ENTRY 22174 20060204 20060525 21762217400000001 SUBENT 22174001 20060204 20060525 21762217400100001 BIB 17 48 2217400100002 REFERENCE (J,NST,27,(6),577,199006) 2217400100003 TITLE -Measurement of Thermal Neutron Cross Section of 2217400100004 137-Cs(N,G)138-Cs Reaction. 2217400100005 AUTHOR (H.Harada,H.Watanabe,T.Sekine,Y.Hatsukawa,K.Kobayashi, 2217400100006 T.Katoh) 2217400100007 INSTITUTE (2JPNPNC) H.H., H.W. 2217400100008 (2JPNJAE) T.S., Y.H., K.K. And Experimental Site 2217400100009 (2JPNNAG) T.K. 2217400100010 FACILITY (REAC,2JPNJAE) Swimming-Pool-Type JRR-4 Reactor 2217400100011 INC-SOURCE (REAC ) 2217400100012 INC-SPECT .Sample irradiated in the T-pipe of the reactor, giving2217400100013 a thermal N-flux 4.0E+13 n/cm2/s and an epithermal 2217400100014 index in the Westcott convention of 0.02. 2217400100015 SAMPLE . 3.0 micro-l of CsCl solution containing 0.1 MBq of 2217400100016 137Cs evaporated to dryness in a small polyethylene 2217400100017 bottle, which was sealed and then placed in a poly- 2217400100018 ethylene capsule with a flux-monitor wire of 0.475 W/O2217400100019 Co/Al alloy 0.76 mm in diameter. 2217400100020 METHOD (ACTIV) Irradiation time 10 min 2217400100021 (CHSEP) Cs separated from 24Na and 38Cl activity by 2217400100022 absorbing it onto 2 mg of Zeolite and filtering off. 2217400100023 DETECTOR (HPGE ) 2.3 keV energy resolution at 1.3 MeV. Counting 2217400100024 efficiency measured with a calibrated multi-gamma 2217400100025 source. 2217400100026 MONITOR (27-CO-59(N,G)27-CO-60,,SIG,,MXW) 2217400100027 DECAY-MON (27-CO-60-G,5.271YR,DG,1173.,1.0, 2217400100028 DG,1332.,1.0) 2217400100029 DECAY-DATA (55-CS-137,30.17YR,DG,662.,0.85) 2217400100030 (55-CS-138-G,33.4MIN,DG,1010.,0.284, 2217400100031 DG,1436.,0.750, 2217400100032 DG,2218.,0.161) 2217400100033 CORRECTION .Corrected for sum coincidence loss. 2217400100034 .Dead time correction not necessary because only ratio 2217400100035 of counts considered in analysis. 2217400100036 ERR-ANALYS (DATA-ERR) Does not include the errors in gamma 2217400100037 emission probabilities and decay constants. 2217400100038 Uncertainties in detector counting efficiencies 2217400100039 estimated to be 5 %. 2217400100040 STATUS .Data Taken from Main Reference. 2217400100041 HISTORY (19910515C) S.W. 2217400100042 (19910523E) 2217400100043 (19910716A) S.W. Half-Life Explanation Added, Data 2217400100044 Corrected in Subent 002 2217400100045 (19910722E) 2217400100046 (20000503A) Corrected by S.M. Reference and Subentry 2217400100047 Added. Dates Corrected 2217400100048 (20060204A) Corrected SM. One reference and 2217400100049 SUBENT 22174003 deleted 2217400100050 ENDBIB 48 0 2217400100051 COMMON 1 3 2217400100052 MONIT 2217400100053 B 2217400100054 3.718E+01 2217400100055 ENDCOMMON 3 0 2217400100056 ENDSUBENT 55 0 2217400199999 SUBENT 22174002 20060204 20060525 21762217400200001 BIB 5 17 2217400200002 REACTION (55-CS-137(N,G)55-CS-138,,SIG,,SPA) Averaged over 2217400200003 thermal and epithermal neutron spectrum 2217400200004 ANALYSIS .Cross section calculated from the intensity ratio of 2217400200005 each of the three 138Cs gammas to the 662 keV gamma 2217400200006 of 137Cs. Data is weighted mean of four runs, giving 2217400200007 12 cross sections. 2217400200008 INC-SPECT .Epithermal components contributes 2% 2217400200009 STATUS .Data Taken from Main Reference. 2217400200010 (COREL,22737002) 2217400200011 (COREL,22738002) 2217400200012 (COREL,22649005) 2217400200013 HISTORY (19910515C) S.W. 2217400200014 (19910523E) 2217400200015 (19910716A) S.W. Data Corrected 2217400200016 (19910722E) 2217400200017 (20000503U) DATA-ERR Corrected 2217400200018 (20060204A) REACTION SF8 and Data-Err corrected 2217400200019 ENDBIB 17 0 2217400200020 NOCOMMON 0 0 2217400200021 DATA 3 1 2217400200022 EN-DUMMY DATA DATA-ERR 2217400200023 EV B B 2217400200024 2.53E-02 0.250 0.013 2217400200025 ENDDATA 3 0 2217400200026 ENDSUBENT 25 0 2217400299999 NOSUBENT 22174003 20060204 20060525 21762217400300001 ENDENTRY 3 0 2217499999999