ENTRY 20456 20190326 22782045600000001 SUBENT 20456001 20190326 22782045600100001 BIB 16 67 2045600100002 INSTITUTE (2UK ALD) 2045600100003 REFERENCE ((R,AWRE-O-89/70,1970)=(P,EANDC(UK)-126,1970)) 2045600100004 AUTHOR (R.E.Coles, D.Porter) 2045600100005 TITLE Elastic and inelastic scattering of neutrons in the 2045600100006 energy range 1.0 to 5.0 MeV by natural molybdenum 2045600100007 FACILITY (VDG,2UK ALD) AWRE 6 MV Van de Graaff accelerator. 2045600100008 INC-SOURCE (P-T) T(p,n)He-3 reaction, tritium gas target with 2045600100009 a 0.0003 cm thick Mo entrance foil and 760 torr gas 2045600100010 pressure. 2045600100011 INC-SPECT (EN-RSL) The incident neutron energies varied from 2045600100012 1 to 5 MeV energy spreads on source neutron energies 2045600100013 varied from 50 keV at 1.0 MeV neutron energy, to 2045600100014 30 keV at 3.0 MeV, to 20 keV at 5.0 MeV. These energy 2045600100015 spreads are almost entirely due to incident proton 2045600100016 energy loss in the gas cell. 2045600100017 SAMPLE Right cylinder of natural Mo, 2.0 cm. outer diam., 2045600100018 1.20 cm inner diam. and 4.99 cm long. 2045600100019 Purity better than 99% 2045600100020 METHOD (TOF) Time of flight, flight path = 1.747 m, 2045600100021 a second time of flight spectrometer, viewing the gas 2045600100022 target at a fixed angle, was used as a monitor to 2045600100023 compare neutron yields at different angles. 2045600100024 * The well known neutron group energies from 2045600100025 n-scattering of iron were used as time calibration 2045600100026 and a check on incident neutron energy. 2045600100027 DETECTOR (SCIN) Liquid scintillator (NE213) and measurement of 2045600100028 detector efficiency with n-energy. The extrapolation 2045600100029 of the counter efficiency curve from 4.2 to 5.0 MeV 2045600100030 was guided by past experience runs using d-d n-source.2045600100031 (LONGC) Two long counters, at 0. and 90. degr., were 2045600100032 used as relative neutron flux monitors for the 2045600100033 excitation function measurements. 2045600100034 In case of angular distributions two long counters 2045600100035 were used to intercompare runs at different incident 2045600100036 energies and so put this data on the same relative 2045600100037 scale for all incident neutron energies. 2045600100038 REL-REF (M,21328001,J.H.Towle,J,NP/A,117,657,1968) - experim. 2045600100039 procedures described 2045600100040 (M,,J.H.Towle+,J,NP/A,118,500,1968) - The neutron 2045600100041 detection system described 2045600100042 (R,,C.M.Lederer+,B,LEDERER-6,,,1967) - 2045600100043 Decay data and their uncertainties together with 2045600100044 further information from refs: 2045600100045 (R,,S.Monaro+,J,CJP,47,995,1969) - for Mo-94, 2045600100046 (R,,J.B.Moorhead+,J,PR,184,1205,1969) - for Mo-95 2045600100047 (R,,K.Hubenthal+,J,NP/A,128,577,1969) - for Mo-98. 2045600100048 ANALYSIS Most of the data analysis, including peak areas, 2045600100049 inelastic continuum analysis and repetitive 2045600100050 calculations were done on a PDP-7 computer. 2045600100051 MONITOR (1-H-1(N,EL)1-H-1,,DA) The scattering at 45 deg from 2045600100052 the polythene sample was measured. 2045600100053 MONIT-REF (,A.Horsley,J,ND/A,2,243,1966) 2045600100054 COMMENT The intension of this work is to provide detailed 2045600100055 experimental data in the range 1.0 to 5.0 MeV prior to2045600100056 an evaluation of scattering cross section for natural 2045600100057 Mo, no attempt has been made to compare the data with 2045600100058 theoretical predictions. 2045600100059 HISTORY (19710505C) 2045600100060 (20170430A) SD:Updated to new date formats,lower case. 2045600100061 REACTION code update in Subents 002,003,005,006. 