ENTRY 23719 20200817 22922371900000001 SUBENT 23719001 20200817 22922371900100001 BIB 12 23 2371900100002 TITLE Prompt gamma rays induced by inelastic scattering of 2371900100003 fission neutrons on iron 2371900100004 AUTHOR (Z.Ilic, E.Mauerhofer, C.Stieghorst, Z.Revay, 2371900100005 M.Rossbach, T.H.Randriamalala, T.Bruckel) 2371900100006 INSTITUTE (2GERJUL,2GERTHA,2GERMUN) 2371900100007 (2GERGER) Kreuzau, Germany 2371900100008 REFERENCE (J,JRN,325,641,2020) 2371900100009 #doi:10.1007/s10967-020-07271-w 2371900100010 FACILITY (REAC,2GERMUN) FRM II research reactor at Forschungs- 2371900100011 Neutronenquelle Heinz-Maier-Leibnitz. FaNGaS (Fast 2371900100012 Neutron induced Gamma Spectrometry) instrument. 2371900100013 REL-REF (I,,T.H.Randriamalala+,J,NIM/A,806,370,2016) 2371900100014 (I,,M.Rossbach+,J,JRN,309,149,2016) 2371900100015 FaNGaS instrument 2371900100016 ANALYSIS Prompt gamma-ray analysis. The cross sections in "mb" 2371900100017 represent the gamma-rays emission probabilities at an 2371900100018 angle of 90 degrees between neutron beam and detector 2371900100019 including the solid angle supported by the detector. 2371900100020 METHOD (GSPEC) 2371900100021 EN-SEC (E,G) 2371900100022 SAMPLE Iron foil with mass of 1.282 g 2371900100023 DETECTOR (HPGE) 2371900100024 HISTORY (20200817C) VS 2371900100025 ENDBIB 23 0 2371900100026 NOCOMMON 0 0 2371900100027 ENDSUBENT 26 0 2371900199999 SUBENT 23719002 20200817 22922371900200001 BIB 3 5 2371900200002 REACTION ((26-FE-56(N,INL)26-FE-56,,SPC,,SPA)// 2371900200003 (26-FE-56(N,INL)26-FE-56,,SPC,,SPA)) 2371900200004 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900200005 STATUS (TABLE) Table 2 J. Radioanal. Nucl. Chem. 325(2020)841 2371900200006 (SUPPL,23719010) Neutron source spectrum 2371900200007 ENDBIB 5 0 2371900200008 COMMON 2 3 2371900200009 EN-DUMMY E-DN 2371900200010 MEV KEV 2371900200011 1. 846.86 2371900200012 ENDCOMMON 3 0 2371900200013 DATA 4 59 2371900200014 E-NM E-NM-ERR DATA DATA-ERR 2371900200015 KEV KEV NO-DIM NO-DIM 2371900200016 846.86 0.04 1.0000 2371900200017 948.3 0.3 0.0007 0.0002 2371900200018 956.1 0.2 0.0012 0.0002 2371900200019 976.8 0.2 0.0006 0.0002 2371900200020 1037.81 0.05 0.0182 0.0014 2371900200021 1172.15 0.09 0.0026 0.0002 2371900200022 1175.1 0.1 0.0020 0.0002 2371900200023 1238.3 0.05 0.0990 0.0092 2371900200024 1272.1 0.5 0.0007 0.0002 2371900200025 1303.52 0.07 0.0033 0.0003 2371900200026 1335.7 0.2 0.0014 0.0002 2371900200027 1386.6 0.4 0.0008 0.0001 2371900200028 1432.5 0.2 0.0006 0.0001 2371900200029 1575.8 0.2 0.0008 0.0001 2371900200030 1579.5 0.2 0.0006 0.0001 2371900200031 1650.4 0.5 0.0008 0.0001 2371900200032 1670.7 0.1 0.0019 0.0002 2371900200033 1771.7 0.1 0.0052 0.0005 2371900200034 1810.77 0.05 0.0632 0.0059 2371900200035 1852. 