ENTRY 31733 20220617 32083173300000001 SUBENT 31733001 20220617 32083173300100001 BIB 14 32 3173300100002 TITLE Fast neutron spectrum unfolding of a TRIGA Mark II 3173300100003 reactor and measurement of spectrum-averaged cross 3173300100004 sections: integral tests of differential cross 3173300100005 sections of neutron threshold reactions 3173300100006 AUTHOR (M.S.Uddin, S.Sudar, S.M.Hossain, R.Khan, 3173300100007 M.A.Zulquarnain, S.M.Qaim) 3173300100008 INSTITUTE (3BANSAV,3HUNKOS,2GERJUL) 3173300100009 (3BANBAN) Bangladesh Atomic Energy Commission, Dhaka 3173300100010 REFERENCE (J,RCA,101,613,2013) 3173300100011 FACILITY (REAC,3BANSAV) 3MW TRIGA Mark II reactor. 3173300100012 INC-SOURCE (REAC) 3173300100013 SAMPLE High purity foils of several metals, namely Al, Ti, 3173300100014 Fe, Ni,Nb, Mo, In and Au, were cut in circular discs 3173300100015 with diameter of 1 cm and placed in an Al-container. 3173300100016 METHOD (ACTIV,GSPEC) Typical irradiation time was 40 min. 3173300100017 A short 10 min irradiation of In and Au foils. 3173300100018 DETECTOR (HPGE) 3173300100019 MONITOR (28-NI-58(N,P)27-CO-58,,SIG,,SPA) 3173300100020 DECAY-MON (27-CO-58-G,70.86D,DG,811.0,0.990) 3173300100021 ERR-ANALYS (ERR-T) Total uncertainties (7-9%) 3173300100022 (ERR-S,0.1,3.) Counting statistics (0.1-3%) 3173300100023 (ERR-1) Peak area analysis (2%) 3173300100024 (ERR-2) Efficiency of detector (5%) 3173300100025 (ERR-3,,0.1) Half-life of product (<0.1%) 3173300100026 (ERR-4,,0.2) Gamma-ray intensity (<0.2%) 3173300100027 (ERR-5) Sample mass (0.01%) 3173300100028 STATUS (TABLE) Table 3 of J,RCA,101,613,2013 3173300100029 HISTORY (20140103C) VS. 3173300100030 (20141212U) VS. BIB minor corrections. 3173300100031 (20180523A) On. ERR-ANALYS(ERR-T) corrected. 3173300100032 (20200722A) On. INC-SPECT moved 014 (new subentry) 3173300100033 (20220613U) VT. Revision in 014 3173300100034 ENDBIB 32 0 3173300100035 COMMON 6 3 3173300100036 EN-DUMMY MONIT MONIT-ERR ERR-1 ERR-2 ERR-5 3173300100037 MEV MB PER-CENT PER-CENT PER-CENT PER-CENT 3173300100038 1.5 91.2 6. 2. 5. 0.01 3173300100039 ENDCOMMON 3 0 3173300100040 ENDSUBENT 39 0 3173300199999 SUBENT 31733002 20200722 31973173300200001 BIB 4 4 3173300200002 REACTION (13-AL-27(N,A)11-NA-24,,SIG,,SPA) 3173300200003 DECAY-DATA (11-NA-24,14.96HR,DG,1368.6,1.) 3173300200004 STATUS (SUPPL,31733014) Neutron spectrum 3173300200005 HISTORY (20200722U) On. STATUS added. 3173300200006 ENDBIB 4 0 3173300200007 NOCOMMON 0 0 3173300200008 DATA 2 1 3173300200009 DATA ERR-T 3173300200010 MB MB 3173300200011 0.67 0.06 3173300200012 ENDDATA 3 0 3173300200013 ENDSUBENT 12 0 3173300299999 SUBENT 31733003 20200722 31973173300300001 BIB 4 4 3173300300002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,SPA) 3173300300003 DECAY-DATA (21-SC-46-G,83.82D,DG,889.0,0.9998) 3173300300004 STATUS (SUPPL,31733014) Neutron spectrum 3173300300005 HISTORY (20200722U) On. STATUS added. 