2045600100062 Meaningless zeros deleted according to the presentation2045600100063 in the Tables. BIB update. Data for Subent 008 were 2045600100064 restored from archive. INC-SPECT update. 2045600100065 (20180123A) On. Major revisions in 002-006. 2045600100066 (20180821U) SD: Part of information from MONITOR moved 2045600100067 to METHOD. REL-REF was updated. 2045600100068 (20190326U) SD: Small corrections in Subents 002-007. 2045600100069 ENDBIB 67 0 2045600100070 NOCOMMON 0 0 2045600100071 ENDSUBENT 70 0 2045600199999 SUBENT 20456002 20190326 22782045600200001 BIB 8 41 2045600200002 REACTION (42-MO-0(N,EL)42-MO-0,,SIG) 2045600200003 ANALYSIS (INTAD) 2045600200004 CORRECTION .Corrections for multiple scattering and flux 2045600200005 attenuation were done using the Monte Carlo program 2045600200006 MAGGIE. 2045600200007 .the polythene scatterer was corrected using the 2045600200008 method by Levin (see REL-REF). 2045600200009 REL-REF (M,,J.B.Parker+,J,NIM,30,77,1964) - Monte Carlo program2045600200010 MAGGIE 2045600200011 (M,,J.S.Levin,R,LA-2177,1959) - appendix to report 2045600200012 La-2177(1959) 2045600200013 ERR-ANALYS (ERR-T) Factors included in error calculations 2045600200014 (combined in quadrature ) were: 2045600200015 - statistical errors on the peak counts, 2045600200016 (ERR-1) counter relative efficiency, 2045600200017 (ERR-2) Uncertainty in the H(n,n) cross sections 2045600200018 (ERR-3) Uncertainty in the correction for flux 2045600200019 attenuation and multiple scattering in the po1ythene 2045600200020 sample 2045600200021 (ERR-4,1.,2.1) Counting statistics in the H peak in the2045600200022 polythene scatterer runs, energy. These were less 2045600200023 than 1% except at 5.0 MeV incident neutron energy, 2045600200024 where they rose to 2.1%. 2045600200025 STATUS (TABLE) Table 6,pag. 22 of the AWRE-O-89/70. 2045600200026 (DEP,20456003) Diff. cr.sect. 2045600200027 COMMENT From the text of the article: It should be noted that 2045600200028 included in the data in table 1 are contributions to 2045600200029 the cross section from the 204 keV inelastic level, 2045600200030 which could not be resolved from the elastic peak. 2045600200031 According to the excitation function data for the 2045600200032 204 keV level, this will increase the elastic cross 2045600200033 section by at most 80 mb at 1.5 MeV, falling to 2045600200034 essentially zero contribution above 3.5 keV. This is 2045600200035 due to a single level in Mo-95 and was only separable 2045600200036 from the elastic peak in the excitation function 2045600200037 runs at 125.degr. 2045600200038 HISTORY (20170430A) SD: ANALYSIS, CORRECTION, COMMENT were 2045600200039 added. STATUS 'DEP' was added. DATA-ERR -> ERR-T. 2045600200040 EN-RSL -> EN-RSL-FW. 2045600200041 (20180123A) On. ERR-ANALYS revised. 2045600200042 (20190326U) SD: EN-RSL-FW -> EN-RSL. 2045600200043 ENDBIB 41 0 2045600200044 COMMON 3 3 2045600200045 ERR-1 ERR-2 ERR-3 2045600200046 PER-CENT PER-CENT PER-CENT 2045600200047 3.3 0.8 1. 2045600200048 ENDCOMMON 3 0 2045600200049 DATA 4 8 2045600200050 EN EN-RSL DATA ERR-T 2045600200051 MEV MEV B B 2045600200052 1.5 4.900 0.170 2045600200053 2.0 3.450 0.120 2045600200054 2.5 2.800 0.090 2045600200055 3.0 0.03 2.350 0.090 2045600200056 3.5 1.750 0.060 2045600200057 4.0 1.500 0.070 2045600200058 4.5 1.450 0.040 2045600200059 5.0 0.05 1.350 0.130 2045600200060 ENDDATA 10 0 2045600200061 ENDSUBENT 60 0 2045600299999 SUBENT 20456003 20190326 22782045600300001 BIB 7 39 2045600300002 REACTION (42-MO-0(N,EL)42-MO-0,,DA) 2045600300003 CORRECTION .Corrections for multiple scattering and flux 2045600300004 attenuation were done using the Monte Carlo program 2045600300005 MAGGIE. 