ENTRY 31698 20120502 31553169800000001 SUBENT 31698001 20120502 31553169800100001 BIB 13 30 3169800100002 TITLE Cross section determination of short-to-medium lived 3169800100003 nuclides in a low power research and an Am-Be neutron 3169800100004 source 3169800100005 AUTHOR (B.J.B.Nyarko, R.B.M.Sogbadji, E.H.K.Akaho, 3169800100006 S.E.Agbemava) 3169800100007 INSTITUTE (3GHAGHA) University of Ghana, School of Nuclear and 3169800100008 Allied Science, P.O. Box AE1, Atomic Energy, Accra 3169800100009 (3GHALGN) National Nuclear Research Institute 3169800100010 REFERENCE (R,INDC(NDS)-0574,72,2010) 3169800100011 DETECTOR (HPGE) HPGe coaxial detector (ORTEC), which has a 3169800100012 relative efficiency of 25% and energy resolution of 3169800100013 1.8 keV at 1332.5 keV gamma-ray of Co-60. 3169800100014 REL-REF Y.A.Ahmed+,J,Nigerian J. Phys.,14,(1),82,2006 3169800100015 The detailed description of the reactor. 3169800100016 (M,,M.Karadag+,J,NIM/A,501,524,2003) 3169800100017 Theoretical description of the method. 3169800100018 (R,,F.De Corte+,J,JRN,257,493,2003) 3169800100019 Properties of the isotopes used during the 3169800100020 experimental measurements against their nuclear 3169800100021 constants 3169800100022 METHOD (ACTIV)Activation 3169800100023 ANALYSIS Cadmium ratio method. 3169800100024 The samples were irradiated with and without cadmium 3169800100025 cover of 1 mm wall thickness. 3169800100026 MONITOR ((MONIT1)25-MN-55(N,G)25-MN-56,,SIG) 3169800100027 DECAY-MON (25-MN-56,2.58HR,DG,1810.70,0.272) 3169800100028 ERR-ANALYS (DATA-ERR) No information on source of uncertainties 3169800100029 STATUS (TABLE) Table 4 of INDC(NDS)-0574,72,2010 3169800100030 HISTORY (20101110C) VS 3169800100031 (20120502U) On. BIB: Formal corrections only 3169800100032 ENDBIB 30 0 3169800100033 COMMON 2 3 3169800100034 EN-NRM MONIT1 3169800100035 EV B 3169800100036 0.0253 13.20 3169800100037 ENDCOMMON 3 0 3169800100038 ENDSUBENT 37 0 3169800199999 SUBENT 31698002 20101110 31493169800200001 BIB 5 21 3169800200002 REACTION (33-AS-75(N,G)33-AS-76,,SIG) 3169800200003 DECAY-DATA (33-AS-76,26.32HR,DG,559.10,0.45) 3169800200004 SAMPLE (33-AS-76,NAT=1.) 3169800200005 Arsenic standard solution which contained 10% nitric 3169800200006 acid. 3169800200007 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800200008 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800200009 reactor, which uses 90.2% enriched uranium-Al alloy 3169800200010 as fuel. The samples were irradiated at thermal 3169800200011 power level of 3 kW and 15 kW. 3169800200012 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800200013 ratio were determined by Cadmium ratio method using 3169800200014 Au and Zr as monitors. 3169800200015 Measured epithermal neutron shaping factor (alpha) at 3169800200016 the outer and inner irradiation channels: 3169800200017 Channel Cadmium Ratio (Rcd) (alpha) 3169800200018 94Zr 197Au 3169800200019 Inner 3169800200020 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800200021 Outer 3169800200022 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800200023 ENDBIB 21 0 3169800200024 NOCOMMON 0 0 3169800200025 DATA 3 1 3169800200026 EN DATA DATA-ERR 3169800200027 EV B B 3169800200028 0.0253 4.28 0.19 3169800200029 ENDDATA 3 0 3169800200030 ENDSUBENT 29 0 3169800299999 SUBENT 31698003 20101112 31493169800300001 BIB 7 26 3169800300002 REACTION (33-AS-75(N,G)33-AS-76,,RI) 3169800300003 DECAY-DATA (33-AS-76,26.32HR,DG,559.10,0.45) 3169800300004 MONITOR ((MONIT2)25-MN-55(N,G)25-MN-56,,RI) 3169800300005 Epithermal Cross Section = 13.90 b 3169800300006 ((MONIT3)33-AS-75(N,G)33-AS-76,,SIG) 3169800300007 Thermal Cross Section = 4.29 b 3169800300008 DECAY-MON (25-MN-56,2.58HR,DG,1810.70,0.272) 3169800300009 SAMPLE (33-AS-76,NAT=1.) 