0.07 0.0029 0.0003 2371900200036 1882.3 0.4 0.0012 0.0001 2371900200037 2015.1 0.2 0.0017 0.0002 2371900200038 2034.66 0.06 0.0056 0.0006 2371900200039 2042.9 0.2 0.0011 0.0002 2371900200040 2079.9 0.2 0.0009 0.0001 2371900200041 2094.7 0.06 0.0120 0.0011 2371900200042 2113.11 0.07 0.0310 0.0029 2371900200043 2273.41 0.06 0.0195 0.0019 2371900200044 2372.6 0.5 0.0008 0.0002 2371900200045 2425.5 0.1 0.0020 0.0002 2371900200046 2470.2 0.2 0.0015 0.0004 2371900200047 2522.42 0.09 0.0153 0.0016 2371900200048 2574.4 0.2 0.0016 0.0002 2371900200049 2579.2 0.2 0.0012 0.0002 2371900200050 2598.9 0.2 0.0128 0.0015 2371900200051 2657. 0.3 0.0016 0.0002 2371900200052 2754.5 0.2 0.0020 0.0002 2371900200053 2759.1 0.1 0.0050 0.0005 2371900200054 2763.4 0.1 0.0044 0.0005 2371900200055 2793.9 0.3 0.0008 0.0002 2371900200056 2959.7 0.2 0.0015 0.0002 2371900200057 2983.2 0.1 0.0050 0.0005 2371900200058 3010. 0.4 0.0008 0.0002 2371900200059 3063.6 0.3 0.0012 0.0002 2371900200060 3151.6 0.4 0.0007 0.0001 2371900200061 3202.8 0.2 0.0033 0.0005 2371900200062 3253.8 0.2 0.0024 0.0003 2371900200063 3272.6 0.3 0.0010 0.0002 2371900200064 3370.2 0.2 0.0022 0.0003 2371900200065 3447.7 0.3 0.0068 0.0010 2371900200066 3547.5 0.2 0.0033 0.0005 2371900200067 3554.1 0.4 0.0020 0.0002 2371900200068 3600.7 0.2 0.0086 0.0010 2371900200069 3606. 0.2 0.0027 0.0005 2371900200070 3662.9 0.3 0.0027 0.0005 2371900200071 3763.7 0.4 0.0010 0.0002 2371900200072 3828.1 0.5 0.0009 0.0002 2371900200073 3833.8 0.5 0.0008 0.0002 2371900200074 4032.4 0.3 0.0013 0.0001 2371900200075 ENDDATA 61 0 2371900200076 ENDSUBENT 75 0 2371900299999 SUBENT 23719003 20200817 22922371900300001 BIB 3 5 2371900300002 REACTION ((26-FE-57(N,INL)26-FE-57,,SPC,,SPA)// 2371900300003 (26-FE-56(N,INL)26-FE-56,,SPC,,SPA)) 2371900300004 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900300005 STATUS (TABLE) Table 3 J. Radioanal. Nucl. Chem. 325(2020)841 2371900300006 (SUPPL,23719010) Neutron source spectrum 2371900300007 ENDBIB 5 0 2371900300008 COMMON 2 3 2371900300009 EN-DUMMY E-DN 2371900300010 MEV KEV 2371900300011 1. 846.86 2371900300012 ENDCOMMON 3 0 2371900300013 DATA 4 12 2371900300014 E-NM E-NM-ERR DATA DATA-ERR 2371900300015 KEV KEV NO-DIM NO-DIM 2371900300016 121.84 0.05 0.0128 0.0011 2371900300017 136.33 0.08 0.0013 0.0003 2371900300018 211.7 0.1 0.0010 0.0002 2371900300019 230.25 0.07 0.0009 0.0002 2371900300020 352.13 0.04 0.0099 0.0014 2371900300021 366.48 0.08 0.0031 0.0005 2371900300022 650.65 0.08 0.0016 0.0002 2371900300023 870.75 0.06 0.0034 0.0003 2371900300024 992.5 0.1 0.0008 0.0002 2371900300025 1298.9 0.1 0.0007 0.0004 2371900300026 1412.4 0.2 0.0005 0.0002 2371900300027 1814. 