2045600300006 .The polythene scatterer was corrected using the 2045600300007 method by Levin. 2045600300008 REL-REF (M,,J.B.Parker+,J,NIM,30,77,1964) - Monte Carlo program2045600300009 MAGGIE 2045600300010 (M,,J.S.Levin,R,LA-2177,1959) - appendix to report 2045600300011 La-2177(1959) 2045600300012 ERR-ANALYS (ERR-T) Factors included in error calculations 2045600300013 (combined in quadrature ) were: 2045600300014 - statistical errors on the peak counts, 2045600300015 (ERR-1) counter relative efficiency, 2045600300016 (ERR-2) Uncertainty in the H(n,n) cross sections 2045600300017 (ERR-3) Uncertainty in the correction for flux 2045600300018 attenuation and multiple scattering in the po1ythene 2045600300019 sample 2045600300020 (ERR-4,1.,2.1) counting statistics in the H peak in the2045600300021 polythene scatterer runs, energy. These were less 2045600300022 than 1% except at 5.0 MeV incident neutron energy, 2045600300023 where they rose to 2.1%. 2045600300024 COMMENT From the text of the article: It should be noted that 2045600300025 included in the data in table 1 are contributions to 2045600300026 the cross section from the 204 keV inelastic level, 2045600300027 which could not be resolved from the elastic peak. 2045600300028 According to our excitation function data for the 2045600300029 204 keV level, this will increase the elastic cross 2045600300030 section by at most 80 mb at 1.5 MeV, falling to 2045600300031 essentially zero contribution above 3.5 keV. This is 2045600300032 due to a single level in Mo-95 and was only separable 2045600300033 from the elastic peak in the excitation function 2045600300034 runs at 125.degr. 2045600300035 STATUS (TABLE) Table 1,pag. 17 of the AWRE-O-89/70. 2045600300036 HISTORY (20170430A) SD: ANALYSIS, CORRECTION, COMMENT were 2045600300037 added. STATUS 'DEP' was added. DATA-ERR -> ERR-T; 2045600300038 DATA -> DATA-CM. EN-RSL -> EN-RSL-FW. 2045600300039 (20180123A) On. ERR-ANALYS revised. 2045600300040 (20190326U) SD: EN-RSL-FW -> EN-RSL. 2045600300041 ENDBIB 39 0 2045600300042 COMMON 3 3 2045600300043 ERR-1 ERR-2 ERR-3 2045600300044 PER-CENT PER-CENT PER-CENT 2045600300045 3.3 0.8 1. 2045600300046 ENDCOMMON 3 0 2045600300047 DATA 5 80 2045600300048 EN EN-RSL COS-CM DATA-CM ERR-T 2045600300049 MEV MEV NO-DIM MB/SR MB/SR 2045600300050 1.5 -0.712 120. 5. 2045600300051 1.5 -0.508 99. 4. 2045600300052 1.5 -0.269 125. 5. 2045600300053 1.5 -0.011 170. 6. 2045600300054 1.5 0.163 235. 10. 2045600300055 1.5 0.333 320. 12. 2045600300056 1.5 0.492 465. 20. 2045600300057 1.5 0.637 680. 25. 2045600300058 1.5 0.762 935. 35. 2045600300059 1.5 0.863 1270. 45. 2045600300060 2.0 -0.712 75. 3. 2045600300061 2.0 -0.508 70. 3. 2045600300062 2.0 -0.269 84. 3. 2045600300063 2.0 -0.011 130. 5. 2045600300064 2.0 0.163 150. 6. 2045600300065 2.0 0.333 185. 7. 2045600300066 2.0 0.492 290. 10. 2045600300067 2.0 0.637 405. 15. 2045600300068 2.0 0.762 715. 25. 2045600300069 2.0 0.863 975. 35. 2045600300070 2.5 -0.712 49. 2. 2045600300071 2.5 -0.508 30. 1. 2045600300072 2.5 -0.269 59. 2. 2045600300073 2.5 -0.011 100. 4. 2045600300074 2.5 0.163 125. 5. 2045600300075 2.5 0.333 140. 5. 2045600300076 2.5 0.492 160. 6. 2045600300077 2.5 0.637 255. 10. 2045600300078 2.5 0.762 460. 20. 2045600300079 2.5 0.863 810. 30. 2045600300080 3.0 0.03 -0.712 44. 2. 2045600300081 3.0 0.03 -0.508 21. 1. 2045600300082 3.0 0.03 -0.269 44. 2. 2045600300083 3.0 0.03 -0.011 100. 4. 2045600300084 3.0 0.03 0.163 135. 5. 