ENTRY M0922 20190110 M099M092200000001 SUBENT M0922001 20190110 M099M092200100001 BIB 9 32 M092200100002 TITLE Data on photoneutron reactions from various M092200100003 experiments for 133Cs, 138Ba and 209Bi nuclei. M092200100004 AUTHOR (V.V.Varlamov,B.S.Ishkhanov,V.N.Orlin, N.N.Peskov) M092200100005 REFERENCE (J,YF,79,(4),315,2016) M092200100006 #doi:10.7868/S004400271604022X M092200100007 (J,PAN,79,(4),501,2016) M092200100008 #doi:10.1134/S1063778816040219 M092200100009 English translation of YF,79,(4),315,2016. M092200100010 INSTITUTE (4RUSMOS) M092200100011 INC-SOURCE (QMPH,ARAD) M092200100012 ANALYSIS The joint analysis of data for total (g,xn) and M092200100013 partial (g,n), (g,2n) and (g,3n) reactions obtained M092200100014 in various experiments was carried out. The new M092200100015 approach to analysis of systematic disagreements M092200100016 between data was proposed on the base of new M092200100017 criteria of systematic uncertainties presence - M092200100018 specially proposed transitional multiplicity M092200100019 functions M092200100020 Fi-theor = SIG(g,in)/SIG(g,xn). M092200100021 Using these functions calculated in the frame of M092200100022 combined photonuclear reaction model new reliable M092200100023 and free from problems of neutron multiplicity M092200100024 sorting data for photoneutron partial reactions M092200100025 cross sections M092200100026 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M092200100027 were evaluated using experimental neutron yield M092200100028 reaction cross sections SIG-exp(g,xn). M092200100029 ERR-ANALYS (DATA-ERR) Mean-root-squared errors. M092200100030 STATUS (APRVD) Approved by V.Varlamov. M092200100031 HISTORY (20160808C) Data were compiled at the Russia MSU SINP M092200100032 CDFE by V.Varlamov. M092200100033 (20190110A) Corrected by V.Varlamov: STATUS. M092200100034 ENDBIB 32 0 M092200100035 NOCOMMON 0 0 M092200100036 ENDSUBENT 35 0 M092200199999 SUBENT M0922002 20160322 M084M092200200001 BIB 3 10 M092200200002 REACTION (55-CS-133(G,X)0-NN-1,UNW,SIG,,,EVAL) M092200200003 ANALYSIS The total neutron reaction cross section obtained as M092200200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M092200200005 STATUS Data plotted in Fig. 3. M092200200006 (DEP,M0922003) M092200200007 Evaluated (g,n) reaction cross section. M092200200008 (DEP,M0922004) M092200200009 Evaluated (g,2n) reaction cross section. M092200200010 (DEP,M0922005) M092200200011 Evaluated (g,3n) reaction cross section. M092200200012 ENDBIB 10 0 M092200200013 NOCOMMON 0 0 M092200200014 DATA 3 66 M092200200015 EN DATA DATA-ERR M092200200016 MEV MB MB M092200200017 9.05 4.25 3.11 M092200200018 9.36 22.37 7.88 M092200200019 9.67 32.69 8.95 M092200200020 9.98 39.14 10.34 M092200200021 10.31 61.99 14.33 M092200200022 10.60 54.16 13.01 M092200200023 10.90 54.67 11.79 M092200200024 11.22 69.87 15.97 M092200200025 11.52 76.37 17.32 M092200200026 11.83 85.16 18.96 M092200200027 12.14 102.70 22.25 M092200200028 12.45 119.60 25.51 M092200200029 12.76 144.80 30.29 M092200200030 13.07 165.40 34.22 M092200200031 13.38 192.90 39.44 M092200200032 13.69 251.20 50.29 M092200200033 14.00 258.00 51.03 M092200200034 14.31 278.80 54.42 M092200200035 14.62 309.20 59.57 M092200200036 14.93 322.90 61.77 M092200200037 15.24 326.80 62.28 M092200200038 15.55 300.60 57.80 M092200200039 15.86 288.60 53.59 M092200200040 16.17 266.80 52.22 M092200200041 