ENTRY 23569 20200415 22872356900000001 SUBENT 23569001 20200415 22872356900100001 BIB 11 28 2356900100002 TITLE The ratio of asymmetric to symmetric fission in p-wave2356900100003 neutron fission of U235 2356900100004 AUTHOR (J.G.Cuninghame, G.P.Kitt, E.R.Rae) 2356900100005 REFERENCE (J,NP,27,154,1961) 2356900100006 INSTITUTE (2UK HAR) 2356900100007 REL-REF (R,,S.Katcoff+,J,NUC,16,(4),78,1958) 2356900100008 DETECTOR (PROPC) Methane-flow proportional counters with 2356900100009 0.7 mg/cm2 thick windows as alpha and beta counters. 2356900100010 Counting time - 15 d for Mo, 45 d for Zr, 60 d for Ag, 2356900100011 90 d for Cd. 2356900100012 METHOD (CHSEP) Irradiation time 2 hr for each run. 2356900100013 CORRECTION Conversion of counts to count rate at the end of 2356900100014 irradiation. 2356900100015 For chemical yield. 2356900100016 Absorption correction. 2356900100017 ANALYSIS Directly measured ( practical) ratio values were 2356900100018 compared with "true" values for thermal fission 2356900100019 obtained either directly or by interpolation from 2356900100020 ref. of S.Katcoff, and "counting factor" was obtained 2356900100021 for any pair of nuclides. This factor was used to 2356900100022 obtain "true value" of ratio. 2356900100023 Thermal fission yields used are given in ASSUMED 2356900100024 ASSUMED (ASSUM1,92-U-235(N,F)40-ZR-97,CUM,FY,,MXW) 2356900100025 (ASSUM2,92-U-235(N,F)42-MO-99,CUM,FY,,MXW) 2356900100026 (ASSUM3,92-U-235(N,F)47-AG-113,CUM,FY,,MXW) 2356900100027 (ASSUM4,92-U-235(N,F)48-CD-115-G,CUM,FY,,MXW) 2356900100028 At thermal energy. 2356900100029 HISTORY (20200415C) M.M. 2356900100030 ENDBIB 28 0 2356900100031 COMMON 4 3 2356900100032 ASSUM1 ASSUM2 ASSUM3 ASSUM4 2356900100033 PC/FIS PC/FIS PC/FIS PC/FIS 2356900100034 5.9 6.06 0.011 0.0097 2356900100035 ENDCOMMON 3 0 2356900100036 ENDSUBENT 35 0 2356900199999 SUBENT 23569002 20200415 22872356900200001 BIB 7 17 2356900200002 REACTION ((92-U-235(N,F)42-MO-99,CUM,FY,,MXW)/ 2356900200003 (92-U-235(N,F)47-AG-112,CUM,FY,,MXW)) 2356900200004 FACILITY BEPO pneumatic irradiation tube (Au/CD ratio ~3) and 2356900200005 BEPO thermal column (Au/Cd ratio ~600) 2356900200006 (REAC,2UK HAR) 2356900200007 INC-SPECT Thermal neutron energy 2356900200008 SAMPLE Natural uranyl nitrate of ~0.2 mg at pneumatic tube. 2356900200009 Natural UO(2) of ~0.5 g and U-235 metal of ~150 mg at 2356900200010 thermal column. 2356900200011 ANALYSIS The 12 "practical" values of ratio 2356900200012 59.2+-0.38, 58.9+-0.39, 57.2+-0.42, 59.3+-0.37, 2356900200013 59.8+-0.56, 58.1+-0.45, 58.2+-0.45, 56.7+-1.53, 2356900200014 55.7+-0.25, 58.0+-0.33, 58.4+-0.17, 58.6+-0.22 2356900200015 were used to obtain mean value 58.2+-1.12. 