2045600300085 3.0 0.03 0.333 135. 5. 2045600300086 3.0 0.03 0.492 130. 5. 2045600300087 3.0 0.03 0.637 155. 6. 2045600300088 3.0 0.03 0.762 315. 12. 2045600300089 3.0 0.03 0.863 670. 25. 2045600300090 3.5 -0.712 33. 2. 2045600300091 3.5 -0.508 15. 1. 2045600300092 3.5 -0.269 23. 1. 2045600300093 3.5 -0.011 72. 3. 2045600300094 3.5 0.163 110. 4. 2045600300095 3.5 0.333 115. 4. 2045600300096 3.5 0.492 90. 3. 2045600300097 3.5 0.637 81. 3. 2045600300098 3.5 0.762 185. 7. 2045600300099 3.5 0.863 490. 20. 2045600300100 4.0 -0.712 34. 2. 2045600300101 4.0 -0.508 16. 1. 2045600300102 4.0 -0.269 12. 1. 2045600300103 4.0 -0.011 62. 3. 2045600300104 4.0 0.163 115. 4. 2045600300105 4.0 0.333 130. 5. 2045600300106 4.0 0.492 93. 4. 2045600300107 4.0 0.637 46. 2. 2045600300108 4.0 0.762 135. 5. 2045600300109 4.0 0.863 405. 15. 2045600300110 4.5 -0.712 36. 2. 2045600300111 4.5 -0.508 20. 1.5 2045600300112 4.5 -0.269 7.5 1. 2045600300113 4.5 -0.011 54. 3. 2045600300114 4.5 0.163 110. 4. 2045600300115 4.5 0.333 140. 6. 2045600300116 4.5 0.492 96. 4. 2045600300117 4.5 0.637 36. 2. 2045600300118 4.5 0.762 72. 3. 2045600300119 4.5 0.863 355. 15. 2045600300120 5.0 0.02 -0.712 32. 2. 2045600300121 5.0 0.02 -0.508 29. 2. 2045600300122 5.0 0.02 -0.269 6.7 0.6 2045600300123 5.0 0.02 -0.011 43. 2. 2045600300124 5.0 0.02 0.163 96. 4. 2045600300125 5.0 0.02 0.333 124. 5. 2045600300126 5.0 0.02 0.492 91. 4. 2045600300127 5.0 0.02 0.637 36. 2. 2045600300128 5.0 0.02 0.762 44. 3. 2045600300129 5.0 0.02 0.863 305. 12. 2045600300130 ENDDATA 82 0 2045600300131 ENDSUBENT 130 0 2045600399999 SUBENT 20456004 20190326 22782045600400001 BIB 7 34 2045600400002 REACTION (42-MO-0(N,INL)42-MO-0,PAR,SIG) 2045600400003 ANALYSIS (INTAD) 2045600400004 CORRECTION .Corrections for multiple scattering and flux 2045600400005 attenuation were done using the Monte Carlo program 2045600400006 MAGGIE. 2045600400007 .The polythene scatterer was corrected using the 2045600400008 method by Levin. 2045600400009 REL-REF (M,,J.B.Parker+,J,NIM,30,77,1964) - Monte Carlo program2045600400010 MAGGIE 2045600400011 (M,,J.S.Levin,R,LA-2177,1959) - appendix to report 2045600400012 La-2177(1959) 2045600400013 ERR-ANALYS (ERR-T) Factors included in error calculations 2045600400014 (combined in quadrature ) were: 2045600400015 - Statistical errors (dominant factor in general), 2045600400016 (ERR-1) counter relative efficiency, 2045600400017 (ERR-2) Uncertainty in the H(n,n) cross sections 2045600400018 (ERR-3) Uncertainty in the correction for flux 2045600400019 attenuation and multiple scattering in the po1ythene 2045600400020 sample 2045600400021 (ERR-4,1.,2.1) counting statistics in the H peak in the2045600400022 polythene scatterer runs, energy. These were less 2045600400023 than 1% except at 5.0 MeV incident neutron energy, 2045600400024 where they rose to 2.1%. 2045600400025 (ERR-5) Uncertainty in assessing the exact shape of the2045600400026 low energy tail and the consequent effect on 2045600400027 adjacent groups. 2045600400028 Total error also includes: 2045600400029 STATUS (TABLE) Table 6,pag. 22 of the AWRE-O-89/70. 2045600400030 (DEP,20456005) Part. cr.sect. 2045600400031 HISTORY (20170430A) SD: ANALYSIS, CORRECTION, STATUS 'DEP' were2045600400032 added. DATA-ERR -> ERR-T. E-LVL-MIN was added. 2045600400033 EN-RSL -> EN-RSL-FW. 2045600400034 (20180123A) On. ERR-ANALYS revised. 2045600400035 (20190326U) SD: EN-RSL-FW -> EN-RSL. 2045600400036 ENDBIB 34 0 2045600400037 COMMON 5 3 2045600400038 E-LVL-MIN ERR-1 ERR-2 ERR-3 ERR-5 2045600400039 KEV PER-CENT PER-CENT PER-CENT PER-CENT 2045600400040 536. 3.3 0.8 1. 7. 