ENTRY 31699 20110119 31493169900000001 SUBENT 31699001 20110119 31493169900100001 BIB 13 34 3169900100002 TITLE The use of miniature neutron source reactor facility 3169900100003 for the determination of neutron-induced cross 3169900100004 section data 3169900100005 AUTHOR (S.A.Jonah,U.Sadiq) 3169900100006 INSTITUTE (3NI ABU)Reactor Engineering Section, Centre for 3169900100007 Energy Research and Training, Ahmadu Bello University, 3169900100008 Zaria, Nigeria; Department of Physics, Ahmadu Bello 3169900100009 University, Zaria 3169900100010 REFERENCE (R,INDC(NDS)-0574,67,2010) 3169900100011 REL-REF (I,,S.A.Jonah+,J,JRN,266,83,2005) 3169900100012 (I,,S.A.Jonah+,J,ARI,64,818,2006) Detailed 3169900100013 descriptions of the irradiation channels and the 3169900100014 characteristic data of the reactor as well as neutron 3169900100015 spectrum parameters (thermal to epithermal flux 3169900100016 ration and the epithermal flux shape factor) 3169900100017 determined by the "Cd-ratio for multi-monitor method". 3169900100018 FACILITY (REAC,3NI ABU)Miniature neutron source reactor. 3169900100019 INC-SOURCE (REAC)Irradiation was performed with and without a 3169900100020 one mm thick Cd box in an outer irradiation channel 3169900100021 at a thermal power level of 15.5 kW, which 3169900100022 corresponds to a thermal neutron flux value of 3169900100023 5.0x10**11 n/cm**2/s preset on the control console 3169900100024 SAMPLE Target materials of low and medium mass nuclei were 3169900100025 made up of high-purity foils and metallic oxides. 3169900100026 DETECTOR (HPGE) Induced radioactivity in detector foils were 3169900100027 counted on a HPGe coaxial detector (ORTEC), which has 3169900100028 a relative efficiency of 10% and resolution of 1.95 3169900100029 keV, at 1.33 MeV, Co-60. 3169900100030 METHOD (ACTIV) 3169900100031 ANALYSIS Cadmium ratio method 3169900100032 STATUS (TABLE) Data taken from the table 2 in the reference 3169900100033 INDC(NDS)-0574,67,2010 3169900100034 (APRVD) Approved by S.A. Jonah, 27 January 2011 3169900100035 HISTORY (20110119C) VS 3169900100036 ENDBIB 34 0 3169900100037 NOCOMMON 0 0 3169900100038 ENDSUBENT 37 0 3169900199999 SUBENT 31699002 20110119 31493169900200001 BIB 1 2 3169900200002 REACTION ((20-CA-46(N,G)20-CA-47,,RI)// 3169900200003 (20-CA-46(N,G)20-CA-47,,SIG)) 3169900200004 ENDBIB 2 0 3169900200005 NOCOMMON 0 0 3169900200006 DATA 4 1 3169900200007 EN-MIN-NM EN-DN DATA DATA-ERR 3169900200008 EV EV NO-DIM NO-DIM 3169900200009 0.55 0.0253 1.21 0.05 3169900200010 ENDDATA 3 0 3169900200011 ENDSUBENT 10 0 3169900299999 SUBENT 31699003 20110120 31493169900300001 BIB 2 4 3169900300002 REACTION (20-CA-46(N,G)20-CA-47,,SIG,,,DERIV) 3169900300003 STATUS (DEP,31699002) Q0 value (ratio of resonance integral 3169900300004 to thermal neutron capture cross section at a neutron 3169900300005 velocity of 2200 m/s) 3169900300006 ENDBIB 4 0 3169900300007 NOCOMMON 0 0 3169900300008 DATA 3 1 3169900300009 EN DATA DATA-ERR 3169900300010 EV B B 3169900300011 0.0253 0.85 0.24 3169900300012 ENDDATA 3 0 3169900300013 ENDSUBENT 12 0 3169900399999 SUBENT 31699004 20110120 31493169900400001 BIB 1 2 3169900400002 REACTION ((31-GA-71(N,G)31-GA-72,,RI)// 3169900400003 (31-GA-71(N,G)31-GA-72,,SIG)) 3169900400004 ENDBIB 2 0 3169900400005 NOCOMMON 0 0 3169900400006 DATA 4 1 3169900400007 EN-MIN-NM EN-DN DATA DATA-ERR 3169900400008 EV EV NO-DIM NO-DIM 3169900400009 0.55 0.0253 6.52 0.66 3169900400010 ENDDATA 3 0 3169900400011 ENDSUBENT 10 0 3169900499999 SUBENT 31699005 20110120 31493169900500001 BIB 2 4 3169900500002 REACTION (31-GA-71(N,G)31-GA-72,,SIG,,,DERIV) 3169900500003 STATUS (DEP,31699004) Q0 value (ratio of resonance integral 3169900500004 to thermal neutron capture cross section at a neutron 3169900500005 velocity of 2200 m/s) 3169900500006 ENDBIB 4 0 3169900500007 NOCOMMON 0 0 3169900500008 DATA 3 1 