3173300300006 ENDBIB 4 0 3173300300007 NOCOMMON 0 0 3173300300008 DATA 2 1 3173300300009 DATA ERR-T 3173300300010 MB MB 3173300300011 11.6 0.95 3173300300012 ENDDATA 3 0 3173300300013 ENDSUBENT 12 0 3173300399999 SUBENT 31733004 20200722 31973173300400001 BIB 4 4 3173300400002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,SPA) 3173300400003 DECAY-DATA (21-SC-47,3.35D,DG,159.3,0.683) 3173300400004 STATUS (SUPPL,31733014) Neutron spectrum 3173300400005 HISTORY (20200722U) On. STATUS added. 3173300400006 ENDBIB 4 0 3173300400007 NOCOMMON 0 0 3173300400008 DATA 2 1 3173300400009 DATA ERR-T 3173300400010 MB MB 3173300400011 16.7 1.37 3173300400012 ENDDATA 3 0 3173300400013 ENDSUBENT 12 0 3173300499999 SUBENT 31733005 20200722 31973173300500001 BIB 4 4 3173300500002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,SPA) 3173300500003 DECAY-DATA (21-SC-48,1.80D,DG,983.5,1.) 3173300500004 STATUS (SUPPL,31733014) Neutron spectrum 3173300500005 HISTORY (20200722U) On. STATUS added. 3173300500006 ENDBIB 4 0 3173300500007 NOCOMMON 0 0 3173300500008 DATA 2 1 3173300500009 DATA ERR-T 3173300500010 MB MB 3173300500011 0.28 0.023 3173300500012 ENDDATA 3 0 3173300500013 ENDSUBENT 12 0 3173300599999 SUBENT 31733006 20200722 31973173300600001 BIB 4 4 3173300600002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,SPA) 3173300600003 DECAY-DATA (25-MN-54,312.20D,DG,834.9,0.9998) 3173300600004 STATUS (SUPPL,31733014) Neutron spectrum 3173300600005 HISTORY (20200722U) On. STATUS added. 3173300600006 ENDBIB 4 0 3173300600007 NOCOMMON 0 0 3173300600008 DATA 2 1 3173300600009 DATA ERR-T 3173300600010 MB MB 3173300600011 72.5 6.00 3173300600012 ENDDATA 3 0 3173300600013 ENDSUBENT 12 0 3173300699999 SUBENT 31733007 20200722 31973173300700001 BIB 4 4 3173300700002 REACTION (26-FE-54(N,A)24-CR-51,,SIG,,SPA) 3173300700003 DECAY-DATA (24-CR-51,27.70D,DG,320.0,0.100) 3173300700004 STATUS (SUPPL,31733014) Neutron spectrum 3173300700005 HISTORY (20200722U) On. STATUS added. 3173300700006 ENDBIB 4 0 3173300700007 NOCOMMON 0 0 3173300700008 DATA 2 1 3173300700009 DATA ERR-T 3173300700010 MB MB 3173300700011 0.79 0.07 3173300700012 ENDDATA 3 0 3173300700013 ENDSUBENT 12 0 3173300799999 SUBENT 31733008 20200722 31973173300800001 BIB 4 4 3173300800002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,SPA) 3173300800003 DECAY-DATA (41-NB-92-M,10.15D,DG,934.5,0.990) 3173300800004 STATUS (SUPPL,31733014) Neutron spectrum 3173300800005 HISTORY (20200722U) On. STATUS added. 3173300800006 ENDBIB 4 0 3173300800007 NOCOMMON 0 0 3173300800008 DATA 2 1 3173300800009 DATA ERR-T 3173300800010 MB MB 3173300800011 6.62 0.54 3173300800012 ENDDATA 3 0 3173300800013 ENDSUBENT 12 0 3173300899999 SUBENT 31733009 20200722 31973173300900001 BIB 4 4 3173300900002 REACTION (42-MO-95(N,P)41-NB-95,,SIG,,SPA) 3173300900003 DECAY-DATA (41-NB-95-G,34.97D,DG,765.8,1.) 