0.2 0.0020 0.0003 2371900300028 ENDDATA 14 0 2371900300029 ENDSUBENT 28 0 2371900399999 SUBENT 23719004 20200817 22922371900400001 BIB 3 5 2371900400002 REACTION ((26-FE-54(N,INL)26-FE-54,,SPC,,SPA)// 2371900400003 (26-FE-56(N,INL)26-FE-56,,SPC,,SPA)) 2371900400004 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900400005 STATUS (TABLE) Table 4 J. Radioanal. Nucl. Chem. 325(2020)841 2371900400006 (SUPPL,23719010) Neutron source spectrum 2371900400007 ENDBIB 5 0 2371900400008 COMMON 2 3 2371900400009 EN-DUMMY E-DN 2371900400010 MEV KEV 2371900400011 1. 846.86 2371900400012 ENDCOMMON 3 0 2371900400013 DATA 4 9 2371900400014 E-NM E-NM-ERR DATA DATA-ERR 2371900400015 KEV KEV NO-DIM NO-DIM 2371900400016 757.6 0.2 0.0006 0.0001 2371900400017 1130.46 0.06 0.0037 0.0004 2371900400018 1153.18 0.09 0.0015 0.0002 2371900400019 1408.32 0.05 0.0349 0.0029 2371900400020 1509.7 0.3 0.0008 0.0002 2371900400021 1550.47 0.04 0.0016 0.0003 2371900400022 1937.0 0.2 0.0010 0.0001 2371900400023 3095.4 0.6 0.0007 0.0002 2371900400024 3166.6 0.2 0.0013 0.0002 2371900400025 ENDDATA 11 0 2371900400026 ENDSUBENT 25 0 2371900499999 SUBENT 23719005 20200817 22922371900500001 BIB 3 5 2371900500002 REACTION ((26-FE-58(N,INL)26-FE-58,,SPC,,SPA)// 2371900500003 (26-FE-56(N,INL)26-FE-56,,SPC,,SPA)) 2371900500004 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900500005 STATUS (TABLE) Table 4 J. Radioanal. Nucl. Chem. 325(2020)841 2371900500006 (SUPPL,23719010) Neutron source spectrum 2371900500007 ENDBIB 5 0 2371900500008 COMMON 2 3 2371900500009 EN-DUMMY E-DN 2371900500010 MEV KEV 2371900500011 1. 846.86 2371900500012 ENDCOMMON 3 0 2371900500013 DATA 4 1 2371900500014 E-NM E-NM-ERR DATA DATA-ERR 2371900500015 KEV KEV NO-DIM NO-DIM 2371900500016 810.67 0.07 0.0041 0.0007 2371900500017 ENDDATA 3 0 2371900500018 ENDSUBENT 17 0 2371900599999 SUBENT 23719006 20200817 22922371900600001 BIB 3 4 2371900600002 REACTION (26-FE-56(N,INL)26-FE-56,PAR,SIG,G,SPA) 2371900600003 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900600004 STATUS (TABLE) Table 2 J. Radioanal. Nucl. Chem. 325(2020)841 2371900600005 (SUPPL,23719010) Neutron source spectrum 2371900600006 ENDBIB 4 0 2371900600007 COMMON 1 3 2371900600008 EN-DUMMY 2371900600009 MEV 2371900600010 1. 2371900600011 ENDCOMMON 3 0 2371900600012 DATA 4 59 2371900600013 E E-ERR DATA DATA-ERR 2371900600014 KEV KEV MB MB 2371900600015 846.86 0.04 586. 41. 2371900600016 948.3 0.3 0.43 0.10 2371900600017 956.1 0.2 0.67 0.13 2371900600018 976.8 0.2 0.37 0.10 2371900600019 1037.81 0.05 10.7 0.7 2371900600020 1172.15 0.09 1.5 0.1 2371900600021 1175.1 0.1 1.2 0.1 2371900600022 1238.30 0.05 58. 5. 2371900600023 1272.1 0.5 0.40 0.10 2371900600024 1303.52 0.07 1.9 0.2 2371900600025 1335.7 0.2 0.8 0.1 2371900600026 1386.6 0.4 0.48 0.07 2371900600027 1432.5 0.2 0.35 0.07 2371900600028 1575.8 0.2 0.47 0.07 2371900600029 1579.5 0.2 0.36 0.07 2371900600030 1650.4 0.5 0.49 0.09 2371900600031 1670.7 0.1 1.1 0.1 2371900600032 1771.7 0.1 3.1 0.3 2371900600033 1810.77 0.05 37. 