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