3169900500009 EN DATA DATA-ERR 3169900500010 EV B B 3169900500011 0.0253 4.79 1.1 3169900500012 ENDDATA 3 0 3169900500013 ENDSUBENT 12 0 3169900599999 SUBENT 31699006 20110120 31493169900600001 BIB 1 2 3169900600002 REACTION ((33-AS-75(N,G)33-AS-76,,RI)// 3169900600003 (33-AS-75(N,G)33-AS-76,,SIG)) 3169900600004 ENDBIB 2 0 3169900600005 NOCOMMON 0 0 3169900600006 DATA 4 1 3169900600007 EN-MIN-NM EN-DN DATA DATA-ERR 3169900600008 EV EV NO-DIM NO-DIM 3169900600009 0.55 0.0253 13.9 0.4 3169900600010 ENDDATA 3 0 3169900600011 ENDSUBENT 10 0 3169900699999 SUBENT 31699007 20110120 31493169900700001 BIB 2 4 3169900700002 REACTION (33-AS-75(N,G)33-AS-76,,SIG,,,DERIV) 3169900700003 STATUS (DEP,31699006) Q0 value (ratio of resonance integral 3169900700004 to thermal neutron capture cross section at a neutron 3169900700005 velocity of 2200 m/s) 3169900700006 ENDBIB 4 0 3169900700007 NOCOMMON 0 0 3169900700008 DATA 3 1 3169900700009 EN DATA DATA-ERR 3169900700010 EV B B 3169900700011 0.0253 4.38 0.33 3169900700012 ENDDATA 3 0 3169900700013 ENDSUBENT 12 0 3169900799999 SUBENT 31699008 20110120 31493169900800001 BIB 1 2 3169900800002 REACTION ((40-ZR-94(N,G)40-ZR-95,,RI)// 3169900800003 (40-ZR-94(N,G)40-ZR-95,,SIG)) 3169900800004 ENDBIB 2 0 3169900800005 NOCOMMON 0 0 3169900800006 DATA 4 1 3169900800007 EN-MIN-NM EN-DN DATA DATA-ERR 3169900800008 EV EV NO-DIM NO-DIM 3169900800009 0.55 0.0253 5.31 0.11 3169900800010 ENDDATA 3 0 3169900800011 ENDSUBENT 10 0 3169900899999 SUBENT 31699009 20110120 31493169900900001 BIB 2 4 3169900900002 REACTION (40-ZR-94(N,G)40-ZR-95,,SIG,,,DERIV) 3169900900003 STATUS (DEP,31699008) Q0 value (ratio of resonance integral 3169900900004 to thermal neutron capture cross section at a neutron 3169900900005 velocity of 2200 m/s) 3169900900006 ENDBIB 4 0 3169900900007 NOCOMMON 0 0 3169900900008 DATA 3 1 3169900900009 EN DATA DATA-ERR 3169900900010 EV B B 3169900900011 0.0253 0.043 0.007 3169900900012 ENDDATA 3 0 3169900900013 ENDSUBENT 12 0 3169900999999 SUBENT 31699010 20110120 31493169901000001 BIB 1 2 3169901000002 REACTION ((92-U-238(N,G)92-U-239,,RI)// 3169901000003 (92-U-238(N,G)92-U-239,,SIG)) 3169901000004 ENDBIB 2 0 3169901000005 NOCOMMON 0 0 3169901000006 DATA 4 1 3169901000007 EN-MIN-NM EN-DN DATA DATA-ERR 3169901000008 EV EV NO-DIM NO-DIM 3169901000009 0.55 0.0253 101.6 2.5 3169901000010 ENDDATA 3 0 3169901000011 ENDSUBENT 10 0 3169901099999 SUBENT 31699011 20110120 31493169901100001 BIB 2 4 3169901100002 REACTION (92-U-238(N,G)92-U-239,,SIG,,,DERIV) 3169901100003 STATUS (DEP,31699010) Q0 value (ratio of resonance integral 3169901100004 to thermal neutron capture cross section at a neutron 3169901100005 velocity of 2200 m/s) 3169901100006 ENDBIB 4 0 3169901100007 NOCOMMON 0 0 3169901100008 DATA 3 1 3169901100009 EN DATA DATA-ERR 3169901100010 EV B B 3169901100011 0.0253 2.73 0.03 3169901100012 ENDDATA 3 0 3169901100013 ENDSUBENT 12 0 3169901199999 SUBENT 31699012 20110120 31493169901200001 BIB 1 2 3169901200002 REACTION ((79-AU-197(N,G)79-AU-198,,RI)// 3169901200003 (79-AU-197(N,G)79-AU-198,,SIG)) 3169901200004 ENDBIB 2 0 3169901200005 NOCOMMON 0 0 3169901200006 DATA 4 1 3169901200007 EN-MIN-NM EN-DN DATA DATA-ERR 3169901200008 EV EV NO-DIM NO-DIM 3169901200009 0.55 0.0253 15.6 0.3 3169901200010 ENDDATA 3 0 3169901200011 ENDSUBENT 10 0 3169901299999 SUBENT 31699013 20110120 31493169901300001 BIB 2 4 3169901300002 REACTION (79-AU-197(N,G)79-AU-198,,SIG,,,DERIV) 3169901300003 STATUS (DEP,31699012) Q0 value (ratio of resonance integral 3169901300004 to thermal neutron capture cross section at a neutron 3169901300005 velocity of 2200 m/s) 3169901300006 ENDBIB 4 0 3169901300007 NOCOMMON 0 0 3169901300008 DATA 3 1 3169901300009 EN DATA DATA-ERR 3169901300010 EV B B 3169901300011 0.0253 98.7 0.1 3169901300012 ENDDATA 3 0 3169901300013 ENDSUBENT 12 0 3169901399999 ENDENTRY 13 0 3169999999999