3. 2371900600034 1852. 0.07 1.7 0.2 2371900600035 1882.3 0.4 0.70 0.07 2371900600036 2015.1 0.2 1.0 0.1 2371900600037 2034.66 0.06 3.3 0.3 2371900600038 2042.9 0.2 0.62 0.09 2371900600039 2079.9 0.2 0.53 0.08 2371900600040 2094.7 0.06 7.0 0.6 2371900600041 2113.11 0.07 18. 1. 2371900600042 2273.41 0.06 11. 1. 2371900600043 2372.6 0.5 0.47 0.09 2371900600044 2425.5 0.1 1.2 0.1 2371900600045 2470.2 0.2 0.9 0.2 2371900600046 2522.42 0.09 9.0 0.8 2371900600047 2574.4 0.2 0.9 0.1 2371900600048 2579.2 0.2 0.7 0.1 2371900600049 2598.9 0.2 7.5 0.8 2371900600050 2657.0 0.3 0.9 0.1 2371900600051 2754.5 0.2 1.2 0.1 2371900600052 2759.1 0.1 2.9 0.3 2371900600053 2763.4 0.1 2.6 0.3 2371900600054 2793.9 0.3 0.45 0.09 2371900600055 2959.7 0.2 0.9 0.1 2371900600056 2983.2 0.1 2.9 0.3 2371900600057 3010.0 0.4 0.47 0.09 2371900600058 3063.6 0.3 0.7 0.1 2371900600059 3151.6 0.4 0.38 0.08 2371900600060 3202.8 0.2 1.9 0.3 2371900600061 3253.8 0.2 1.4 0.1 2371900600062 3272.6 0.3 0.58 0.09 2371900600063 3370.2 0.2 1.3 0.1 2371900600064 3447.7 0.3 4.0 0.5 2371900600065 3547.5 0.2 1.9 0.3 2371900600066 3554.1 0.4 1.2 0.1 2371900600067 3600.7 0.2 5.1 0.6 2371900600068 3606.0 0.2 1.6 0.3 2371900600069 3662.9 0.3 1.6 0.3 2371900600070 3763.7 0.4 0.56 0.09 2371900600071 3828.1 0.5 0.52 0.09 2371900600072 3833.8 0.5 0.48 0.09 2371900600073 4032.4 0.3 0.79 0.03 2371900600074 ENDDATA 61 0 2371900600075 ENDSUBENT 74 0 2371900699999 SUBENT 23719007 20200817 22922371900700001 BIB 3 4 2371900700002 REACTION (26-FE-57(N,INL)26-FE-57,PAR,SIG,G,SPA) 2371900700003 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900700004 STATUS (TABLE) Table 3 J. Radioanal. Nucl. Chem. 325(2020)841 2371900700005 (SUPPL,23719010) Neutron source spectrum 2371900700006 ENDBIB 4 0 2371900700007 COMMON 1 3 2371900700008 EN-DUMMY 2371900700009 MEV 2371900700010 1. 2371900700011 ENDCOMMON 3 0 2371900700012 DATA 4 12 2371900700013 E E-ERR DATA DATA-ERR 2371900700014 KEV KEV MB MB 2371900700015 121.84 0.05 324. 24. 2371900700016 136.33 0.08 32. 7. 2371900700017 211.7 0.1 26. 6. 2371900700018 230.25 0.07 23. 4. 2371900700019 352.13 0.04 251. 32. 2371900700020 366.48 0.08 79. 13. 2371900700021 650.65 0.08 41. 5. 2371900700022 870.75 0.06 85. 8. 2371900700023 992.5 0.1 22. 5. 2371900700024 1298.9 0.1 18. 10. 2371900700025 1412.4 0.2 14. 4. 2371900700026 1814.0 0.2 52. 8. 2371900700027 ENDDATA 14 0 2371900700028 ENDSUBENT 27 0 2371900799999 SUBENT 23719008 20200817 22922371900800001 BIB 3 4 2371900800002 REACTION (26-FE-54(N,INL)26-FE-54,PAR,SIG,G,SPA) 2371900800003 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900800004 STATUS (TABLE) Table 4 J. Radioanal. Nucl. Chem. 325(2020)841 2371900800005 (SUPPL,23719010) Neutron source spectrum 2371900800006 ENDBIB 4 0 2371900800007 COMMON 1 3 2371900800008 EN-DUMMY 2371900800009 MEV 2371900800010 1. 