2356900200016 By "counting factor" the "true" value was calculated. 2356900200017 ERR-ANALYS (DATA-ERR) Standard deviation 2356900200018 STATUS (TABLE) Table 1 of Nuclear Physics,v.27,p.154,1961 2356900200019 ENDBIB 17 0 2356900200020 NOCOMMON 0 0 2356900200021 DATA 3 1 2356900200022 EN-DUMMY DATA DATA-ERR 2356900200023 EV NO-DIM NO-DIM 2356900200024 0.0253 551. 11. 2356900200025 ENDDATA 3 0 2356900200026 ENDSUBENT 25 0 2356900299999 SUBENT 23569003 20200415 22872356900300001 BIB 7 9 2356900300002 REACTION ((92-U-235(N,F)42-MO-99,CUM,FY)/ 2356900300003 (92-U-235(N,F)47-AG-112,CUM,FY)) 2356900300004 FACILITY (VDG,2UK ALD) 2356900300005 INC-SOURCE (P-T) Protons on to water-cooled Zr tritide target 2356900300006 SAMPLE U-235 metal of ~5 g 2356900300007 ANALYSIS One run - "practical value" - 101+-16, 2356900300008 By "counting factor" the "true" value was calculated. 2356900300009 ERR-ANALYS (DATA-ERR) Standard deviation 2356900300010 STATUS (TABLE) Table 1 of Nuclear Physics,v.27,p.154,1961 2356900300011 ENDBIB 9 0 2356900300012 NOCOMMON 0 0 2356900300013 DATA 5 1 2356900300014 EN +EN-ERR -EN-ERR DATA DATA-ERR 2356900300015 KEV KEV KEV NO-DIM NO-DIM 2356900300016 65. 30. 25. 956. 186. 2356900300017 ENDDATA 3 0 2356900300018 ENDSUBENT 17 0 2356900399999 SUBENT 23569004 20200415 22872356900400001 BIB 7 15 2356900400002 REACTION ((92-U-235(N,F)42-MO-99,CUM,FY)/ 2356900400003 (92-U-235(N,F)47-AG-112,CUM,FY)) 2356900400004 FACILITY (VDG,2UK HAR) 2356900400005 (VDG,2UK ALD) 2356900400006 INC-SOURCE (P-LI7) Tin (10 keV) Li targets 2356900400007 SAMPLE U-235 oxide UO(3) of ~5.5 g at AERE ; 2356900400008 U-235 oxide UO(3) of ~5.5 g and U-235 metal of ~ 5 g 2356900400009 at AWRE. 2356900400010 ANALYSIS The 7 "practical" values of ratio 2356900400011 107.6+-7.3, 86.6+-4.1, 86.3+-4.6, 73.4+-5.9, 2356900400012 70.5+-11.7,86.6+-4.1, 86.3+-4.6 2356900400013 were used to obtain mean value 84.8+-11.1 . 2356900400014 By "counting factor" the "true" value was calculated. 2356900400015 ERR-ANALYS (DATA-ERR) Standard deviation 2356900400016 STATUS (TABLE) Table 1 of Nuclear Physics,v.27,p.154,1961 2356900400017 ENDBIB 15 0 2356900400018 NOCOMMON 0 0 2356900400019 DATA 5 1 2356900400020 EN +EN-ERR -EN-ERR DATA DATA-ERR 2356900400021 KEV KEV KEV NO-DIM NO-DIM 2356900400022 125. 8. 25. 803. 107. 2356900400023 ENDDATA 3 0 2356900400024 ENDSUBENT 23 0 2356900499999 SUBENT 23569005 20200415 22872356900500001 BIB 7 10 2356900500002 REACTION ((92-U-235(N,F)42-MO-99,CUM,FY)/ 2356900500003 (92-U-235(N,F)47-AG-112,CUM,FY)) 2356900500004 FACILITY (VDG,2UK HAR) 2356900500005 (VDG,2UK ALD) 2356900500006 INC-SOURCE (P-LI7) Tin (10 keV) Li targets 2356900500007 SAMPLE U-235 metal of ~5 g . 