16.48 242.10 48.44 M092200200042 16.79 214.20 44.96 M092200200043 17.10 206.40 44.50 M092200200044 17.41 187.30 42.10 M092200200045 17.72 162.20 38.08 M092200200046 18.03 146.00 35.46 M092200200047 18.34 129.70 32.35 M092200200048 18.65 126.20 31.64 M092200200049 18.96 122.70 31.37 M092200200050 19.27 106.20 27.77 M092200200051 19.58 95.50 25.45 M092200200052 19.89 91.45 24.80 M092200200053 20.20 95.57 25.80 M092200200054 20.51 82.28 22.71 M092200200055 20.82 75.35 21.18 M092200200056 21.13 71.20 20.15 M092200200057 21.43 69.17 19.73 M092200200058 21.75 68.15 19.49 M092200200059 22.06 73.72 20.74 M092200200060 22.36 69.97 20.12 M092200200061 22.67 64.42 17.37 M092200200062 22.98 61.62 18.22 M092200200063 23.29 57.77 17.69 M092200200064 23.60 55.22 17.04 M092200200065 23.91 43.78 14.77 M092200200066 24.22 47.54 15.68 M092200200067 24.53 43.08 14.85 M092200200068 24.84 42.56 14.83 M092200200069 25.15 35.42 13.76 M092200200070 25.46 34.43 14.16 M092200200071 25.77 35.08 15.04 M092200200072 26.08 29.44 15.29 M092200200073 26.39 44.05 19.07 M092200200074 27.01 29.44 17.55 M092200200075 27.32 36.82 19.03 M092200200076 27.63 29.82 17.05 M092200200077 27.94 26.04 16.05 M092200200078 28.25 17.58 13.42 M092200200079 28.56 27.00 16.55 M092200200080 28.87 20.55 14.76 M092200200081 29.18 20.86 16.89 M092200200082 29.49 20.62 19.57 M092200200083 ENDDATA 68 0 M092200200084 ENDSUBENT 83 0 M092200299999 SUBENT M0922003 20160322 M084M092200300001 BIB 4 23 M092200300002 REACTION ((55-CS-133(G,N)55-CS-132,,SIG,,,EVAL)+ M092200300003 (55-CS-133(G,N+P)54-XE-131,,SIG,,,EVAL)) M092200300004 ANALYSIS The contribution of partial reaction (g,n) cross M092200300005 section into the experimental total neutron yield M092200300006 reaction (g,xn) cross section obtained using M092200300007 quasimonoenergetic annihilation photons at Livermore M092200300008 (USA) was evaluated using specially theoretically M092200300009 calculated transitional multiplicity function - M092200300010 ratio M092200300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092200300012 by the way M092200300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M092200300014 REL-REF (R,L0014008,B.L.Berman+,J,PR,177,1745,1969) M092200300015 Experimental data for the total neutron yield M092200300016 reaction (g,xn)= (g,n) + 2(g,2n) + 3(g,3n) cross M092200300017 section. M092200300018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092200300019 Theoretical preequilibrium model of photonuclear M092200300020 reactions based on the Fermi gas densities. M092200300021 STATUS Data plotted in Fig. 3. M092200300022 (DEP,L0014008) M092200300023 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092200300024 + 3(g,3n) cross section. M092200300025 ENDBIB 23 0 M092200300026 NOCOMMON 0 0 M092200300027 DATA 3 66 M092200300028 EN DATA DATA-ERR M092200300029 MEV MB MB M092200300030 9.05 4.25 3.04 M092200300031 9.36 22.37 7.63 M092200300032 9.67 32.69 8.60 M092200300033 9.98 39.14 9.92 M092200300034 10.31 61.99 13.66 M092200300035 10.60 54.16 12.42 M092200300036 10.90 54.67 11.19 M092200300037 11.22 69.87 15.20 M092200300038 11.52 76.37 16.48 M092200300039 11.83 85.16 18.03 M092200300040 12.14 102.70 21.13 M092200300041 12.45 119.60 24.20 M092200300042 12.76 144.80 28.71 M092200300043 13.07 165.40 32.41 M092200300044 13.38 192.90 37.33 M092200300045 13.69 251.20 47.54 M092200300046 14.00 258.00 48.21 M092200300047 