ENTRY 22430 20220216 23092243000000001 SUBENT 22430001 20220216 23092243000100001 BIB 16 58 2243000100002 TITLE Measurement of the effective neutron capture cross 2243000100003 section of Cesium-134 by triple neutron capture 2243000100004 reaction method 2243000100005 AUTHOR (T.Katoh, S.Nakamura, H.Harada, Y.Hatsukawa, 2243000100006 N.Shinohara, K.Hata, K.Kobayashi,S.Motoishi, M.Tanase)2243000100007 INSTITUTE (2JPNJAE) Hatsukawa, Shinohara, Hata, Kabayashi, 2243000100008 Motoishi, Tanase 2243000100009 (2JPNPNC) Katoh, Nakamura, Harada 2243000100010 (2JPNGMT) Katoh 2243000100011 REFERENCE (J,NST,36,635,1999) Main ref. Data are given 2243000100012 ((S,JAERI-C-98-003,237,1998)= 2243000100013 (S,INDC(JPN)-180,237,1998)) Conf. Proc., data given 2243000100014 REL-REF (I,22295001,H.Harada+,J,NST,32,395,1995) Exp.detail 2243000100015 FACILITY (REAC,2JPNJAE) Swimming pool type reactor JRR-3 2243000100016 INC-SOURCE (REAC) HR-1 pipe of the reactor JRR-3 2243000100017 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG) Co/Al Alloy, 2243000100018 Co 0.46 wt% 2243000100019 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) Au/Al Alloy, 2243000100020 Au 0.112 wt% 2243000100021 DECAY-MON (27-CO-60-G,5.271YR,DG,1173.,0.9997, 2243000100022 DG,1333.,0.9999) 2243000100023 (79-AU-198-G,2.695D,DG,412.,0.955) 2243000100024 METHOD (ACTIV,CADMB,GSPEC) 2243000100025 DETECTOR (HPGE) High purity Ge detector with 90% efficiency 2243000100026 and an energy resolution of 2.1 keV FWHM at 1.33 MeV 2243000100027 gamma-energy of 60Co 2243000100028 INC-SPECT 1/E spectrum of the reactor, thermal neutron flux 2243000100029 8.68 x 10**13 n/cm2/sec,Westcott epithermal index 0.012243000100030 SAMPLE 1st monitor sample is Co/Al alloy wire (Co 0.46 wt%), 2243000100031 diameter 0.381 mm 2243000100032 2nd monitor sample is Au/Al alloy wire (Au 0.112 wt%),2243000100033 diameter 0.51 mm 2243000100034 ANALYSIS The amount of 135Cs was estimated by the activity 2243000100035 measurement of the 136Cs induced from 135Cs(n,g)136Cs 2243000100036 reaction, since 135Cs decays by a beta-transition, 2243000100037 it does not emit gamma-rays 2243000100038 Gamma-rays with energies of 796, 802, 819, 1039, 2243000100039 1048, 1168 and 1235 originated from 134Cs and 136Cs 2243000100040 nuclides induced by one- and triple-neutron capture 2243000100041 of 133Cs were used in this experiment 2243000100042 ERR-ANALYS (ERR-T) Total Error 2243000100043 (ERR-1) Error in the detection Efficiencies of gamma 2243000100044 (ERR-2) Error in the measurement of neutron field 2243000100045 (ERR-3,,0.1) Error from the Error of 133Cs cross-sect.2243000100046 (ERR-4) Error propagated from the error of cross-sec.2243000100047 value of 135Cs 2243000100048 (ERR-5) Error from 136Cs decay constants 2243000100049 (ERR-6) Error from the emission probabilities of 2243000100050 gamma-rays 2243000100051 (ERR-S) Statistical error 2243000100052 HISTORY (19991203C) + + Compiled by S.M. + + 2243000100053 (20010709A) . . Corrected by S.M. 2243000100054 (20011009U) Last checking has been done. 2243000100055 (20140108U) SD: Author's list was updated. Minor 2243000100056 corrections. 