ENTRY 21186 20090315 22082118600000001 SUBENT 21186001 20090315 22082118600100001 BIB 12 26 2118600100002 INSTITUTE (2UK HAR) 2118600100003 REFERENCE (J,JNE,4,409,1957) 2118600100004 AUTHOR (T.S.Green,V.G.Small,D.E.Glanville) 2118600100005 TITLE -The thermal neutron absorption cross-section of U-233 2118600100006 FACILITY (OSCIP) Pile oscillator. 2118600100007 INC-SOURCE (REAC ) Bepo reactor at aere . 2118600100008 SAMPLE .Solution of U-O2-so4 in d2-O using U-233. Solutions 2118600100009 contained in Pt-Fe cans and sealed in welded 2118600100010 aluminium containers. 2118600100011 .Solution of boric acid in d2-O for comparison 2118600100012 measurement. 2118600100013 METHOD .Comparison of flux modulation of oscillated sample 2118600100014 with that of gold. 2118600100015 DETECTOR (BF3) Boron chamber with cylindrical hole along its 2118600100016 axis. 2118600100017 Boron thermocouple to measure relative neutron 2118600100018 flux at various points along the chamber axis, 2118600100019 absolutely calibrated using gold activation. 2118600100020 PART-DET (N) Reactor neutrons. 2118600100021 STATUS (NDD) From neudada 2118600100022 HISTORY (19791119T) 2118600100023 (19800110E) 2118600100024 (20070926A) Date is corrected 2118600100025 (20090218A) (n,g) changed to (n,abs) for U-233 in 2118600100026 subent 002 2118600100027 (20090315U) Last checking has been done. 2118600100028 ENDBIB 26 0 2118600100029 NOCOMMON 0 0 2118600100030 ENDSUBENT 29 0 2118600199999 SUBENT 21186002 20090315 22082118600200001 BIB 6 23 2118600200002 REACTION 1((92-U-233(N,ABS),,SIG,,MXW)/ 2118600200003 (5-B-0(N,G),,SIG,,MXW)) 2118600200004 2((92-U-233(N,ABS),,SIG,,MXW)/ 2118600200005 (79-AU-197(N,G)79-AU-198-G,,SIG,,MXW)) 2118600200006 3(92-U-233(N,ABS),,SIG,,MXW) 2118600200007 MONITOR 2((5-B-0(N,ABS),,SIG,,MXW)/ 2118600200008 (79-AU-197(N,G)79-AU-198-G,,SIG,,MXW)) 2118600200009 Measured in BEPO oscillator using same B2-O3 in 2118600200010 D2-O specimen as used here. 2118600200011 3(79-AU-197(N,G)79-AU-198-G,,SIG,,MXW) 2118600200012 STATUS .Data from text of publication. 2118600200013 CORRECTION .Correction for the effect of fission neutrons from 2118600200014 U-233 on the pile. 2118600200015 ERR-ANALYS (ERR-1) Uncertainty in U-233 effective cross-sections 2118600200016 1.6% 2118600200017 (ERR-2) Uncertainty in U-233 effective cross-sections 2118600200018 due to determination of corrections for 2118600200019 fission netrons. 2118600200020 1.3% 2118600200021 HISTORY (20070926A) Ratio to data changed. 2118600200022 (n,abs) changed to (n,g) 2118600200023 (20090218A) (n,g) changed to (n,abs) for U-233 2118600200024 (20090315U) Last checking has been done. 2118600200025 ENDBIB 23 0 2118600200026 COMMON 6 3 2118600200027 EN-DUMMY MONIT 2MONIT-ERR 2MONIT 3ERR-1 ERR-2 2118600200028 EV NO-DIM PER-CENT B PER-CENT PER-CENT 2118600200029 2.53E-02 7.95 1. 9.86E+01 1.6 1.32118600200030 ENDCOMMON 3 0 2118600200031 DATA 5 1 2118600200032 DATA 1DATA-ERR 1DATA 2DATA 3DATA-ERR 3 2118600200033 NO-DIM NO-DIM NO-DIM B B 2118600200034 7.38E-01 2.2E-02 5.87 5.78E+02 1.7E+01 2118600200035 ENDDATA 3 0 2118600200036 ENDSUBENT 35 0 2118600299999 ENDENTRY 2 0 2118699999999