3169800300010 Arsenic standard solution which contained 10% nitric 3169800300011 acid. 3169800300012 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800300013 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800300014 reactor, which uses 90.2 %enriched uranium-Al alloy 3169800300015 as fuel. The samples were irradiated at thermal 3169800300016 power level of 3 kW and 15 kW. 3169800300017 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800300018 ratio were determined by Cadmium ratio method using 3169800300019 Au and Zr as monitors. 3169800300020 Measured epithermal neutron shaping factor (alpha) at 3169800300021 the outer and inner irradiation channels: 3169800300022 Channel Cadmium Ratio (Rcd) (alpha) 3169800300023 94Zr 197Au 3169800300024 Inner 3169800300025 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800300026 Outer 3169800300027 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800300028 ENDBIB 26 0 3169800300029 NOCOMMON 0 0 3169800300030 DATA 6 1 3169800300031 EN-MIN DATA DATA-ERR MONIT2 EN-NRM3 MONIT3 3169800300032 EV B B B EV B 3169800300033 0.55 61.88 1.07 13.90 0.0253 4.29 3169800300034 ENDDATA 3 0 3169800300035 ENDSUBENT 34 0 3169800399999 SUBENT 31698004 20120502 31553169800400001 BIB 6 21 3169800400002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 3169800400003 DECAY-DATA (79-AU-198,2.70D,DG,411.80,0.9556) 3169800400004 SAMPLE (79-AU-198,NAT=1.) Al-0.1%Au foil. 3169800400005 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800400006 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800400007 reactor, which uses 90.2% enriched uranium-Al alloy 3169800400008 as fuel. 3169800400009 The samples were irradiated at thermal power level of 3169800400010 3 kW and 15 kW. 3169800400011 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800400012 ratio were determined by Cadmium ratio method using 3169800400013 Au and Zr as monitors. 3169800400014 Measured epithermal neutron shaping factor (alpha) at 3169800400015 the outer and inner irradiation channels: 3169800400016 Channel Cadmium Ratio (Rcd) (alpha) 3169800400017 94Zr 197Au 3169800400018 Inner 3169800400019 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800400020 Outer 3169800400021 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800400022 HISTORY (20120502A) On. SAMPLE: Illegal blank removed. 3169800400023 ENDBIB 21 0 3169800400024 NOCOMMON 0 0 3169800400025 DATA 3 1 3169800400026 EN DATA DATA-ERR 3169800400027 EV B B 3169800400028 0.0253 97.47 0.64 3169800400029 ENDDATA 3 0 3169800400030 ENDSUBENT 29 0 3169800499999 SUBENT 31698005 20120502 31553169800500001 BIB 8 26 3169800500002 REACTION (79-AU-197(N,G)79-AU-198,,RI) 3169800500003 DECAY-DATA (79-AU-198,2.70D,DG,411.80,0.9556) 3169800500004 MONITOR ((MONIT2)25-MN-55(N,G)25-MN-56,,RI) 3169800500005 Epithermal Cross Section = 13.90 b 3169800500006 ((MONIT3)79-AU-197(N,G)79-AU-198,,SIG) 3169800500007 Thermal Cross Section = 98.66 b 3169800500008 DECAY-MON (25-MN-56,2.58HR,DG,1810.70,0.272) 3169800500009 SAMPLE (79-AU-198,NAT=1.) Al-0.1%Au foil 3169800500010 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800500011 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800500012 reactor, which uses 90.2% enriched uranium-Al alloy 3169800500013 as fuel. 3169800500014 The samples were irradiated at thermal power level of 3169800500015 3 kW and 15 kW. 3169800500016 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800500017 ratio were determined by Cadmium ratio method using 3169800500018 Au and Zr as monitors. 