14.31 278.80 51.37 M092200300048 14.62 309.20 56.18 M092200300049 14.93 322.90 58.23 M092200300050 15.24 326.80 58.70 M092200300051 15.55 300.60 54.51 M092200300052 15.86 288.40 50.41 M092200300053 16.17 263.30 48.96 M092200300054 16.48 226.70 43.84 M092200300055 16.79 181.30 38.28 M092200300056 17.10 152.60 35.35 M092200300057 17.41 118.90 31.24 M092200300058 17.72 88.06 26.57 M092200300059 18.03 68.43 23.52 M092200300060 18.34 53.41 20.61 M092200300061 18.65 46.50 19.65 M092200300062 18.96 41.26 19.00 M092200300063 19.27 33.21 16.44 M092200300064 19.58 28.30 14.79 M092200300065 19.89 26.20 14.21 M092200300066 20.20 27.05 14.79 M092200300067 20.51 23.55 12.89 M092200300068 20.82 22.27 11.99 M092200300069 21.13 22.09 11.48 M092200300070 21.43 22.64 11.33 M092200300071 21.75 23.49 11.32 M092200300072 22.06 26.34 12.24 M092200300073 22.36 25.44 11.82 M092200300074 22.67 23.45 10.46 M092200300075 22.98 22.14 10.55 M092200300076 23.29 20.32 10.05 M092200300077 23.60 18.94 9.59 M092200300078 23.91 14.60 7.97 M092200300079 24.22 15.43 8.46 M092200300080 24.53 13.63 7.82 M092200300081 24.84 13.15 7.73 M092200300082 25.15 10.72 6.99 M092200300083 25.46 10.21 7.18 M092200300084 25.77 10.19 7.66 M092200300085 26.08 8.40 7.18 M092200300086 26.39 12.36 9.64 M092200300087 27.01 8.01 7.79 M092200300088 27.32 9.88 8.98 M092200300089 27.63 7.88 7.75 M092200300090 27.94 6.79 7.11 M092200300091 28.25 4.52 5.49 M092200300092 28.56 6.85 7.42 M092200300093 28.87 5.14 6.22 M092200300094 29.18 5.15 6.80 M092200300095 29.49 5.03 7.44 M092200300096 ENDDATA 68 0 M092200300097 ENDSUBENT 96 0 M092200399999 SUBENT M0922004 20160322 M084M092200400001 BIB 4 22 M092200400002 REACTION ((55-CS-133(G,2N)55-CS-131,,SIG,,,EVAL)+ M092200400003 (55-CS-133(G,2N+P)54-XE-130,,SIG,,,EVAL)) M092200400004 ANALYSIS The contribution of partial reaction (g,n) cross M092200400005 section into the experimental total neutron yield M092200400006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M092200400007 obtained using quasimonoenergetic annihilation M092200400008 photons at Livermore (USA) was evaluated using M092200400009 specially theoretically calculated transitional M092200400010 multiplicity function - ratio M092200400011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092200400012 by the way M092200400013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092200400014 REL-REF (R,L0014008,B.L.Berman+,J,PR,177,1745,1969) M092200400015 Experimental data for the total neutron yield M092200400016 reaction (g,xn) cross section. M092200400017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092200400018 Theoretical preequilibrium model of photonuclear M092200400019 reactions based on the Fermi gas densities. M092200400020 STATUS Data plotted in Fig. 3. M092200400021 (DEP,L0014008) M092200400022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) + M092200400023 3(g,3n) cross section. M092200400024 ENDBIB 22 0 M092200400025 NOCOMMON 0 0 M092200400026 DATA 3 44 M092200400027 EN DATA DATA-ERR M092200400028 MEV MB MB M092200400029 15.86 0.26 3.07 M092200400030 16.17 3.52 3.17 M092200400031 16.48 15.38 4.50 M092200400032 16.79 32.93 6.59 M092200400033 17.10 53.73 9.06 M092200400034 17.41 68.41 10.77 M092200400035 17.72 74.17 11.43 M092200400036 18.03 77.53 11.87 M092200400037 18.34 76.29 11.67 M092200400038 18.65 79.65 11.91 M092200400039 18.96 81.41 12.30 M092200400040 19.27 72.98 11.27 