2371900800011 ENDCOMMON 3 0 2371900800012 DATA 4 9 2371900800013 E E-ERR DATA DATA-ERR 2371900800014 KEV KEV MB MB 2371900800015 757.6 0.2 6. 1. 2371900800016 1130.46 0.06 34. 3. 2371900800017 1153.18 0.09 13. 1. 2371900800018 1408.32 0.05 321. 22. 2371900800019 1509.7 0.3 0.49 0.09 2371900800020 1550.47 0.04 14. 3. 2371900800021 1937.0 0.2 9. 1. 2371900800022 3095.4 0.6 6. 1. 2371900800023 3166.6 0.2 12. 2. 2371900800024 ENDDATA 11 0 2371900800025 ENDSUBENT 24 0 2371900899999 SUBENT 23719009 20200817 22922371900900001 BIB 3 4 2371900900002 REACTION (26-FE-58(N,INL)26-FE-58,PAR,SIG,G,SPA) 2371900900003 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 2371900900004 STATUS (TABLE) Table 4 J. Radioanal. Nucl. Chem. 325(2020)841 2371900900005 (SUPPL,23719010) Neutron source spectrum 2371900900006 ENDBIB 4 0 2371900900007 COMMON 1 3 2371900900008 EN-DUMMY 2371900900009 MEV 2371900900010 1. 2371900900011 ENDCOMMON 3 0 2371900900012 DATA 4 1 2371900900013 E E-ERR DATA DATA-ERR 2371900900014 KEV KEV MB MB 2371900900015 810.67 0.07 786. 130. 2371900900016 ENDDATA 3 0 2371900900017 ENDSUBENT 16 0 2371900999999 SUBENT 23719010 20200817 22922371901000001 BIB 1 34 2371901000002 SUPPL-INF (INCSP) The thermal neutrons were filtered from the 2371901000003 fast neutron beam by boron carbide plate with a 2371901000004 thickness of 1 cm and two lead plates with a total 2371901000005 thickness of 5 cm. The fast neutron spectrum in the 2371901000006 energy range 0.075-20 MeV at the sample position was 2371901000007 determined by means of the foil activation technique. 2371901000008 Neutron flux 2371901000009 Col. 1: Incident neutron energy min. value (MeV) 2371901000010 Col. 2: Incident neutron energy max. value (MeV) 2371901000011 Col. 3: Neutron flux (1/cm2s) 2371901000012 ------------------------------------------------ 2371901000013 0.86 0.91 2.73E+06 2371901000014 0.91 0.98 3.82E+06 2371901000015 0.98 1.16 8.37E+06 2371901000016 1.16 1.68 1.98E+07 2371901000017 1.68 2.36 2.52E+07 2371901000018 2.36 3.07 2.01E+07 2371901000019 3.07 3.83 1.37E+07 2371901000020 3.83 4.71 8.43E+06 2371901000021 4.71 5.65 4.53E+06 2371901000022 5.65 6.56 2.29E+06 2371901000023 6.56 7.49 1.38E+06 2371901000024 7.49 8.26 6.96E+05 2371901000025 8.26 9.02 4.38E+05 2371901000026 9.02 9.90 3.02E+05 2371901000027 9.90 10.56 1.05E+05 2371901000028 10.56 11.28 1.07E+05 2371901000029 11.28 12.09 7.20E+04 2371901000030 12.09 12.98 4.23E+04 2371901000031 12.98 13.97 2.40E+04 2371901000032 13.97 15.09 1.30E+04 2371901000033 15.09 16.69 7.32E+03 2371901000034 16.69 18.55 2.74E+03 2371901000035 18.55 20.76 5.16E+02 2371901000036 ENDBIB 34 0 2371901000037 NOCOMMON 0 0 2371901000038 NODATA 0 0 2371901000039 ENDSUBENT 38 0 2371901099999 ENDENTRY 10 0 2371999999999