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