M092200400041 19.58 67.19 10.60 M092200400042 19.89 65.25 10.53 M092200400043 20.20 68.52 10.95 M092200400044 20.51 58.73 9.76 M092200400045 20.82 53.08 9.14 M092200400046 21.13 49.11 8.63 M092200400047 21.43 46.53 8.35 M092200400048 21.75 44.66 8.13 M092200400049 22.06 47.38 8.46 M092200400050 22.36 44.53 8.26 M092200400051 22.67 40.98 6.87 M092200400052 22.98 39.47 7.63 M092200400053 23.29 37.44 7.60 M092200400054 23.60 36.29 7.42 M092200400055 23.91 29.18 6.78 M092200400056 24.22 32.11 7.19 M092200400057 24.53 29.45 7.01 M092200400058 24.84 29.41 7.08 M092200400059 25.15 24.70 6.75 M092200400060 25.46 24.21 6.95 M092200400061 25.77 24.82 7.34 M092200400062 26.08 20.81 8.01 M092200400063 26.39 30.82 9.16 M092200400064 27.01 19.44 8.89 M092200400065 27.32 23.18 8.73 M092200400066 27.63 17.70 7.62 M092200400067 27.94 14.42 6.84 M092200400068 28.25 12.74 5.60 M092200400069 28.56 9.01 6.02 M092200400070 28.87 8.90 5.16 M092200400071 29.18 8.26 5.57 M092200400072 29.49 7.44 6.08 M092200400073 ENDDATA 46 0 M092200400074 ENDSUBENT 73 0 M092200499999 SUBENT M0922005 20160322 M084M092200500001 BIB 4 22 M092200500002 REACTION ((55-CS-133(G,3N)55-CS-130,,SIG,,,EVAL)+ M092200500003 (55-CS-133(G,3N+P)54-XE-129,,SIG,,,EVAL)) M092200500004 ANALYSIS The contribution of partial reaction (g,n) cross M092200500005 section into the experimental total neutron yield M092200500006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M092200500007 obtained using quasimonoenergetic annihilation M092200500008 photons at Livermore (USA) was evaluated using M092200500009 specially theoretically calculated transitional M092200500010 multiplicity function - ratio M092200500011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092200500012 by the way M092200500013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092200500014 REL-REF (R,L0014008,B.L.Berman+,J,PR,177,1745,1969) M092200500015 Experimental data for the total neutron yield M092200500016 reaction (g,xn) cross section. M092200500017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092200500018 Theoretical preequilibrium model of photonuclear M092200500019 reactions based on the Fermi gas densities. M092200500020 STATUS Data plotted in Fig. 3. M092200500021 (DEP,L0014008) M092200500022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) + M092200500023 3(g,3n) cross section. M092200500024 ENDBIB 22 0 M092200500025 NOCOMMON 0 0 M092200500026 DATA 3 13 M092200500027 EN DATA DATA-ERR M092200500028 MEV MB MB M092200500029 25.46 0.01 0.03 M092200500030 25.77 0.07 0.04 M092200500031 26.08 0.23 0.10 M092200500032 26.39 0.87 0.27 M092200500033 27.01 1.98 0.86 M092200500034 27.32 3.77 1.31 M092200500035 27.63 4.24 1.68 M092200500036 27.94 4.05 2.10 M092200500037 28.25 4.83 2.33 M092200500038 28.56 6.51 3.11 M092200500039 28.87 7.41 3.39 M092200500040 29.18 7.45 4.52 M092200500041 29.49 8.15 6.05 M092200500042 ENDDATA 15 0 M092200500043 ENDSUBENT 42 0 M092200599999 SUBENT M0922006 20160322 M084M092200600001 BIB 3 10 M092200600002 REACTION (56-BA-138(G,X)0-NN-1,UNW,SIG,,,EVAL) M092200600003 ANALYSIS The total neutron reaction cross section obtained as M092200600004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,2n). M092200600005 STATUS Data plotted in Fig. 5. M092200600006 (DEP,M0922007) M092200600007 Evaluated (g,n) reaction cross section. M092200600008 (DEP,M0922008) M092200600009 Evaluated (g,2n) reaction cross