ENTRY 31700 20110202 31493170000000001
SUBENT 31700001 20110202 31493170000100001
BIB 14 55 3170000100002
TITLE Measurement of thermal neutron capture cross section 3170000100003
and resonance integral of the 138Ba(n,g)139Ba 3170000100004
reaction using 55Mn(n,g)56Mn as a monitor 3170000100005
AUTHOR (S.E.Agbemava,R.B.M.Sogbadji,B.J.B.Nyarko,R.Della) 3170000100006
INSTITUTE (3GHALGN)Ghana Atomic Energy Commission, National 3170000100007
Nuclear Research Institute, P.O. Box LG80, Legon, 3170000100008
Ghana 3170000100009
(3GHAGHA)University of Ghana, Graduate School of 3170000100010
Nuclear and Allied Sciences, P.O. Box AE1, Atomic 3170000100011
Energy, Accra, Ghana 3170000100012
REFERENCE (J,ANE,38,(2-3),379,2011) Main reference . 3170000100013
#doi:10.1016/j.anucene.2010.10.005 3170000100014
(P,INDC(NDS)-0574,72,2010) Thermal neutron capture 3170000100015
cross sections and resonance integrals 3170000100016
(Au-197,As-75,Al-27,V-51,I-127, 3170000100017
Sm-152,Sm-154,Ba-138,Mg-26 and U-238) 3170000100018
FACILITY (REAC,3GHAGHA)Ghana Research Reactor-1 (GHARR-1) at 3170000100019
the Ghana Atomic Energy Commission 3170000100020
SAMPLE (56-BA-138,NAT=0.717) 3170000100021
A 10 ppm standard solution of barium. The certified 3170000100022
concentration of the barium in the barium standard 3170000100023
solution was 9.92 +/- 0.03 mg/g 3170000100024
Comparator isotope Mn-56, was also contained in a 3170000100025
10 ppm standard solution of manganese. The certified 3170000100026
concentration of manganese in the manganese standard 3170000100027
was 10.01 +/- 0.03 mg/g. 3170000100028
About 10 ml of the solution was poured into 3170000100029
a polyethylene capsule (12.00 mm in outer diameter and 3170000100030
24.00 mm in outer length) for the irradiation within a 3170000100031
Cd capsule. 3170000100032
DETECTOR (HPGE) After the irradiation, induced radioactivity 3170000100033
in the target samples were counted from a distance of 3170000100034
7.20 cm from the detector using a high purity Ge- 3170000100035
detector (ORTEC) with relative efficiency of 25% and 3170000100036
an energy resolution of 1.8 keV (FWHM) at 1.33 MeV of 3170000100037
60Co. 3170000100038
METHOD (ACTIV) Activation 3170000100039
(CADMB) Cadmium ratio method. The samples were 3170000100040
irradiated with and without cadmium cover of 1 mm 3170000100041
wall thickness. 3170000100042
(SITA) Single-target irradiation 3170000100043
MONITOR ((MONIT1)25-MN-55(N,G)25-MN-56,,SIG) 3170000100044
DECAY-MON (25-MN-56,2.5785HR,DG,846.8,0.989) 3170000100045
MONIT-REF ((MONIT),De Corte+,R,IAEA-TECDOC-564,1990) 3170000100046
INC-SOURCE Irradiations of samples were performed at a thermal 3170000100047
power level of 15 kW, which corresponds to thermal 3170000100048
neutron flux value of 1x10**11 n/cm**2/s. The epitherma3170000100049
neutron shaping factor (a) of the inner irradiation 3170000100050
channel 2 which was used for the measurement is 3170000100051
0.961 +/- 0.034 and the Cadmium ratio are 3.47 +/- 0.073170000100052
and 2.36 +/- 0.01 for 94Zr and 197Au respectively. 3170000100053
STATUS (TABLE) Data taken from table 3 in 3170000100054
ANE,38,(2-3),379,2011 3170000100055
(APRVD) Approved by S.E. Agbemava, 2011-02-25 3170000100056
HISTORY (20110203C) 3170000100057
ENDBIB 55 0 3170000100058
COMMON 2 3 3170000100059
EN-NRM1 MONIT1 3170000100060
EV B 3170000100061
0.0253 13.2 3170000100062
ENDCOMMON 3 0 3170000100063
ENDSUBENT 62 0 3170000199999
SUBENT 31700002 20110202 31493170000200001
BIB 4 25 3170000200002
REACTION (56-BA-138(N,G)56-BA-139,,SIG) 3170000200003
Thermal capture cross section 3170000200004