2045600400041 ENDCOMMON 3 0 2045600400042 DATA 4 8 2045600400043 EN EN-RSL DATA ERR-T 2045600400044 MEV MEV B B 2045600400045 1.5 0.909 0.135 2045600400046 2.0 1.926 0.250 2045600400047 2.5 1.981 0.220 2045600400048 3.0 0.03 2.071 0.220 2045600400049 3.5 1.687 0.190 2045600400050 4.0 1.733 0.230 2045600400051 4.5 1.846 0.250 2045600400052 5.0 0.05 1.880 0.370 2045600400053 ENDDATA 10 0 2045600400054 ENDSUBENT 53 0 2045600499999 SUBENT 20456005 20190326 22782045600500001 BIB 8 50 2045600500002 REACTION (42-MO-0(N,INL)42-MO-0,PAR,SIG) 2045600500003 ANALYSIS (INTAD) 2045600500004 Angular distribution measurements included a polythene2045600500005 scatterer run at each incident neutron energy to 2045600500006 obtain an absolute scale. 2045600500007 COMMENT Since natural Mo contains seven isotopes with 2045600500008 different level schemes, inelastically scattered 2045600500009 neutron spectra are complex. These spectra were split 2045600500010 into discrete groups of levels and an inelastic 2045600500011 continuum. Each group of levels contained one or more 2045600500012 levels from one or more isotopes. 2045600500013 E-LVL quantity given below was calculated from the 2045600500014 energies of the individual levels weighted by the 2045600500015 appropriate isotope abundances. 2045600500016 CORRECTION .Corrections for multiple scattering and flux 2045600500017 attenuation were done using the Monte Carlo program 2045600500018 MAGGIE. 2045600500019 .the polythene scatterer was corrected using the 2045600500020 method by Levin. 2045600500021 Impossible to separate the 204 keV inelastic peak 2045600500022 which was included in the elastic peak area. 2045600500023 REL-REF (M,,J.B.Parker+,J,NIM,30,77,1964) - Monte Carlo program2045600500024 MAGGIE 2045600500025 (M,,J.S.Levin,R,LA-2177,1959) - appendix to report 2045600500026 La-2177(1959) 2045600500027 ERR-ANALYS (ERR-T) Total errors vary from +- 4% to +- 20% where 2045600500028 the associated peaks in the time of flight spectra 2045600500029 are large or easily resolved, up to +- 50% for small 2045600500030 peaks. 2045600500031 Factors included in error calculations (combined in 2045600500032 quadrature ) were: 2045600500033 - Statistical errors (dominant factor in general), 2045600500034 (ERR-1) counter relative efficiency, 2045600500035 (ERR-2) Uncertainty in the H(n,n) cross sections 2045600500036 (ERR-3) Uncertainty in the correction for flux 2045600500037 attenuation and multiple scattering in the po1ythene 2045600500038 sample 2045600500039 (ERR-4,1.,2.1) counting statistics in the H peak in the2045600500040 polythene scatterer runs, energy. These were less 2045600500041 than 1% except at 5.0 MeV incident neutron energy, 2045600500042 where they rose to 2.1%. 2045600500043 (ERR-5) Uncertainty in assessing the exact shape of the2045600500044 low energy tail and the consequent effect on 2045600500045 adjacent groups. 2045600500046 STATUS (TABLE) Table 2,pag. 18 of the AWRE-O-89/70. 2045600500047 (COREL,20456006) data from excitation function runs 2045600500048 HISTORY (20170430A) SD: SF4=Mo-0 was added to REACTION code. 2045600500049 DATA-ERR -> ERR-T. EN-RSL -> EN-RSL-FW. 2045600500050 (20180123A) On. ERR-ANALYS revised. 2045600500051 (20190326U) SD: EN-RSL-FW -> EN-RSL. 2045600500052 ENDBIB 50 0 2045600500053 COMMON 4 3 2045600500054 ERR-1 ERR-2 ERR-3 ERR-5 2045600500055 PER-CENT PER-CENT PER-CENT PER-CENT 2045600500056 3.3 0.8 1. 7. 