3169800500019 Measured epithermal neutron shaping factor (alpha) at 3169800500020 the outer and inner irradiation channels: 3169800500021 Channel Cadmium Ratio (Rcd) (alpha) 3169800500022 94Zr 197Au 3169800500023 Inner 3169800500024 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800500025 Outer 3169800500026 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800500027 HISTORY (20120502A) On. SAMPLE: Illegal blank removed. 3169800500028 ENDBIB 26 0 3169800500029 NOCOMMON 0 0 3169800500030 DATA 6 1 3169800500031 EN-MIN DATA DATA-ERR MONIT2 EN-NRM3 MONIT3 3169800500032 EV B B B EV B 3169800500033 0.55 1549. 174. 13.90 0.0253 98.66 3169800500034 ENDDATA 3 0 3169800500035 ENDSUBENT 34 0 3169800599999 SUBENT 31698006 20101114 31493169800600001 BIB 5 21 3169800600002 REACTION (62-SM-152(N,G)62-SM-153,,SIG) 3169800600003 DECAY-DATA (62-SM-153,46.27HR,DG,103.20,0.283) 3169800600004 SAMPLE (62-SM-152,NAT=0.2670) 3169800600005 Samarium standard solution which contained 10% nitric 3169800600006 acid. 3169800600007 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800600008 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800600009 reactor, which uses 90.2 %enriched uranium-Al alloy 3169800600010 as fuel. The samples were irradiated at thermal 3169800600011 power level of 3 kW and 15 kW. 3169800600012 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800600013 ratio were determined by Cadmium ratio method using 3169800600014 Au and Zr as monitors. 3169800600015 Measured epithermal neutron shaping factor (alpha) at 3169800600016 the outer and inner irradiation channels: 3169800600017 Channel Cadmium Ratio (Rcd) (alpha) 3169800600018 94Zr 197Au 3169800600019 Inner 3169800600020 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800600021 Outer 3169800600022 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800600023 ENDBIB 21 0 3169800600024 NOCOMMON 0 0 3169800600025 DATA 3 1 3169800600026 EN DATA DATA-ERR 3169800600027 EV B B 3169800600028 0.0253 238.93 19.11 3169800600029 ENDDATA 3 0 3169800600030 ENDSUBENT 29 0 3169800699999 SUBENT 31698007 20101114 31493169800700001 BIB 7 26 3169800700002 REACTION (62-SM-152(N,G)62-SM-153,,RI) 3169800700003 DECAY-DATA (62-SM-153,46.27HR,DG,103.20,0.283) 3169800700004 MONITOR ((MONIT2)25-MN-55(N,G)25-MN-56,,RI) 3169800700005 Epithermal Cross Section = 13.90 b 3169800700006 ((MONIT3)62-SM-152(N,G)62-SM-153,,SIG) 3169800700007 Thermal Cross Section = 220 b 3169800700008 DECAY-MON (25-MN-56,2.58HR,DG,1810.70,0.272) 3169800700009 SAMPLE (62-SM-152,NAT=0.2670) 3169800700010 Samarium standard solution which contained 10% nitric 3169800700011 acid. 3169800700012 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800700013 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800700014 reactor, which uses 90.2% enriched uranium-Al alloy 3169800700015 as fuel. The samples were irradiated at thermal 3169800700016 power level of 3 kW and 15 kW. 3169800700017 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800700018 ratio were determined by Cadmium ratio method using 3169800700019 Au and Zr as monitors. 