DECAY-DATA (56-BA-139,83.06MIN,DG,165.9,0.2376) 3170000200005
CORRECTION Correction for departure from 1/v cross-section 3170000200006
behavior for Ba and Mn respectively. 3170000200007
Self-shielding factor for thermal neutrons. 3170000200008
ERR-ANALYS (ERR-T) Total uncertainty - studied reaction (2.31%) 3170000200009
(MONIT1-ERR) Total uncertainty - monitor 3170000200010
reaction (2.73%) 3170000200011
(ERR-S) Statistical uncertainty - studied 3170000200012
reaction (2.03%) 3170000200013
(ERR-1) Detector efficiency - studied reaction (2.94%) 3170000200014
(ERR-2) Detector efficiency - monitor reaction (1.17%) 3170000200015
(ERR-3) Mass of the sample (Ba) (0.02%) 3170000200016
(ERR-4) Mass of the sample (Mn) (0.02%) 3170000200017
(ERR-5) Gamma-ray emission probability of the 3170000200018
studied reaction (1.00%) 3170000200019
(ERR-6) Gamma-ray emmission probability of the 3170000200020
monitor reaction (0.30%) 3170000200021
(ERR-7) Thermal neutron self-shielding factor for the 3170000200022
studied reaction (0.01%) 3170000200023
(ERR-8) Thermal neutron self-shielding factor for the 3170000200024
monitor reaction (0.01%) 3170000200025
(ERR-9) Statistical uncertainty - monitor 3170000200026
reaction (1.35%) 3170000200027
ENDBIB 25 0 3170000200028
COMMON 9 6 3170000200029
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 3170000200030
ERR-7 ERR-8 ERR-9 3170000200031
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3170000200032
PER-CENT PER-CENT PER-CENT 3170000200033
2.94 1.17 0.02 0.02 1.00 0.30 3170000200034
0.01 0.01 1.35 3170000200035
ENDCOMMON 6 0 3170000200036
DATA 4 1 3170000200037
EN DATA ERR-T ERR-S 3170000200038
EV B B PER-CENT 3170000200039
0.0253 0.53 0.01 2.03 3170000200040
ENDDATA 3 0 3170000200041
ENDSUBENT 40 0 3170000299999
SUBENT 31700003 20110203 31493170000300001
BIB 4 21 3170000300002
REACTION (56-BA-138(N,G)56-BA-139,,RI) 3170000300003
DECAY-DATA (56-BA-139,83.06MIN,DG,165.9,0.2376) 3170000300004
MONITOR ((MONIT2)25-MN-55(N,G)25-MN-56,,RI) 3170000300005
Epithermal Cross Section = 13.90 b 3170000300006
((MONIT3)56-BA-138(N,G)56-BA-139,,SIG) 3170000300007
Thermal Cross Section = 0.405 b 3170000300008
ERR-ANALYS (ERR-T) Total uncertainty - studied reaction (2.21%) 3170000300009
(MONIT1-ERR) Total uncertainty - monitor 3170000300010
reaction (2.35%) 3170000300011
(ERR-S) Statistical uncertainty - studied 3170000300012
reaction (2.03%) 3170000300013
(ERR-1) Detector efficiency - studied reaction (2.94%) 3170000300014
(ERR-2) Detector efficiency - monitor reaction (1.17%) 3170000300015
(ERR-3) Mass of the sample (Ba) (0.02%) 3170000300016
(ERR-4) Mass of the sample (Mn) (0.02%) 3170000300017
(ERR-5) Thermal neutron self-shielding factor for the 3170000300018
studied reaction (0.01%) 3170000300019
(ERR-6) Thermal neutron self-shielding factor for the 3170000300020
monitor reaction (0.01%) 3170000300021
(ERR-7) Statistical uncertainty - monitor 3170000300022
reaction (1.35%) 3170000300023
ENDBIB 21 0 3170000300024
COMMON 7 6 3170000300025
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 3170000300026
ERR-7 3170000300027
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3170000300028
PER-CENT 3170000300029
2.94 1.17 0.02 0.02 0.01 0.01 3170000300030
1.35 3170000300031
ENDCOMMON 6 0 3170000300032
DATA 7 1 3170000300033
EN-MIN DATA DATA-ERR ERR-S MONIT2 EN-NRM3 3170000300034
MONIT3 3170000300035
EV B B PER-CENT B EV 3170000300036
B 3170000300037
0.55 0.380 0.005 2.03 13.90 0.02533170000300038
0.405 3170000300039
ENDDATA 6 0 3170000300040
ENDSUBENT 39 0 3170000399999
ENDENTRY 3 0 3170099999999