2045600500057 ENDCOMMON 3 0 2045600500058 DATA 5 46 2045600500059 EN EN-RSL E-LVL DATA ERR-T 2045600500060 MEV MEV MEV B B 2045600500061 1.5 0.536 0.105 0.017 2045600500062 1.5 0.680 0.042 0.012 2045600500063 1.5 0.778 0.535 0.045 2045600500064 1.5 0.869 0.175 0.050 2045600500065 1.5 1.045 0.052 0.025 2045600500066 2.0 0.536 0.036 0.013 2045600500067 2.0 0.680 0.080 0.013 2045600500068 2.0 0.778 0.310 0.030 2045600500069 2.0 0.869 0.150 0.025 2045600500070 2.0 1.045 0.250 0.035 2045600500071 2.5 0.536 0.021 0.003 2045600500072 2.5 0.680 0.040 0.010 2045600500073 2.5 0.778 0.290 0.025 2045600500074 2.5 0.869 0.110 0.015 2045600500075 2.5 1.045 0.090 0.017 2045600500076 2.5 1.270 0.032 0.009 2045600500077 2.5 1.410 0.038 0.009 2045600500078 2.5 1.500 0.360 0.015 2045600500079 2.5 1.600 0.150 0.021 2045600500080 3.0 0.03 0.778 0.125 0.015 2045600500081 3.0 0.03 0.869 0.055 0.007 2045600500082 3.0 0.03 1.045 0.090 0.016 2045600500083 3.0 0.03 1.270 0.032 0.016 2045600500084 3.0 0.03 1.410 0.034 0.013 2045600500085 3.0 0.03 1.500 0.165 0.010 2045600500086 3.0 0.03 1.600 0.170 0.020 2045600500087 3.5 0.778 0.044 0.008 2045600500088 3.5 0.869 0.035 0.014 2045600500089 3.5 1.045 0.023 0.007 2045600500090 3.5 1.270 0.020 0.006 2045600500091 3.5 1.410 0.021 0.006 2045600500092 3.5 1.500 0.130 0.011 2045600500093 3.5 1.600 0.064 0.004 2045600500094 4.0 0.778 0.017 0.007 2045600500095 4.0 0.869 0.006 0.003 2045600500096 4.0 1.045 0.028 0.010 2045600500097 4.0 1.270 0.017 0.010 2045600500098 4.0 1.500 0.115 0.010 2045600500099 4.5 0.778 0.007 0.004 2045600500100 4.5 0.869 0.003 0.002 2045600500101 4.5 1.045 0.005 0.0025 2045600500102 4.5 1.270 0.0065 0.0030 2045600500103 4.5 1.500 0.074 0.011 2045600500104 5.0 0.02 1.045 0.0018 0.0012 2045600500105 5.0 0.02 1.270 0.0027 0.0018 2045600500106 5.0 0.02 1.500 0.025 0.0075 2045600500107 ENDDATA 48 0 2045600500108 ENDSUBENT 107 0 2045600599999 SUBENT 20456006 20190326 22782045600600001 BIB 9 54 2045600600002 REACTION (42-MO-0(N,INL)42-MO-0,PAR,SIG) 2045600600003 ANALYSIS Two long counters were used to intercompare runs at 2045600600004 different incident energies and so put this data on 2045600600005 the same relative scale for all incident neutron 2045600600006 energies. This was converted to an absolute scale by 2045600600007 comparing the elastic cross sections for angular 2045600600008 distribution and excitation function data. 2045600600009 CORRECTION .Corrections for multiple scattering and flux 2045600600010 attenuation were done using the Monte Carlo program 2045600600011 MAGGIE. 2045600600012 REL-REF (M,,J.B.Parker+,J,NIM,30,77,1964) - Monte Carlo program2045600600013 MAGGIE 2045600600014 COMMENT Since natural Mo contains seven isotopes with 2045600600015 different level schemes, inelastically scattered 2045600600016 neutron spectra are complex. These spectra were split 2045600600017 into discrete groups of levels and an inelastic 2045600600018 continuum. Each group of levels contained one or more 2045600600019 levels from one or more isotopes. 2045600600020 E-LVL quantity given below was calculated from the 2045600600021 energies of the individual levels weighted by the 2045600600022 appropriate isotope abundances. 2045600600023 FLAG (1.) In the measurement of excitation function 2045600600024 data, two runs were made at 2.4 MeV incident energy. 2045600600025 ERR-ANALYS (ERR-T) Total errors vary from +- 4% to +- 20% where 2045600600026 the associated peaks in the time of flight spectra 2045600600027 are large or easily resolved, up to +- 50% for small 2045600600028 peaks. 