3169800700020 Measured epithermal neutron shaping factor (alpha) at 3169800700021 the outer and inner irradiation channels: 3169800700022 Channel Cadmium Ratio (Rcd) (alpha) 3169800700023 94Zr 197Au 3169800700024 Inner 3169800700025 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800700026 Outer 3169800700027 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800700028 ENDBIB 26 0 3169800700029 NOCOMMON 0 0 3169800700030 DATA 6 1 3169800700031 EN-MIN DATA DATA-ERR MONIT2 EN-NRM3 MONIT3 3169800700032 EV B B B EV B 3169800700033 0.55 3121.48 249. 13.90 0.0253 220. 3169800700034 ENDDATA 3 0 3169800700035 ENDSUBENT 34 0 3169800799999 SUBENT 31698008 20101114 31493169800800001 BIB 5 21 3169800800002 REACTION (12-MG-26(N,G)12-MG-27,,SIG) 3169800800003 DECAY-DATA (12-MG-27,9.46MIN,DG,1014.40,0.28) 3169800800004 SAMPLE (12-MG-26,NAT=0.1101) 3169800800005 Magnesium standard solution which contained 10% nitric 3169800800006 acid. 3169800800007 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800800008 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800800009 reactor, which uses 90.2% enriched uranium-Al alloy 3169800800010 as fuel. The samples were irradiated at thermal 3169800800011 power level of 3 kW and 15 kW. 3169800800012 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800800013 ratio were determined by Cadmium ratio method using 3169800800014 Au and Zr as monitors. 3169800800015 Measured epithermal neutron shaping factor (alpha) at 3169800800016 the outer and inner irradiation channels: 3169800800017 Channel Cadmium Ratio (Rcd) (alpha) 3169800800018 94Zr 197Au 3169800800019 Inner 3169800800020 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800800021 Outer 3169800800022 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800800023 ENDBIB 21 0 3169800800024 NOCOMMON 0 0 3169800800025 DATA 3 1 3169800800026 EN DATA DATA-ERR 3169800800027 EV B B 3169800800028 0.0253 0.032 0.001 3169800800029 ENDDATA 3 0 3169800800030 ENDSUBENT 29 0 3169800899999 SUBENT 31698009 20101114 31493169800900001 BIB 7 26 3169800900002 REACTION (12-MG-26(N,G)12-MG-27,,RI) 3169800900003 DECAY-DATA (12-MG-27,9.46MIN,DG,1014.4,0.28) 3169800900004 MONITOR ((MONIT2)25-MN-55(N,G)25-MN-56,,RI) 3169800900005 Epithermal Cross Section = 13.90 b 3169800900006 ((MONIT3)12-MG-26(N,G)12-MG-27,,SIG) 3169800900007 Thermal Cross Section = 0.037 b 3169800900008 DECAY-MON (25-MN-56,2.58HR,DG,1810.70,0.272) 3169800900009 SAMPLE (12-MG-26,NAT=0.1101) 3169800900010 Magnesium standard solution which contained 10% nitric 3169800900011 acid. 3169800900012 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169800900013 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169800900014 reactor, which uses 90.2% enriched uranium-Al alloy 3169800900015 as fuel. The samples were irradiated at thermal 3169800900016 power level of 3 kW and 15 kW. 3169800900017 INC-SPECT The spectral parameter and thermal to epithermal flux 3169800900018 ratio were determined by Cadmium ratio method using 3169800900019 Au and Zr as monitors. 