2356900500008 ANALYSIS One run - "practical" value - 48.4+-7.5 2356900500009 By "counting factor" the "true" value was calculated. 2356900500010 ERR-ANALYS (DATA-ERR) Standard deviation 2356900500011 STATUS (TABLE) Table 1 of Nuclear Physics,v.27,p.154,1961 2356900500012 ENDBIB 10 0 2356900500013 NOCOMMON 0 0 2356900500014 DATA 5 1 2356900500015 EN +EN-ERR -EN-ERR DATA DATA-ERR 2356900500016 KEV KEV KEV NO-DIM NO-DIM 2356900500017 200. 5. 30. 458. 87. 2356900500018 ENDDATA 3 0 2356900500019 ENDSUBENT 18 0 2356900599999 SUBENT 23569006 20200415 22872356900600001 BIB 7 14 2356900600002 REACTION ((92-U-235(N,F)42-MO-99,CUM,FY)/ 2356900600003 (92-U-235(N,F)47-AG-112,CUM,FY)) 2356900600004 FACILITY 1(VDG,2UK HAR) 2356900600005 2(CCW,2UK ALD) 2356900600006 INC-SOURCE1(P-LI7) Tin (10 keV) Li targets for 300 keV neutrons, 2356900600007 40-keV Li target for 540 and 100 keV neutrons. 2356900600008 2(D-T) 2356900600009 SAMPLE U-235 oxide UO(3) of ~5.5 g . 2356900600010 ANALYSIS One run for each energy, "practical" values of ratio 2356900600011 48.8+-3.2, 41.4+-0.7,42.7+-1.2, 0.456+-0.001, 2356900600012 respectively for 300., 540., 1000., 14000 keV. 2356900600013 By "counting factor" the "true" value was calculated. 2356900600014 ERR-ANALYS (DATA-ERR) Standard deviation 2356900600015 STATUS (TABLE) Table 1 of Nuclear Physics,v.27,p.154,1961 2356900600016 ENDBIB 14 0 2356900600017 NOCOMMON 0 0 2356900600018 DATA 5 4 2356900600019 EN +EN-ERR -EN-ERR DATA DATA-ERR 2356900600020 KEV KEV KEV NO-DIM NO-DIM 2356900600021 300. 8. 42. 458. 59. 2356900600022 540. 20. 65. 392. 44. 2356900600023 1000. 20. 87. 404. 46. 2356900600024 14000. 4.41 0.48 2356900600025 ENDDATA 6 0 2356900600026 ENDSUBENT 25 0 2356900699999 SUBENT 23569007 20200415 22872356900700001 BIB 7 11 2356900700002 REACTION ((92-U-235(N,F)40-ZR-97,CUM,FY,,MXW)/ 2356900700003 (92-U-235(N,F)42-MO-99,CUM,FY,,MXW)) 2356900700004 INC-SOURCE (THCOL) Thermal column at Harwell 2356900700005 INC-SPECT Thermal neutron energy 2356900700006 SAMPLE Natural UO(3) of ~0.6 g . 2356900700007 ANALYSIS The 4 "practical" values of ratio 2356900700008 7.81+-0.012, 7.75+-0.015, 7.85+-0.023, 7.82+-0.015 2356900700009 were used to obtain mean value 7.81+-0.04 . 2356900700010 By "counting factor" the "true" value was calculated. 