2045600600029 Factors included in error calculations (combined in 2045600600030 quadrature ) were: 2045600600031 - Statistical errors (dominant factor in general), 2045600600032 (ERR-1) Uncertainty in counter relative efficiency, 2045600600033 (ERR-2) Uncertainties due to long counter dead time 2045600600034 correction and relative efficiency, scatterer 2045600600035 interference with 0 deg long counter data and 0 deg to2045600600036 90 deg ratio of d(sigma)/d(omega) for T(p,n) reaction.2045600600037 STATUS (TABLE) Table 3,pag. 19 of the AWRE-O-89/70. 2045600600038 (DEP,20456003) To put inelastic excitation cross 2045600600039 sections on an absolute scale, the elastic peak areas 2045600600040 were used. Two directly comparable sets were available,2045600600041 at 2.0 and 3.0 MeV incident neutron energy, and two 2045600600042 more, at 1.5 and 2.5 MeV, by comparison with excitation2045600600043 function values at 1.4 and 1.6 MeV and 2.4 and 2.6 MeV.2045600600044 From these four sets of absolute (from angular 2045600600045 distribution data) and relative (from excitation 2045600600046 function data) differential cross sections at 125.degr.2045600600047 for the elastically scattered neutrons, a factor was 2045600600048 calculated to put all the inelastic excitation 2045600600049 function data on an absolute cross section scale. 2045600600050 (COREL,20456005) data from angular distribution runs 2045600600051 HISTORY (20170430A) SD: SF4=Mo-0 was added to REACTION code. 2045600600052 DETECTOR was added. DATA-ERR -> ERR-T. BIB update. 2045600600053 EN-RSL -> EN-RSL-FW. 2045600600054 (20180123A) On. ERR-ANALYS revised. 2045600600055 (20190326A) SD: EN-RSL-FW -> EN-RSL. ANALYSIS added. 2045600600056 ENDBIB 54 0 2045600600057 COMMON 2 3 2045600600058 ERR-1 ERR-2 2045600600059 PER-CENT PER-CENT 2045600600060 3.3 4.8 2045600600061 ENDCOMMON 3 0 2045600600062 DATA 6 88 2045600600063 EN EN-RSL E-LVL DATA ERR-T FLAG 2045600600064 MEV MEV MEV B B NO-DIM 2045600600065 1.0 0.05 0.204 0.098 0.010 2045600600066 1.2 0.204 0.080 0.010 2045600600067 1.2 0.536 0.145 0.012 2045600600068 1.2 0.680 0.110 0.013 2045600600069 1.2 0.778 0.750 0.060 2045600600070 1.2 0.869 0.145 0.025 2045600600071 1.4 0.204 0.044 0.010 2045600600072 1.4 0.536 0.096 0.009 2045600600073 1.4 0.680 0.087 0.009 2045600600074 1.4 0.778 0.710 0.050 2045600600075 1.4 0.869 0.275 0.025 2045600600076 1.6 0.204 0.059 0.008 2045600600077 1.6 0.536 0.081 0.006 2045600600078 1.6 0.680 0.040 0.004 2045600600079 1.6 0.778 0.665 0.040 2045600600080 1.6 0.869 0.120 0.012 2045600600081 1.6 1.045 0.120 0.013 2045600600082 1.8 0.204 0.089 0.008 2045600600083 1.8 0.536 0.074 0.006 2045600600084 1.8 0.680 0.023 0.003 2045600600085 1.8 0.778 0.600 0.035 2045600600086 1.8 0.869 0.105 0.012 2045600600087 1.8 1.045 0.185 0.020 2045600600088 2.0 0.204 0.061 0.007 2045600600089 2.0 0.536 0.064 0.005 2045600600090 2.0 0.778 0.370 0.025 2045600600091 2.0 0.869 0.150 0.013 2045600600092 2.0 1.045 0.160 0.013 2045600600093 2.0 1.410 0.076 0.010 2045600600094 2.0 1.500 0.155 0.020 2045600600095 2.0 1.600 0.059 0.012 2045600600096 2.2 0.204 0.060 0.007 2045600600097 2.2 0.536 0.044 0.004 2045600600098 2.2 0.680 0.039 0.003 2045600600099 2.2 0.778 0.345 0.025 2045600600100 2.2 0.869 0.180 0.015 2045600600101 2.2 1.045 0.300 0.020 2045600600102 2.2 1.410 0.086 0.008 2045600600103 2.2 1.500 0.270 0.030 2045600600104 2.2 1.600 0.150 0.017 2045600600105 2.4 0.204 0.015 0.0025 1.2045600600106 2.4 0.204 0.029 0.0025 1.2045600600107 2.4 0.536 0.036 0.003 1.2045600600108 2.4 0.536 0.038 0.003 1.2045600600109 2.4 0.680 0.027 0.003 1.2045600600110 2.4 0.680 0.034 0.003 1.2045600600111 2.4 0.778 0.260 0.020 1.2045600600112 2.4 0.778 0.300 0.020 1.2045600600113 2.4 0.869 0.130 0.013 1.2045600600114 2.4 0.869 0.145 0.012 1.2045600600115 2.4 1.045 0.170 0.012 1.2045600600116 2.4 1.270 0.022 0.006 1.2045600600117 2.4 1.270 0.029 