3169800900020 Measured epithermal neutron shaping factor (alpha) at 3169800900021 the outer and inner irradiation channels: 3169800900022 Channel Cadmium Ratio (Rcd) (alpha) 3169800900023 94Zr 197Au 3169800900024 Inner 3169800900025 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169800900026 Outer 3169800900027 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169800900028 ENDBIB 26 0 3169800900029 NOCOMMON 0 0 3169800900030 DATA 6 1 3169800900031 EN-MIN DATA DATA-ERR MONIT2 EN-NRM3 MONIT3 3169800900032 EV B B B EV B 3169800900033 0.55 0.260 0.004 13.90 0.0253 0.037 3169800900034 ENDDATA 3 0 3169800900035 ENDSUBENT 34 0 3169800999999 SUBENT 31698010 20101123 31493169801000001 BIB 5 21 3169801000002 REACTION (56-BA-138(N,G)56-BA-139,,SIG) 3169801000003 DECAY-DATA (56-BA-139,84.63MIN,DG,165.80,0.2376) 3169801000004 SAMPLE (56-BA-138,NAT=0.7170) 3169801000005 Barium standard solution which contained 10% nitric 3169801000006 acid. 3169801000007 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169801000008 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169801000009 reactor, which uses 90.2% enriched uranium-Al alloy 3169801000010 as fuel. The samples were irradiated at thermal 3169801000011 power level of 3 kW and 15 kW. 3169801000012 INC-SPECT The spectral parameter and thermal to epithermal flux 3169801000013 ratio were determined by Cadmium ratio method using 3169801000014 Au and Zr as monitors. 3169801000015 Measured epithermal neutron shaping factor (alpha) at 3169801000016 the outer and inner irradiation channels: 3169801000017 Channel Cadmium Ratio (Rcd) (alpha) 3169801000018 94Zr 197Au 3169801000019 Inner 3169801000020 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169801000021 Outer 3169801000022 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169801000023 ENDBIB 21 0 3169801000024 NOCOMMON 0 0 3169801000025 DATA 3 1 3169801000026 EN DATA DATA-ERR 3169801000027 EV B B 3169801000028 2.53E-02 0.58 1.E-02 3169801000029 ENDDATA 3 0 3169801000030 ENDSUBENT 29 0 3169801099999 SUBENT 31698011 20101123 31493169801100001 BIB 7 26 3169801100002 REACTION (56-BA-138(N,G)56-BA-139,,RI) 3169801100003 DECAY-DATA (56-BA-139,84.63MIN,DG,165.80,0.2376) 3169801100004 MONITOR ((MONIT2)25-MN-55(N,G)25-MN-56,,RI) 3169801100005 Epithermal Cross Section = 13.90 b 3169801100006 ((MONIT3)56-BA-138(N,G)56-BA-139,,SIG) 3169801100007 Thermal Cross Section = 0.41 b 3169801100008 DECAY-MON (25-MN-56,2.58HR,DG,1810.70,0.272) 3169801100009 SAMPLE (56-BA-138,NAT=0.7170) 3169801100010 Barium standard solution which contained 10% nitric 3169801100011 acid. 3169801100012 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169801100013 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169801100014 reactor, which uses 90.2% enriched uranium-Al alloy 3169801100015 as fuel. The samples were irradiated at thermal 3169801100016 power level of 3 kW and 15 kW. 3169801100017 INC-SPECT The spectral parameter and thermal to epithermal flux 3169801100018 ratio were determined by Cadmium ratio method using 3169801100019 Au and Zr as monitors. 3169801100020 Measured epithermal neutron shaping factor (alpha) at 3169801100021 the outer and inner irradiation channels: 3169801100022 Channel Cadmium Ratio (Rcd) (alpha) 3169801100023 94Zr 197Au 3169801100024 Inner 3169801100025 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169801100026 Outer 3169801100027 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169801100028 ENDBIB 26 0 3169801100029 NOCOMMON 0 0 3169801100030 DATA 6 1 3169801100031 EN-MIN DATA DATA-ERR MONIT2 EN-NRM3 MONIT3 3169801100032 EV B B B EV B 3169801100033 0.55 0.380 0.005 13.90 0.0253 0.405 3169801100034 ENDDATA 3 0 