3173300900004 STATUS (SUPPL,31733014) Neutron spectrum 3173300900005 HISTORY (20200722U) On. STATUS added. 3173300900006 ENDBIB 4 0 3173300900007 NOCOMMON 0 0 3173300900008 DATA 2 1 3173300900009 DATA ERR-T 3173300900010 MB MB 3173300900011 0.15 0.013 3173300900012 ENDDATA 3 0 3173300900013 ENDSUBENT 12 0 3173300999999 SUBENT 31733010 20200722 31973173301000001 BIB 4 4 3173301000002 REACTION (42-MO-98(N,A)40-ZR-95,,SIG,,SPA) 3173301000003 DECAY-DATA (40-ZR-95,64.02D,DG,756.7,0.540) 3173301000004 STATUS (SUPPL,31733014) Neutron spectrum 3173301000005 HISTORY (20200722U) On. STATUS added. 3173301000006 ENDBIB 4 0 3173301000007 NOCOMMON 0 0 3173301000008 DATA 2 1 3173301000009 DATA ERR-T 3173301000010 MB MB 3173301000011 0.011 0.001 3173301000012 ENDDATA 3 0 3173301000013 ENDSUBENT 12 0 3173301099999 SUBENT 31733011 20200722 31973173301100001 BIB 4 4 3173301100002 REACTION (41-NB-93(N,2N)41-NB-92-M,,SIG,,SPA) 3173301100003 DECAY-DATA (41-NB-92-M,10.15D,DG,934.5,0.990) 3173301100004 STATUS (SUPPL,31733014) Neutron spectrum 3173301100005 HISTORY (20200722U) On. STATUS added. 3173301100006 ENDBIB 4 0 3173301100007 NOCOMMON 0 0 3173301100008 DATA 2 1 3173301100009 DATA ERR-T 3173301100010 MB MB 3173301100011 0.48 0.04 3173301100012 ENDDATA 3 0 3173301100013 ENDSUBENT 12 0 3173301199999 SUBENT 31733012 20200722 31973173301200001 BIB 4 4 3173301200002 REACTION (49-IN-113(N,INL)49-IN-113-M,,SIG,,SPA) 3173301200003 DECAY-DATA (49-IN-113-M,1.658HR,DG,391.69,0.642) 3173301200004 STATUS (SUPPL,31733014) Neutron spectrum 3173301200005 HISTORY (20200722U) On. STATUS added. 3173301200006 ENDBIB 4 0 3173301200007 NOCOMMON 0 0 3173301200008 DATA 2 1 3173301200009 DATA ERR-T 3173301200010 MB MB 3173301200011 133.7 10.70 3173301200012 ENDDATA 3 0 3173301200013 ENDSUBENT 12 0 3173301299999 SUBENT 31733013 20200722 31973173301300001 BIB 4 4 3173301300002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG,,SPA) 3173301300003 DECAY-DATA (49-IN-115-M,4.49HR,DG,336.2,0.4583) 3173301300004 STATUS (SUPPL,31733014) Neutron spectrum 3173301300005 HISTORY (20200722U) On. STATUS added. 3173301300006 ENDBIB 4 0 3173301300007 NOCOMMON 0 0 3173301300008 DATA 2 1 3173301300009 DATA ERR-T 3173301300010 MB MB 3173301300011 162.6 13.00 3173301300012 ENDDATA 3 0 3173301300013 ENDSUBENT 12 0 3173301399999 SUBENT 31733014 20220613 32083173301400001 BIB 2 94 3173301400002 SUPPL-INF (INCSP) The spectrum of fast neutrons having energies 3173301400003 from 0.5 to 20 MeV was unfolded by threshold 3173301400004 activation reactions and code SULSA. 3173301400005 Using the 58Ni(n,p)58Co reaction as monitor the flux 3173301400006 of neutrons above 0.5 MeV was determined to be about 3173301400007 9.98E+12 n/cm2/s at the reactor power of 1 MW. 3173301400008 The flux of thermal neutrons via the 197Au(n,g)198Au 3173301400009 reaction amounted to 2.48E+13 n/cm2/s/. 