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