3169801100035 ENDSUBENT 34 0 3169801199999 SUBENT 31698012 20101123 31493169801200001 BIB 5 21 3169801200002 REACTION (20-CA-48(N,G)20-CA-49,,SIG) 3169801200003 DECAY-DATA (20-CA-49,8.72MIN,DG,3084.50,0.921) 3169801200004 SAMPLE (20-CA-48,NAT=0.0019) 3169801200005 Calcium standard solution which contained 10% nitric 3169801200006 acid. 3169801200007 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169801200008 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169801200009 reactor, which uses 90.2% enriched uranium-Al alloy 3169801200010 as fuel. The samples were irradiated at thermal 3169801200011 power level of 3 kW and 15 kW. 3169801200012 INC-SPECT The spectral parameter and thermal to epithermal flux 3169801200013 ratio were determined by Cadmium ratio method using 3169801200014 Au and Zr as monitors. 3169801200015 Measured epithermal neutron shaping factor (alpha) at 3169801200016 the outer and inner irradiation channels: 3169801200017 Channel Cadmium Ratio (Rcd) (alpha) 3169801200018 94Zr 197Au 3169801200019 Inner 3169801200020 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169801200021 Outer 3169801200022 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169801200023 ENDBIB 21 0 3169801200024 NOCOMMON 0 0 3169801200025 DATA 3 1 3169801200026 EN DATA DATA-ERR 3169801200027 EV B B 3169801200028 0.0253 1.14 0.02 3169801200029 ENDDATA 3 0 3169801200030 ENDSUBENT 29 0 3169801299999 SUBENT 31698013 20101124 31493169801300001 BIB 7 26 3169801300002 REACTION (20-CA-48(N,G)20-CA-49,,RI) 3169801300003 DECAY-DATA (20-CA-49,8.72MIN,DG,3084.50,0.921) 3169801300004 MONITOR ((MONIT2)25-MN-55(N,G)25-MN-56,,RI) 3169801300005 Epithermal Cross Section = 13.90 b 3169801300006 ((MONIT3)20-CA-48(N,G)20-CA-49,,SIG) 3169801300007 Thermal Cross Section = 1.12 b 3169801300008 DECAY-MON (25-MN-56,2.58HR,DG,1810.70,0.272) 3169801300009 SAMPLE (20-CA-48,NAT=0.0019) 3169801300010 Calcium standard solution which contained 10% nitric 3169801300011 acid. 3169801300012 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169801300013 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169801300014 reactor, which uses 90.2% enriched uranium-Al alloy 3169801300015 as fuel. The samples were irradiated at thermal 3169801300016 power level of 3 kW and 15 kW. 3169801300017 INC-SPECT The spectral parameter and thermal to epithermal flux 3169801300018 ratio were determined by Cadmium ratio method using 3169801300019 Au and Zr as monitors. 3169801300020 Measured epithermal neutron shaping factor (alpha) at 3169801300021 the outer and inner irradiation channels: 3169801300022 Channel Cadmium Ratio (Rcd) (alpha) 3169801300023 94Zr 197Au 3169801300024 Inner 3169801300025 irr.ch.2 3.47+/-0.04 2.36+/-0.01 -0.961+/-0.034 3169801300026 Outer 3169801300027 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169801300028 ENDBIB 26 0 3169801300029 NOCOMMON 0 0 3169801300030 DATA 6 1 3169801300031 EN-MIN DATA DATA-ERR MONIT2 EN-NRM3 MONIT3 3169801300032 EV B B B EV B 3169801300033 0.55 0.89 0.01 13.90 0.0253 1.12 3169801300034 ENDDATA 3 0 3169801300035 ENDSUBENT 34 0 3169801399999 SUBENT 31698014 20101126 31493169801400001 BIB 5 16 3169801400002 REACTION (13-AL-27(N,G)13-AL-28,,SIG) 3169801400003 DECAY-DATA (13-AL-28,2.24MIN,DG,1779.00,1.) 3169801400004 SAMPLE (13-AL-28,NAT=1.) 