ENTRY 20459 20160907 22522045900000001 SUBENT 20459001 20160907 22522045900100001 BIB 15 31 2045900100002 INSTITUTE (2UK HAR) 2045900100003 REFERENCE (J,JIN,33,3972,197111) 2045900100004 REL-REF (O,12365001,M.J.Cabell+,J,JNE/AB,16,195,1962) prev. 2045900100005 measurements. 2045900100006 AUTHOR (M.J.Cabell, M.Wilkins) 2045900100007 TITLE The thermal neutron capture cross-section of U-233 2045900100008 FACILITY (SPECM,2UK HAR) AEI type MS5 mass spectrometer. 2045900100009 INC-SOURCE DIDO reactor. 2-year irradiation in the 2045900100010 graphite reflector. 2045900100011 INC-SPECT Essentially thermal spectrum. Westcott epith. index 2045900100012 (R=(7.5+-1.0)*E-04, temperature=116+-9 deg-C.) 2045900100013 SAMPLE U-233 (99.76%) and U-236 (99.76%) mounted on 2045900100014 very pure precipitated silica. 2045900100015 Irradiated U was separated from fiss.prod. by reverse 2045900100016 phase partition chromatography. 2045900100017 METHOD Mass spectrometer analysis after 2 year irradiation. 2045900100018 ANALYSIS Westcott formalism. 2045900100019 MONITOR (92-U-236(N,G)92-U-237,,SIG,,MXW) 2045900100020 = 6.4+-1.0 b, BNL-325,2-nd ed.(1965) 2045900100021 ERR-ANALYS (ERR-T) Total uncertainty 2045900100022 (ERR-S) Random error 2045900100023 (ERR-1) Uncertainty in g-values of U-235 for abcorption2045900100024 and fission 2045900100025 (ERR-2) Uncertainty in variation of g(T) from various 2045900100026 data sets 2045900100027 (ERR-3) Uncertainty in resonance integrals of U-233 for2045900100028 absorption and fission, etc. 2045900100029 STATUS (TABLE) Data from the publication. 2045900100030 HISTORY (19720221C) 2045900100031 (20160907A) SD:Updated to new date formats,lower case. 2045900100032 ERR-ANALYS update. Ref. JNE/AB,16,195 moved to REL-REF.2045900100033 ENDBIB 31 0 2045900100034 COMMON 3 3 2045900100035 ERR-1 ERR-2 ERR-3 2045900100036 B B B 2045900100037 1.27 0.90 0.08 2045900100038 ENDCOMMON 3 0 2045900100039 ENDSUBENT 38 0 2045900199999 SUBENT 20459002 20160907 22522045900200001 BIB 2 5 2045900200002 REACTION (92-U-233(N,G)92-U-234,,SIG) 2045900200003 COMMENT Capture cross-section for 2200 m/sec neutrons is 2045900200004 derived from the effective capture cross-sections 2045900200005 of 48.69 +- 0.14 b in the reactor spectrum, using the 2045900200006 Westcott values of g and r*s. 2045900200007 ENDBIB 5 0 2045900200008 NOCOMMON 0 0 2045900200009 DATA 4 1 2045900200010 EN DATA ERR-T ERR-S 2045900200011 MEV B B B 2045900200012 2.5300E-08 48.35 1.62 0.14 2045900200013 ENDDATA 3 0 2045900200014 ENDSUBENT 13 0 2045900299999 ENDENTRY 2 0 2045999999999