2356900700011 ERR-ANALYS (DATA-ERR) Standard deviation 2356900700012 STATUS (TABLE) Table 2 of Nuclear Physics,v.27,p.154,1961 2356900700013 ENDBIB 11 0 2356900700014 NOCOMMON 0 0 2356900700015 DATA 3 1 2356900700016 EN-DUMMY DATA DATA-ERR 2356900700017 EV NO-DIM NO-DIM 2356900700018 0.0253 0.974 0.005 2356900700019 ENDDATA 3 0 2356900700020 ENDSUBENT 19 0 2356900799999 SUBENT 23569008 20200415 22872356900800001 BIB 6 11 2356900800002 REACTION ((92-U-235(N,F)40-ZR-97,CUM,FY)/ 2356900800003 (92-U-235(N,F)42-MO-99,CUM,FY)) 2356900800004 FACILITY (VDG,2UK HAR) 2356900800005 (VDG,2UK ALD) 2356900800006 SAMPLE U-235 oxide UO(3) of ~5 g 2356900800007 ANALYSIS Two "practical" values of ratio 2356900800008 9.01+-0.075, 8.25+-0.035 2356900800009 were used to obtain mean value 8.63+-0.38 . 2356900800010 By "counting factor" the "true" value was calculated. 2356900800011 ERR-ANALYS (DATA-ERR) Standard deviation 2356900800012 STATUS (TABLE) Table 2 of Nuclear Physics,v.27,p.154,1961 2356900800013 ENDBIB 11 0 2356900800014 NOCOMMON 0 0 2356900800015 DATA 5 1 2356900800016 EN +EN-ERR -EN-ERR DATA DATA-ERR 2356900800017 KEV KEV KEV NO-DIM NO-DIM 2356900800018 125. 8. 25. 1.08 0.05 2356900800019 ENDDATA 3 0 2356900800020 ENDSUBENT 19 0 2356900899999 SUBENT 23569009 20200415 22872356900900001 BIB 7 11 2356900900002 REACTION ((92-U-235(N,F)40-ZR-97,CUM,FY,,MXW)/ 2356900900003 (92-U-235(N,F)48-CD-115-G,CUM,FY)) 2356900900004 INC-SOURCE (THCOL) Thermal column at Harwell 2356900900005 INC-SPECT Thermal neutron energy 2356900900006 SAMPLE Natural UO(3) of ~0.6 g . 2356900900007 ANALYSIS The 4 "practical" values of ratio 2356900900008 270.+-1.2, 278.+-1.6,276.+-1.9,275.+-1.9 2356900900009 were used to obtain mean value 275.+-3.5. 2356900900010 By "counting factor" the "true" value was calculated. 2356900900011 ERR-ANALYS (DATA-ERR) Standard deviation 2356900900012 STATUS (TABLE) Table 2 of Nuclear Physics,v.27,p.154,1961 2356900900013 ENDBIB 11 0 2356900900014 NOCOMMON 0 0 2356900900015 DATA 3 1 2356900900016 EN-DUMMY DATA DATA-ERR 2356900900017 EV NO-DIM NO-DIM 2356900900018 0.0253 625. 8. 2356900900019 ENDDATA 3 0 2356900900020 ENDSUBENT 19 0 2356900999999 SUBENT 23569010 20200415 22872356901000001 BIB 6 11 2356901000002 REACTION ((92-U-235(N,F)40-ZR-97,CUM,FY)/ 2356901000003 (92-U-235(N,F)48-CD-115-G,CUM,FY)) 2356901000004 FACILITY (VDG,2UK HAR) 2356901000005 (VDG,2UK ALD) 2356901000006 SAMPLE U-235 oxide UO(3) of ~5 g 2356901000007 ANALYSIS Two "practical" values of ratio 2356901000008 350.+-14., 362.+-35. 2356901000009 were used to obtain mean value 356.+-26. . 2356901000010 By "counting factor" the "true" value was calculated. 2356901000011 ERR-ANALYS (DATA-ERR) Standard deviation 2356901000012 STATUS (TABLE) Table 2 of Nuclear Physics,v.27,p.154,1961 2356901000013 ENDBIB 11 0 2356901000014 NOCOMMON 0 0 2356901000015 DATA 5 1 2356901000016 EN +EN-ERR -EN-ERR DATA DATA-ERR 2356901000017 KEV KEV KEV NO-DIM NO-DIM 2356901000018 125. 8. 25. 809. 61. 2356901000019 ENDDATA 3 0 2356901000020 ENDSUBENT 19 0 2356901099999 ENDENTRY 10 0 2356999999999