ENTRY 32712 20140523 31643271200000001
SUBENT 32712001 20140523 31643271200100001
BIB 15 50 3271200100002
TITLE Cross-sections of Sc-45(n,2n)Sc-44m,g reaction from 3271200100003
the reaction threshold to 20 MeV 3271200100004
AUTHOR (J.Luo,R.Liu,L.Jiang,Z.Liu,G.Sun,S.Ge) 3271200100005
INSTITUTE (3CPRHXU,3CPRBJG,3CPRNPC) 3271200100006
REFERENCE (J,RCA,101,607,2013) 3271200100007
#doi:10.1524/ract.2013.2065 3271200100008
FACILITY (NGEN,3CPRNPC) Pd-300 neutron generator 3271200100009
SAMPLE About 7 gram of high purity Sc2O3 powder(natural 3271200100010
isotopic composition) was pressed at 10 ton/cm2, and 3271200100011
a pellet, 0.4 cm thick and 2.0 cm in diameter was 3271200100012
obtained. Monitor foils (Nb, 99.99% pure, 0.5 mm 3271200100013
thick) of the same diameter as the pellets were then 3271200100014
attached in front and at the back of each sample. 3271200100015
DETECTOR (HPGE) The crystal geometry is 70.1 x 72.3 mm in 3271200100016
diameter and length. The relative efficiency is about 3271200100017
68%, and energy resolution is 1.69 keV at 1332 keV 3271200100018
gamma ray from Co-60. The efficiency of the detector 3271200100019
was pre-calibrated using various standard gamma 3271200100020
sources, which were Mn-54, Co-57, Co-60, Cd-109, 3271200100021
Ba-133, Cs-137, Eu-152, Am-241 and Ra-226. 3271200100022
(FISCH) The neutron flux was monitored by a uranium 3271200100023
fission chamber. 3271200100024
METHOD (ACTIV) Irradiation of the samples was lasted about 2 3271200100025
hours with a yield around 3E10 to 4E10 n/s. The groups 3271200100026
of samples were placed at 0deg., 90deg. or 135deg. 3271200100027
angles relative to the beam direction and centered 3271200100028
about the T-Ti target at distances of around 5 cm. 3271200100029
MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 3271200100030
MONIT-REF (,M.Wagner+,B,PH-DAT,13-5,1990) 3271200100031
INC-SOURCE (D-T) An effective deuteron beam energy of 125 keV 3271200100032
and beam current of 200 uA were used to produce 3271200100033
neutrons. The tritium-titanium (T-Ti) target used in 3271200100034
the generator was 2.38 mg/cm2 thick. 3271200100035
ERR-ANALYS (ERR-T) Total uncertainty of cross section 3271200100036
(ERR-S,0.1,1.0) Counting statistics (0.1-1.0%) 3271200100037
(ERR-1,2.,3.) Detector efficiency (2-3%) 3271200100038
(ERR-2) Weight of samples (0.1%) 3271200100039
(ERR-3) Self-absorption of gamma-ray (0.5%) 3271200100040
(ERR-4,0.,5.) The coincidence sum effect of cascade 3271200100041
gamma-rays (0-5%) 3271200100042
(ERR-5,0.1,1.) The uncertainties of irradiation, 3271200100043
cooling and measuring times (0.1-1.%) 3271200100044
(MONIT-ERR) Standard cross sections (1.5%) 3271200100045
CORRECTION Measurements were corrected for gamma-ray attenuations 3271200100046
and fluctuation of neutron flux. 3271200100047
STATUS (TABLE) All measured reactions cross sections are 3271200100048
taken from Table 2 at page 609 in J,RCA,101,607,2013, 3271200100049
and the isomeric cross section ratios are taken from 3271200100050
subsection 4.4 at page 610 in J,RCA,101,607,2013. 3271200100051
HISTORY (20140523C) Compiled by CHEN Guochang (CNDC) 3271200100052
ENDBIB 50 0 3271200100053
COMMON 3 3 3271200100054
ERR-2 ERR-3 MONIT-ERR 3271200100055
PER-CENT PER-CENT PER-CENT 3271200100056
0.1 0.5 1.5 3271200100057
ENDCOMMON 3 0 3271200100058
ENDSUBENT 57 0 3271200199999
SUBENT 32712002 20140523 31643271200200001
BIB 2 6 3271200200002
REACTION 1(21-SC-45(N,2N)21-SC-44-M,,SIG) 3271200200003
2(21-SC-45(N,2N)21-SC-44-G,,SIG) 3271200200004
3(21-SC-45(N,2N)21-SC-44,,SIG) 3271200200005
4(21-SC-45(N,2N)21-SC-44-M/G,,SIG/RAT) 3271200200006
DECAY-DATA1(21-SC-44-M,58.6HR,DG,271.13,0.867) 3271200200007
2(21-SC-44-G,3.927HR,DG,1157.03,0.999) 3271200200008
ENDBIB 6 0 3271200200009
NOCOMMON 0 0 3271200200010
DATA 10 3 3271200200011
EN EN-ERR DATA 1ERR-T 1DATA 2ERR-T 23271200200012
DATA 3ERR-T 3DATA 4ERR-T 4 3271200200013
MEV MEV MB MB MB MB 3271200200014
MB MB NO-DIM NO-DIM 3271200200015
13.5 0.2 76. 5. 98. 10.3271200200016
174. 15. 0.78 0.09 3271200200017
14.1 0.2 108. 7. 145. 13.3271200200018
253. 20. 0.74 0.08 3271200200019
14.8 0.2 134. 8. 186. 16.3271200200020
320. 24. 0.72 0.08 3271200200021
ENDDATA 10 0 3271200200022
ENDSUBENT 21 0 3271200299999
ENDENTRY 2 0 3271299999999