section. M092200600010 (DEP,M0922009) M092200600011 Evaluated (g,3n) reaction cross section. M092200600012 ENDBIB 10 0 M092200600013 NOCOMMON 0 0 M092200600014 DATA 3 61 M092200600015 EN DATA DATA-ERR M092200600016 MEV MB MB M092200600017 8.48 1.50 1.03 M092200600018 8.79 14.27 3.94 M092200600019 9.10 21.48 4.59 M092200600020 9.41 35.57 7.37 M092200600021 9.72 30.58 5.86 M092200600022 10.03 37.12 6.73 M092200600023 10.34 41.58 7.38 M092200600024 10.65 52.84 8.96 M092200600025 10.96 54.26 7.94 M092200600026 11.27 63.67 10.45 M092200600027 11.57 78.22 12.83 M092200600028 11.89 83.91 12.80 M092200600029 12.19 101.20 14.73 M092200600030 12.50 122.10 17.42 M092200600031 12.81 147.80 20.81 M092200600032 13.12 170.60 23.65 M092200600033 13.43 194.10 26.80 M092200600034 13.74 214.10 29.34 M092200600035 14.05 245.70 32.33 M092200600036 14.36 267.80 34.97 M092200600037 14.67 307.00 40.00 M092200600038 14.98 319.20 41.56 M092200600039 15.29 335.80 43.83 M092200600040 15.60 314.50 41.42 M092200600041 15.91 302.00 39.90 M092200600042 16.22 260.70 37.07 M092200600043 16.53 235.40 34.56 M092200600044 16.84 207.20 31.48 M092200600045 17.15 176.00 27.81 M092200600046 17.46 161.30 26.88 M092200600047 17.77 141.10 23.64 M092200600048 18.08 135.20 23.10 M092200600049 18.39 122.40 21.17 M092200600050 18.70 112.40 19.82 M092200600051 19.01 96.60 17.56 M092200600052 19.32 91.64 17.53 M092200600053 19.63 81.62 16.10 M092200600054 19.94 76.22 15.32 M092200600055 20.25 74.98 15.02 M092200600056 20.56 79.58 16.11 M092200600057 20.87 63.18 13.64 M092200600058 21.18 67.42 14.44 M092200600059 21.48 74.04 15.63 M092200600060 21.80 68.52 14.83 M092200600061 22.11 45.51 11.33 M092200600062 22.41 46.95 10.18 M092200600063 22.72 45.47 11.01 M092200600064 23.03 49.91 11.81 M092200600065 23.34 49.25 11.80 M092200600066 23.65 38.99 10.15 M092200600067 23.96 33.88 9.48 M092200600068 24.27 29.88 9.20 M092200600069 24.58 22.46 7.78 M092200600070 24.89 24.93 9.03 M092200600071 25.20 33.42 10.50 M092200600072 25.51 26.17 10.25 M092200600073 25.82 17.41 8.54 M092200600074 26.13 20.44 9.36 M092200600075 26.44 26.09 10.99 M092200600076 26.75 20.93 9.85 M092200600077 27.06 16.53 9.05 M092200600078 ENDDATA 63 0 M092200600079 ENDSUBENT 78 0 M092200699999 SUBENT M0922007 20160322 M084M092200700001 BIB 4 22 M092200700002 REACTION ((56-BA-138(G,N)56-BA-137,,SIG,,,EVAL)+ M092200700003 (56-BA-138(G,N+P)55-CS-136,,SIG,,,EVAL)) M092200700004 ANALYSIS The contribution of partial reaction (g,n) cross M092200700005 section into the experimental total neutron yield M092200700006 reaction (g,xn) cross section obtained using M092200700007 quasimonoenergetic annihilation photons at Livermore M092200700008 (USA) was evaluated using specially theoretically M092200700009 calculated transitional multiplicity function - M092200700010 ratio M092200700011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092200700012 by the way M092200700013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M092200700014 REL-REF (R,L0019004,B.L.Berman+,J,PR/C,2,2318,1970) M092200700015 Experimental data for the total neutron yield M092200700016 reaction (g,xn)= (g,n) + 2(g,2n) cross section. M092200700017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092200700018 Theoretical preequilibrium model of photonuclear M092200700019 reactions based on the Fermi gas densities. M092200700020 STATUS Data plotted in Fig. 5. M092200700021 (DEP,L0019004) M092200700022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092200700023 + 3(g,3n) cross section19 M092200700024 ENDBIB 22 0 M092200700025 NOCOMMON 0 0 M092200700026 DATA 3 61 M092200700027 EN DATA DATA-ERR M092200700028 MEV MB MB M092200700029 8.48 1.50 0.95 M092200700030 8.79 14.27 3.73 M092200700031 9.10 21.48 4.35 M092200700032 9.41 35.57 6.97 M092200700033 9.72 30.58 5.52 M092200700034 10.03 37.12 6.32 M092200700035 10.34 41.58 6.91 M092200700036 10.65 52.84 8.37 M092200700037 10.96 54.26 7.34 M092200700038 11.27 63.67 9.74 M092200700039 11.57 78.22 11.96 M092200700040 11.89 83.91 11.86 M092200700041 12.19 101.20 13.61 M092200700042 12.50 122.10 16.06 M092200700043 12.81 147.80 19.16 M092200700044 13.12 170.60 21.75 M092200700045 13.43 194.10 24.63 M092200700046 13.74 214.10 26.95 M092200700047 14.05 245.70 29.60 M092200700048 14.36 267.80 31.99 M092200700049 14.67 307.00 36.58 M092200700050 14.98 319.10 38.00 M092200700051 15.29 333.90 39.97 M092200700052 15.60 304.30 37.04 M092200700053 15.91 275.00 34.17 M092200700054 16.22 216.00 29.96 M092200700055 16.53 171.90 25.97 M092200700056 16.84 130.10 21.93 M092200700057 17.15 94.19 18.07 M092200700058 17.46 73.83 16.36 M092200700059 17.77 56.17 13.79 M092200700060 18.08 47.66 12.98 M092200700061 18.39 38.71 11.55 M092200700062 18.70 32.42 10.52 M092200700063 19.01 25.83 9.06 M092200700064 19.32 22.89 8.70 M092200700065 19.63 19.11 7.77 M092200700066 19.94 16.89 7.24 M092200700067 20.25 15.93 7.06 M092200700068 20.56 16.34 7.48 M092200700069 20.87 12.61 6.08 M092200700070 21.18 13.15 6.44 M092200700071 21.48 14.24 7.00 M092200700072 21.80 13.27 6.56 M092200700073 22.11 9.01 4.67 M092200700074 22.41 9.55 4.54 M092200700075 22.72 9.46 4.66 M092200700076 23.03 10.53 5.08 M092200700077 23.34 10.48 5.05 M092200700078 23.65 8.33 4.18 M092200700079 23.96 7.25 3.77 M092200700080 24.27 6.42 3.51 M092200700081 24.58 4.85 2.83 M092200700082 24.89 5.39 3.23 M092200700083 25.20 7.21 4.09 M092200700084 25.51 5.61 3.73 M092200700085 25.82 3.68 2.92 M092200700086 26.13 4.25 3.28 M092200700087 26.44 5.33 3.99 M092200700088 26.75 4.18 3.41 M092200700089 27.06 3.22 2.94 M092200700090 ENDDATA 63 0 M092200700091 ENDSUBENT 90 0 M092200799999 SUBENT M0922008 20160322 M084M092200800001 BIB 4 22 M092200800002 REACTION ((56-BA-138(G,2N)56-BA-136,,SIG,,,EVAL)+ M092200800003 (56-BA-138(G,2N+P)55-CS-135,,SIG,,,EVAL)) M092200800004 ANALYSIS The contribution of partial reaction (g,n) cross M092200800005 section into the experimental total neutron yield M092200800006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M092200800007 obtained using quasimonoenergetic annihilation M092200800008 photons at Livermore (USA) was evaluated using M092200800009 specially theoretically calculated transitional M092200800010 multiplicity function - ratio M092200800011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092200800012 by the way M092200800013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092200800014 REL-REF (R,L0019004,B.L.Berman+,J,PR/C,2,2318,1970) M092200800015 Experimental data for the total neutron yield M092200800016 reaction (g,xn)= (g,n) + 2(g,2n)cross section. M092200800017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092200800018 Theoretical preequilibrium model of photonuclear M092200800019 reactions based on the Fermi gas densities. M092200800020 STATUS Data plotted in