0.006 1.2045600600118 2.4 1.410 0.055 0.012 1.2045600600119 2.4 1.410 0.056 0.012 1.2045600600120 2.4 1.500 0.230 0.030 1.2045600600121 2.4 1.500 0.290 0.030 1.2045600600122 2.4 1.600 0.260 0.035 1.2045600600123 2.4 1.600 0.335 0.035 1.2045600600124 2.6 0.204 0.024 0.002 2045600600125 2.6 0.536 0.044 0.004 2045600600126 2.6 0.680 0.012 0.002 2045600600127 2.6 0.778 0.280 0.020 2045600600128 2.6 0.869 0.150 0.013 2045600600129 2.6 1.045 0.160 0.012 2045600600130 2.6 1.270 0.040 0.006 2045600600131 2.6 1.410 0.050 0.010 2045600600132 2.6 1.500 0.250 0.020 2045600600133 2.6 1.600 0.375 0.035 2045600600134 2.8 0.204 0.004 0.0010 2045600600135 2.8 0.536 0.018 0.002 2045600600136 2.8 0.680 0.020 0.002 2045600600137 2.8 0.778 0.260 0.020 2045600600138 2.8 0.869 0.052 0.004 2045600600139 2.8 1.045 0.082 0.006 2045600600140 2.8 1.270 0.060 0.005 2045600600141 2.8 1.410 0.041 0.006 2045600600142 2.8 1.500 0.170 0.017 2045600600143 2.8 1.600 0.200 0.025 2045600600144 3.0 0.03 0.536 0.010 0.0015 2045600600145 3.0 0.03 0.680 0.016 0.002 2045600600146 3.0 0.03 0.778 0.155 0.015 2045600600147 3.0 0.03 0.869 0.068 0.015 2045600600148 3.0 0.03 1.045 0.083 0.010 2045600600149 3.0 0.03 1.270 0.037 0.005 2045600600150 3.0 0.03 1.410 0.032 0.005 2045600600151 3.0 0.03 1.500 0.175 0.020 2045600600152 3.0 0.03 1.600 0.225 0.025 2045600600153 ENDDATA 90 0 2045600600154 ENDSUBENT 153 0 2045600699999 SUBENT 20456007 20190326 22782045600700001 BIB 6 15 2045600700002 REACTION (42-MO-0(N,TOT),,SIG) 2045600700003 COMMENT In obtaining the total cross section, values of the 2045600700004 (n,gamma) and (n,p) cross sections by J.Schmidt were 2045600700005 used (see REL-REF), although these are too small to 2045600700006 have any appreciable effect on the final value. 2045600700007 REL-REF (R,,J.J.Schmidt,R,KFK-120,1966) 2045600700008 ERR-ANALYS (DATA-ERR) Sum of uncertainties of elastic and 2045600700009 inelastic cr. sect. 2045600700010 STATUS (TABLE) Table 6,pag. 22 of the AWRE-O-89/70. 2045600700011 (DEP,20456002) el.cr.sect. 2045600700012 (DEP,20456004) inel.cr.sect. 2045600700013 and inelastic scattering to a continuum above 2045600700014 1600 keV level. 2045600700015 HISTORY (20170430A) SD: STATUS 'DEP' added. EN-RSL->EN-RSL-FW. 2045600700016 (20190326U) SD: EN-RSL-FW -> EN-RSL. 2045600700017 ENDBIB 15 0 2045600700018 NOCOMMON 0 0 2045600700019 DATA 4 8 2045600700020 EN EN-RSL DATA DATA-ERR 2045600700021 MEV MEV B B 2045600700022 1.5 5.830 0.300 2045600700023 2.0 5.390 0.370 2045600700024 2.5 4.800 0.310 2045600700025 3.0 0.03 4.440 0.310 2045600700026 3.5 3.450 0.250 2045600700027 4.0 3.250 0.300 2045600700028 4.5 3.310 0.290 2045600700029 5.0 0.05 3.250 0.500 2045600700030 ENDDATA 10 0 2045600700031 ENDSUBENT 30 0 2045600799999 SUBENT 20456008 20170430 22612045600800001 BIB 6 8 2045600800002 REACTION (42-MO-0(0,0),,TEM) 2045600800003 ANALYSIS A simple statistical evaporation model. 2045600800004 MISC-COL (MISC) Incident neutron energy 2045600800005 STATUS (TABLE) Table 5,pag. 21 of the AWRE-O-89/70. 2045600800006 ERR-ANALYS (DATA-ERR) The error on the nuclear temperature is 2045600800007 estimated to be +- 5%. 2045600800008 HISTORY (20170430S) SD: Data were restored from archive. 2045600800009 EN -> MISC. 2045600800010 ENDBIB 8 0 2045600800011 NOCOMMON 0 0 2045600800012 DATA 3 6 2045600800013 DATA DATA-ERR MISC 2045600800014 MEV MEV MEV 2045600800015 0.30 0.02 2.5 2045600800016 0.34 0.02 3.0 2045600800017 0.47 0.02 3.5 2045600800018 0.52 0.03 4.0 2045600800019 0.62 0.03 4.5 2045600800020 0.71 0.04 5.0 2045600800021 ENDDATA 8 0 2045600800022 ENDSUBENT 21 0 2045600899999 ENDENTRY 8 0 2045699999999