ENTRY 31631 20160929 31753163100000001
SUBENT 31631001 20160929 31753163100100001
BIB 13 34 3163100100002
TITLE Measurement of thermal neutron cross sections of the 3163100100003
reactions 126Sn(n,gamma)127g,127mSn 3163100100004
AUTHOR (Sheng-Dong Zhang,Lei Yang,Jingru Guo,Fangding Wang, 3163100100005
An-Zhi Cui,Lijun Diao) 3163100100006
INSTITUTE (3CPRAEP) 3163100100007
REFERENCE (J,RCA,94,385,2006) 3163100100008
FACILITY (REAC,3CPRAEP) 3163100100009
SAMPLE About 4-10 Bq of 126Sn carried by PbS precipitate 3163100100010
was used as target, because PbS does not produce any 3163100100011
gamma-emitting nuclide on irradiation, and can 3163100100012
co-precipitate 126Sn completely. The PbS (126Sn) was 3163100100013
deposited on the bottom of the polyethylene box as a 3163100100014
thin layer. The polyethylene box was sealed and 3163100100015
housed in an Al can together with the neutron flux 3163100100016
monitors 197Au and 55Mn. 3163100100017
The number of the 126Sn atoms in the samples were 3163100100018
determined by the activities of the 126Sn beta-decay 3163100100019
product Sb-126m and Sb-126g. The sample was aged for 753163100100020
days to reach secular equilibrium. 3163100100021
INC-SOURCE The thermal neutron fluxes of three irradiation runs 3163100100022
were found to be 2.09x10**13 n/cm2/s, 1.77x10**13 3163100100023
n/cm2/s and 2.02x10**13 n/cm2/s, respectively, by 3163100100024
using the neutron activation equation. 3163100100025
DETECTOR (HPGE) 3163100100026
METHOD (ACTIV,GSPEC,CHSEP) 3163100100027
MONITOR (79-AU-197(N,G)79-AU-198,,SIG) - Neutron flux monitor 3163100100028
(25-MN-55(N,G)25-MN-56,,SIG) - Neutron flux monitor 3163100100029
DECAY-MON (79-AU-198-G,2.69D,DG,411.8,0.947) 3163100100030
(25-MN-56,2.578HR,DG,846.7,0.989) 3163100100031
STATUS (TABLE) from the abstract. 3163100100032
HISTORY (20080724C) SD 3163100100033
(20160923A) VS. SF8=SPA deleted in 002-004; 3163100100034
EN-DUMMY->EN; DECAY-DATA corrected in 002 and 004; 3163100100035
ERR-ANALYS modified 002-003. 3163100100036
ENDBIB 34 0 3163100100037
COMMON 1 3 3163100100038
EN 3163100100039
EV 3163100100040
0.0253 3163100100041
ENDCOMMON 3 0 3163100100042
ENDSUBENT 41 0 3163100199999
SUBENT 31631002 20160929 31753163100200001
BIB 6 13 3163100200002
REACTION (50-SN-126(N,G)50-SN-127-M,,SIG) 3163100200003
DECAY-DATA (50-SN-127-M,4.13MIN) 3163100200004
(51-SB-127,3.85D,DG,473.2,0.248,DG,684.9,0.368, 3163100200005
DG,782.6,0.15) 3163100200006
(50-SN-127-G,2.10HR) 3163100200007
RAD-DET (51-SB-127,DG) 3163100200008
ERR-ANALYS (ERR-T) The largest uncertainty comes from the average 3163100200009
deviation in two irradiated targets. 3163100200010
(ERR-1,2.6,2.8) error in 127Sb radioactivity 3163100200011
(ERR-2,2.0,4.7) error of the thermal neutron flux 3163100200012
STATUS (DEP,31631003) 3163100200013
HISTORY (20160923A) VS. SF8=SPA deleted; DECAY-DATA corrected; 3163100200014
ERR-ANALYS modified. 3163100200015
ENDBIB 13 0 3163100200016
NOCOMMON 0 0 3163100200017
DATA 2 1 3163100200018
DATA ERR-T 3163100200019
B B 3163100200020
0.39 0.1 3163100200021
ENDDATA 3 0 3163100200022
ENDSUBENT 21 0 3163100299999
SUBENT 31631003 20160929 31753163100300001
BIB 4 10 3163100300002
REACTION (50-SN-126(N,G)50-SN-127-G,,SIG) 3163100300003
DECAY-DATA (50-SN-127-G,2.10HR,DG,823.1,0.1064,DG,1095.6,0.1938, 3163100300004
DG,1114.3,0.38) 3163100300005
ERR-ANALYS (ERR-T) The uncertainty consists of the average 3163100300006
deviation of cross sections from three irradiated 3163100300007
targets. 3163100300008
(ERR-S,5.6,8.5) 127gSn counting statistics, error of 3163100300009
the weighted average and error of counting efficiency 3163100300010
(ERR-1,2.0,4.7) error of the thermal neutron flux 3163100300011
HISTORY (20160923A) VS. SF8=SPA deleted. ERR-ANALYS modified. 3163100300012
ENDBIB 10 0 3163100300013
NOCOMMON 0 0 3163100300014
DATA 2 1 3163100300015
DATA ERR-T 3163100300016
B B 3163100300017
0.200 0.039 3163100300018
ENDDATA 3 0 3163100300019
ENDSUBENT 18 0 3163100399999
SUBENT 31631004 20160929 31753163100400001
BIB 4 5 3163100400002
REACTION (50-SN-126(N,G)50-SN-127,,SIG) 3163100400003
ERR-ANALYS (ERR-T) see above (subents 002,003) 3163100400004
STATUS (DEP,31631002) 3163100400005
(DEP,31631003) 3163100400006
HISTORY (20160923A) VS. SF8=SPA deleted, DECAY-DATA deleted. 3163100400007
ENDBIB 5 0 3163100400008
NOCOMMON 0 0 3163100400009
DATA 2 1 3163100400010
DATA ERR-T 3163100400011
B B 3163100400012
0.59 0.14 3163100400013
ENDDATA 3 0 3163100400014
ENDSUBENT 13 0 3163100499999
ENDENTRY 4 0 3163199999999