2243000100057 (20180316A) SD: REACTION code corrected in Subent 002. 2243000100058 (20220216U) SD: Year of the JAERI-C-98-003,237 ref. 2243000100059 updated (1997 -> 1998). 2243000100060 ENDBIB 58 0 2243000100061 COMMON 8 6 2243000100062 ERR-S ERR-1 ERR-2 ERR-4 ERR-5 ERR-6 2243000100063 MONIT1 MONIT2 2243000100064 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2243000100065 B B 2243000100066 4.5 2. 2.4 3.6 0.2 1.2243000100067 37.18 98.65 2243000100068 ENDCOMMON 6 0 2243000100069 ENDSUBENT 68 0 2243000199999 SUBENT 22430002 20180316 22702243000200001 BIB 8 36 2243000200002 REACTION (55-CS-134(N,G)55-CS-135,,SIG,,SPA) Effective Cross 2243000200003 Section Equal to Sig0*(1+R*SQRT(T/T0)*S0*G-EPI) 2243000200004 DECAY-DATA (55-CS-134-G,2.062YR,DG,563.,0.0835, 2243000200005 DG,569.,0.1543, 2243000200006 DG,605.,0.9756, 2243000200007 DG,796.,0.8544, 2243000200008 DG,802.,0.0873, 2243000200009 DG,1039.,0.01, 2243000200010 DG,1168.,0.1805) 2243000200011 (55-CS-135-G,2.3E+6YR) 2243000200012 (55-CS-136-G,13.16D,DG,819.,0.998, 2243000200013 DG,1048.,0.798, 2243000200014 DG,1235.,0.198) 2243000200015 REL-REF (R,22469001,S.Nakamura+,J,NST,36,847,199910) Data 2243000200016 for Cs-133 2243000200017 (R,,K.Shibata+,S,JAERI-D-97-003,1997) Data for CS-136 2243000200018 ASSUMED (ASSUM1,55-CS-133(N,G)55-CS-134,,SIG,,MXW) 2243000200019 (ASSUM2,55-CS-135(N,G)55-CS-136,,SIG,,MXW) 2243000200020 (ASSUM3,55-CS-136(N,G)55-CS-137,,SIG,,MXW) 2243000200021 (ASSUM4,55-CS-133(N,G)55-CS-134,,RI) 2243000200022 (ASSUM5,55-CS-135(N,G)55-CS-136,,RI) 2243000200023 MISC-COL (MISC) (55-CS-136(N,G)55-CS-137,,RI) 2243000200024 SAMPLE .Natural CsCl sample, purity 99.99% in 133Cs was used 2243000200025 as target, weight Near 2 microgram sealed in a quartz 2243000200026 tube 4 mm inner diameter, 50 mm length. Then the 134Cs2243000200027 nuclei were obtained by triple neutron irradiation of 2243000200028 133Cs to make the amount of 134Cs nuclei definite. 2243000200029 These 134Cs nuclei were used as sample for the 2243000200030 134Cs(n,g)135Cs reaction. 2243000200031 STATUS (TABLE) Table 5 of Nucl.Sci.Tech.,36(1999)635 2243000200032 .Corrections are taken from NST,36,635,1999 2243000200033 HISTORY (20010709A) Decay-Data and Assumed Values Added 2243000200034 Reaction Code Changed 2243000200035 (20011009U) Last checking has been done. 2243000200036 (20180316A) SD: Sum of reactions re-coded as one 2243000200037 according to remark from N.Otsuka.EN-MIN -> EN-DUMMY. 2243000200038 ENDBIB 36 0 2243000200039 COMMON 10 6 2243000200040 ASSUM1 ASSUM1-ERR ASSUM2 ASSUM2-ERR ASSUM3 ASSUM4 2243000200041 ASSUM4-ERR ASSUM5 ASSUM5-ERR MISC 2243000200042 B B B B B B 2243000200043 B B B B 2243000200044 29. 1.1 8.3 0.3 13. 298. 2243000200045 16. 39.7 2.7 57.22 2243000200046 ENDCOMMON 6 0 2243000200047 DATA 3 1 2243000200048 EN-DUMMY DATA ERR-T 2243000200049 EV B B 2243000200050 2.53E-02 140.6 8.5 2243000200051 ENDDATA 3 0 2243000200052 ENDSUBENT 51 0 2243000299999 ENDENTRY 2 0 2243099999999