3173301400010 (Data received from Dr. Uddin 9 JAN 2014) 3173301400011 -------------------------- 3173301400012 Energy Neutron flux 3173301400013 (MeV) (n/cm2/s) 3173301400014 -------------------------- 3173301400015 0.375 1.5990E+12 3173301400016 0.625 1.3530E+12 3173301400017 0.875 1.1420E+12 3173301400018 1.125 9.7160E+11 3173301400019 1.375 8.3170E+11 3173301400020 1.625 7.0850E+11 3173301400021 1.875 5.8300E+11 3173301400022 2.125 5.0560E+11 3173301400023 2.375 4.3250E+11 3173301400024 2.625 3.6650E+11 3173301400025 2.875 3.0920E+11 3173301400026 3.125 2.5710E+11 3173301400027 3.375 2.1310E+11 3173301400028 3.625 1.8230E+11 3173301400029 3.875 1.4570E+11 3173301400030 4.125 1.2170E+11 3173301400031 4.375 1.0080E+11 3173301400032 4.625 8.4320E+10 3173301400033 4.875 7.0340E+10 3173301400034 5.125 6.0820E+10 3173301400035 5.375 5.2880E+10 3173301400036 5.625 4.3680E+10 3173301400037 5.875 3.7490E+10 3173301400038 6.125 3.2070E+10 3173301400039 6.375 2.7560E+10 3173301400040 6.625 2.3680E+10 3173301400041 6.875 2.0340E+10 3173301400042 7.125 1.6360E+10 3173301400043 7.375 1.4990E+10 3173301400044 7.625 1.2790E+10 3173301400045 7.875 1.0900E+10 3173301400046 8.125 9.2160E+09 3173301400047 8.375 7.8560E+09 3173301400048 8.625 6.6600E+09 3173301400049 8.875 5.6390E+09 3173301400050 9.125 4.7740E+09 3173301400051 9.375 4.0390E+09 3173301400052 9.625 3.4100E+09 3173301400053 9.875 2.8810E+09 3173301400054 10.15 2.4200E+09 3173301400055 10.4 2.0440E+09 3173301400056 10.65 1.7230E+09 3173301400057 10.9 1.4580E+09 3173301400058 11.15 1.2270E+09 3173301400059 11.4 1.0340E+09 3173301400060 11.65 8.7120E+08 3173301400061 11.9 7.3660E+08 3173301400062 12.15 6.2110E+08 3173301400063 12.4 5.2460E+08 3173301400064 12.65 4.4250E+08 3173301400065 12.9 3.7330E+08 3173301400066 13.15 3.3400E+08 3173301400067 13.4 2.6680E+08 3173301400068 13.65 2.2480E+08 3173301400069 13.9 1.9010E+08 3173301400070 14.15 1.6080E+08 3173301400071 14.4 1.3590E+08 3173301400072 14.65 1.1470E+08 3173301400073 14.9 9.6980E+07 3173301400074 15.15 8.2040E+07 3173301400075 15.4 6.9310E+07 3173301400076 15.65 5.8640E+07 3173301400077 15.9 4.9550E+07 3173301400078 16.15 4.1880E+07 3173301400079 16.4 3.5450E+07 3173301400080 16.65 2.9990E+07 3173301400081 16.9 2.5330E+07 3173301400082 17.15 2.1460E+07 3173301400083 17.4 1.8110E+07 3173301400084 17.65 1.5300E+07 3173301400085 17.9 1.2920E+07 3173301400086 18.15 1.0990E+07 3173301400087 18.4 9.3180E+06 3173301400088 18.65 7.8410E+06 3173301400089 18.9 6.6360E+06 3173301400090 19.15 5.6080E+06 3173301400091 19.4 4.7460E+06 3173301400092 19.65 4.0170E+06 3173301400093 19.9 3.3930E+06 3173301400094 HISTORY (20200722C) On 3173301400095 (20220613U) VT. SUPPL-INF: RESFN->INCSP replaced 3173301400096 ENDBIB 94 0 3173301400097 NOCOMMON 0 0 3173301400098 NODATA 0 0 3173301400099 ENDSUBENT 98 0 3173301499999 ENDENTRY 14 0 3173399999999