile material (0.1%) 2330900500008 (ERR-3) 239Pu and 233U half-lives (0.0%) 2330900500009 (ERR-4) Alpha scintillation counting (0.2%) 2330900500010 (ERR-5) Neutron temperature and Cd ratio (0.1%) 2330900500011 STATUS (TABLE) Table 9 of J.Nucl.Energy 22(1968)477 2330900500012 (DEP,23309002) 233U(n,f) cross section 2330900500013 (DEP,23309003) 235U(n,f) cross section 2330900500014 ENDBIB 12 0 2330900500015 COMMON 5 3 2330900500016 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2330900500017 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900500018 0.5 0.1 0.0 0.2 0.1 2330900500019 ENDCOMMON 3 0 2330900500020 DATA 4 1 2330900500021 EN DATA ERR-T ERR-S 2330900500022 EV NO-DIM PER-CENT PER-CENT 2330900500023 0.0253 0.917 0.7 0.4 2330900500024 ENDDATA 3 0 2330900500025 ENDSUBENT 24 0 2330900599999 SUBENT 23309006 20160921 22562330900600001 BIB 3 12 2330900600002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-233(N,F),,SIG)) 2330900600003 ERR-ANALYS Standard deviation: 2330900600004 (ERR-T) Total (1.0%) 2330900600005 (ERR-S) Experimental error on count ratios R (0.5%) 2330900600006 (ERR-1) Mass analysis 235U/233U (0.0%) 2330900600007 (ERR-2) Purity of fissile material (0.1%) 2330900600008 (ERR-3) 239Pu and 233U half-lives (0.7%) 2330900600009 (ERR-4) Alpha scintillation counting (0.0%) 2330900600010 (ERR-5) Neutron temperature and Cd ratio (0.4%) 2330900600011 STATUS (TABLE) Table 9 of J.Nucl.Energy 22(1968)477 2330900600012 (DEP,23309002) 233U(n,f) cross section 2330900600013 (DEP,23309004) 239PU(n,f) cross section 2330900600014 ENDBIB 12 0 2330900600015 COMMON 5 3 2330900600016 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2330900600017 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900600018 0.0 0.1 0.7 0.0 0.4 2330900600019 ENDCOMMON 3 0 2330900600020 DATA 4 1 2330900600021 EN DATA ERR-T ERR-S 2330900600022 EV NO-DIM PER-CENT PER-CENT 2330900600023 0.0253 1.388 1.0 0.5 2330900600024 ENDDATA 3 0 2330900600025 ENDSUBENT 24 0 2330900699999 SUBENT 23309007 20180406 22662330900700001 BIB 4 13 2330900700002 REACTION ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2330900700003 ERR-ANALYS Standard deviation: 2330900700004 (ERR-T) Total (1.1%) 2330900700005 (ERR-S) Experimental error on count ratios R (0.5%) 2330900700006 (ERR-1) Mass analysis 235U/233U (0.5%) 2330900700007 (ERR-2) Purity of fissile material (0.1%) 2330900700008 (ERR-3) 239Pu and 233U half-lives (0.7%) 2330900700009 (ERR-4) Alpha scintillation counting (0.2%) 2330900700010 (ERR-5) Neutron temperature and Cd ratio (0.4%) 2330900700011 STATUS (TABLE) Table 9 of J.Nucl.Energy 22(1968)477 2330900700012 (DEP,23309002) 233U(n,f) cross section 2330900700013 (DEP,23309004) 239Pu(n,f) cross section 2330900700014 HISTORY (20180406U) On. STATUS corrected. 2330900700015 ENDBIB 13 0 2330900700016 COMMON 5 3 2330900700017 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2330900700018 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2330900700019 0.5 0.1 0.7 0.2 0.4 2330900700020 ENDCOMMON 3 0 2330900700021 DATA 4 1 2330900700022 EN DATA ERR-T ERR-S 2330900700023 EV NO-DIM PER-CENT PER-CENT 2330900700024 0.0253 1.273 1.1 0.5 2330900700025 ENDDATA 3 0 2330900700026 ENDSUBENT 25 0 2330900799999 ENDENTRY 7 0 2330999999999