3169801400005 Al-0.1%Au wire 3169801400006 INC-SOURCE (A-BE) The Americium-Beryllium Neutron Source at 3169801400007 Ghana Atomic Energy Commission is a 20 Ci Am-Be 3169801400008 neutron source which is moderated with water. The 3169801400009 neutron emission is quoted as 2.2x10*6 n/cm/Ci. 3169801400010 Flux of 4.2x10*4 n/s/cm2. 3169801400011 INC-SPECT Measured epithermal neutron shaping factor (alpha) of 3169801400012 channels 1 and 2 of the Am-Be neutron source: 3169801400013 Channels Flux ratios (alpha) 3169801400014 (thermal neutron flux/ 3169801400015 epithermal neutron flux) 3169801400016 Irr. ch. 1 20.2 0.134+/-0.001 3169801400017 Irr. ch. 2 29.7 -0.239+/-0.003 3169801400018 ENDBIB 16 0 3169801400019 NOCOMMON 0 0 3169801400020 DATA 3 1 3169801400021 EN DATA DATA-ERR 3169801400022 EV B B 3169801400023 0.0253 0.20 0.02 3169801400024 ENDDATA 3 0 3169801400025 ENDSUBENT 24 0 3169801499999 SUBENT 31698015 20101126 31493169801500001 BIB 5 17 3169801500002 REACTION (23-V-51(N,G)23-V-52,,SIG) 3169801500003 DECAY-DATA (23-V-52,3.75MIN,DG,1434.10,1.) 3169801500004 SAMPLE (23-V-51,NAT=0.9975) 3169801500005 Vanadium standard solution which contained 10% nitric 3169801500006 acid. 3169801500007 INC-SOURCE (A-BE) The Americium-Beryllium Neutron Source at 3169801500008 Ghana Atomic Energy Commission is a 20 Ci Am-Be 3169801500009 neutron source which is moderated with water. The 3169801500010 neutron emission is quoted as 2.2x10*6 n/cm/Ci. 3169801500011 Flux of 4.2x10*4 n/s/cm2. 3169801500012 INC-SPECT Measured epithermal neutron shaping factor (alpha) of 3169801500013 channels 1 and 2 of the Am-Be neutron source: 3169801500014 Channels Flux ratios (alpha) 3169801500015 (thermal neutron flux/ 3169801500016 epithermal neutron flux) 3169801500017 Irr. ch. 1 20.2 0.134+/-0.001 3169801500018 Irr. ch. 2 29.7 -0.239+/-0.003 3169801500019 ENDBIB 17 0 3169801500020 NOCOMMON 0 0 3169801500021 DATA 3 1 3169801500022 EN DATA DATA-ERR 3169801500023 EV B B 3169801500024 0.0253 5.66 0.36 3169801500025 ENDDATA 3 0 3169801500026 ENDSUBENT 25 0 3169801599999 SUBENT 31698016 20101126 31493169801600001 BIB 5 17 3169801600002 REACTION (53-I-127(N,G)53-I-128,,SIG) 3169801600003 DECAY-DATA (53-I-128,24.99MIN,DG,442.90,0.169) 3169801600004 SAMPLE (53-I-128,NAT=1.) 3169801600005 Iodine standard solution which contained 10% nitric 3169801600006 acid. 3169801600007 INC-SOURCE (A-BE) The Americium-Beryllium Neutron Source at 3169801600008 Ghana Atomic Energy Commission is a 20 Ci Am-Be 3169801600009 neutron source which is moderated with water. The 3169801600010 neutron emission is quoted as 2.2x10*6 n/cm/Ci. 3169801600011 Flux of 4.2x10*4 n/s/cm2. 3169801600012 INC-SPECT Measured epithermal neutron shaping factor (alpha) of 3169801600013 channels 1 and 2 of the Am-Be neutron source: 3169801600014 Channels Flux ratios (alpha) 3169801600015 (thermal neutron flux/ 3169801600016 epithermal neutron flux) 3169801600017 Irr. ch. 1 20.2 0.134+/-0.001 3169801600018 Irr. ch. 2 29.7 -0.239+/-0.003 3169801600019 ENDBIB 17 0 3169801600020 NOCOMMON 0 0 3169801600021 DATA 3 1 3169801600022 EN DATA DATA-ERR 3169801600023 EV B B 3169801600024 0.0253 4.63 0.60 3169801600025 ENDDATA 3 0 3169801600026 ENDSUBENT 25 0 3169801699999 SUBENT 31698017 20101214 31493169801700001 BIB 5 21 3169801700002 REACTION (62-SM-154(N,G)62-SM-155,,SIG) 3169801700003 DECAY-DATA (62-SM-155,22.3MIN,DG,104.40,0.746) 3169801700004 SAMPLE (62-SM-154,NAT=0.2270) 3169801700005 Samarium standard solution which contained 10% nitric 3169801700006 acid. 3169801700007 FACILITY (REAC,3GHALGN) Miniature neutron source reactor. 3169801700008 Ghana Research Reactor-1 is a 30 kW tank-in-pool 3169801700009 reactor, which uses 90.2% enriched uranium-Al alloy 3169801700010 as fuel. The samples were irradiated at thermal 3169801700011 power level of 3 kW and 15 kW. 3169801700012 INC-SPECT The spectral parameter and thermal to epithermal flux 3169801700013 ratio were determined by Cadmium ratio method using 3169801700014 Au and Zr as monitors. 3169801700015 Measured epithermal neutron shaping factor (alpha) at 3169801700016 the outer and inner irradiation channels: 3169801700017 Channel Cadmium Ratio (Rcd) (alpha) 3169801700018 94Zr 197Au 3169801700019 Inner 3169801700020 irr.ch.2 3.47+/-0.07 2.36+/-0.01 -0.961+/-0.034 3169801700021 Outer 3169801700022 irr.ch.7 11.28+/-0.40 3.78+/-0.01 0.037+/-0.001 3169801700023 ENDBIB 21 0 3169801700024 NOCOMMON 0 0 3169801700025 DATA 3 1 3169801700026 EN DATA DATA-ERR 3169801700027 EV B B 3169801700028 0.0253 7.77 0.46 3169801700029 ENDDATA 3 0 3169801700030 ENDSUBENT 29 0 3169801799999 SUBENT 31698018 20101214 31493169801800001 BIB 5 17 3169801800002 REACTION (62-SM-154(N,G)62-SM-155,,SIG) 3169801800003 DECAY-DATA (62-SM-155,22.3MIN,DG,104.40,0.746) 3169801800004 SAMPLE (62-SM-154,NAT=0.2270) 3169801800005 Samarium standard solution which contained 10% nitric 3169801800006 acid. 3169801800007 INC-SOURCE (A-BE) The Americium-Beryllium Neutron Source at 3169801800008 Ghana Atomic Energy Commission is a 20 Ci Am-Be 3169801800009 neutron source which is moderated with water. The 3169801800010 neutron emission is quoted as 2.2x10*6 n/cm/Ci. 3169801800011 Flux of 4.2x10*4 n/s/cm2. 3169801800012 INC-SPECT Measured epithermal neutron shaping factor (alpha) of 3169801800013 channels 1 and 2 of the Am-Be neutron source: 3169801800014 Channels Flux ratios (alpha) 3169801800015 (thermal neutron flux/ 3169801800016 epithermal neutron flux) 3169801800017 Irr. ch. 1 20.2 0.134+/-0.001 3169801800018 Irr. ch. 2 29.7 -0.239+/-0.003 3169801800019 ENDBIB 17 0 3169801800020 NOCOMMON 0 0 3169801800021 DATA 3 1 3169801800022 EN DATA DATA-ERR 3169801800023 EV B B 3169801800024 0.0253 7.06 0.53 3169801800025 ENDDATA 3 0 3169801800026 ENDSUBENT 25 0 3169801899999 SUBENT 31698019 20101214 31493169801900001 BIB 5 17 3169801900002 REACTION (92-U-238(N,G)92-U-239,,SIG) 3169801900003 DECAY-DATA (92-U-239,23.74MIN,DG,74.70,0.500) 3169801900004 SAMPLE (92-U-238,NAT=0.9927) 3169801900005 Uranium standard solution which contained 10% nitric 3169801900006 acid. 3169801900007 INC-SOURCE (A-BE) The Americium-Beryllium Neutron Source at 3169801900008 Ghana Atomic Energy Commission is a 20 Ci Am-Be 3169801900009 neutron source which is moderated with water. The 3169801900010 neutron emission is quoted as 2.2x10*6 n/cm/Ci. 3169801900011 Flux of 4.2x10*4 n/s/cm2. 3169801900012 INC-SPECT Measured epithermal neutron shaping factor (alpha) of 3169801900013 channels 1 and 2 of the Am-Be neutron source: 3169801900014 Channels Flux ratios (alpha) 3169801900015 (thermal neutron flux/ 3169801900016 epithermal neutron flux) 3169801900017 Irr. ch. 1 20.2 0.134+/-0.001 3169801900018 Irr. ch. 2 29.7 -0.239+/-0.003 3169801900019 ENDBIB 17 0 3169801900020 NOCOMMON 0 0 3169801900021 DATA 3 1 3169801900022 EN DATA DATA-ERR 3169801900023 EV B B 3169801900024 0.0253 3.12 0.51 3169801900025 ENDDATA 3 0 3169801900026 ENDSUBENT 25 0 3169801999999 ENDENTRY 19 0 3169899999999