Fig. 5. M092200800021 (DEP,L0019004) M092200800022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092200800023 + 3(g,3n) cross section. M092200800024 ENDBIB 22 0 M092200800025 NOCOMMON 0 0 M092200800026 DATA 3 40 M092200800027 EN DATA DATA-ERR M092200800028 MEV MB MB M092200800029 14.98 0.08 3.41 M092200800030 15.29 1.88 3.70 M092200800031 15.60 10.24 4.23 M092200800032 15.91 26.99 5.58 M092200800033 16.22 44.65 6.97 M092200800034 16.53 63.49 8.45 M092200800035 16.84 77.13 9.42 M092200800036 17.15 81.78 9.62 M092200800037 17.46 87.51 10.41 M092200800038 17.77 84.97 9.74 M092200800039 18.08 87.56 10.01 M092200800040 18.39 83.66 9.52 M092200800041 18.70 79.94 9.21 M092200800042 19.01 70.77 8.43 M092200800043 19.32 68.74 8.75 M092200800044 19.63 62.51 8.26 M092200800045 19.94 59.33 8.02 M092200800046 20.25 59.05 7.90 M092200800047 20.56 63.24 8.56 M092200800048 20.87 50.58 7.51 M092200800049 21.18 54.28 7.95 M092200800050 21.48 59.80 8.56 M092200800051 21.80 55.25 8.21 M092200800052 22.11 36.50 6.62 M092200800053 22.41 37.40 5.59 M092200800054 22.72 36.02 6.31 M092200800055 23.03 39.38 6.69 M092200800056 23.34 38.77 6.71 M092200800057 23.65 30.66 5.95 M092200800058 23.96 26.63 5.68 M092200800059 24.27 23.46 5.66 M092200800060 24.58 17.61 4.93 M092200800061 24.89 19.53 5.78 M092200800062 25.20 26.14 6.37 M092200800063 25.51 20.30 6.42 M092200800064 25.82 13.26 5.43 M092200800065 26.13 15.17 5.71 M092200800066 26.44 18.70 6.34 M092200800067 26.75 14.36 5.57 M092200800068 27.06 10.75 5.00 M092200800069 ENDDATA 42 0 M092200800070 ENDSUBENT 69 0 M092200899999 SUBENT M0922009 20160322 M084M092200900001 BIB 4 22 M092200900002 REACTION ((56-BA-138(G,3N)56-BA-135,,SIG,,,EVAL)+ M092200900003 (56-BA-138(G,3N+P)55-CS-134,,SIG,,,EVAL)) M092200900004 ANALYSIS The contribution of partial reaction (g,n) cross M092200900005 section into the experimental total neutron yield M092200900006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M092200900007 obtained using quasimonoenergetic annihilation M092200900008 photons at Livermore (USA) was evaluated using M092200900009 specially theoretically calculated transitional M092200900010 multiplicity function - ratio M092200900011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092200900012 by the way M092200900013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092200900014 REL-REF (R,L0019004,B.L.Berman+,J,PR/C,2,2318,1970) M092200900015 Experimental data for the total neutron yield M092200900016 reaction (g,xn)= (g,n) + 2(g,2n)cross section. M092200900017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092200900018 Theoretical preequilibrium model of photonuclear M092200900019 reactions based on the Fermi gas densities. M092200900020 STATUS Data plotted in Fig. 5. M092200900021 (DEP,L0019004) M092200900022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092200900023 + 3(g,3n) cross section. M092200900024 ENDBIB 22 0 M092200900025 NOCOMMON 0 0 M092200900026 DATA 3 7 M092200900027 EN DATA DATA-ERR M092200900028 MEV MB MB M092200900029 25.20 0.07 0.04 M092200900030 25.51 0.27 0.10 M092200900031 25.82 0.47 0.20 M092200900032 26.13 1.01 0.37 M092200900033 26.44 2.06 0.66 M092200900034 26.75 2.40 0.87 M092200900035 27.06 2.56 1.11 M092200900036 ENDDATA 9 0 M092200900037 ENDSUBENT 36 0 M092200999999 SUBENT M0922010 20160322 M084M092201000001 BIB 3 10 M092201000002 REACTION (83-BI-209(G,X)0-NN-1,UNW,SIG,,,EVAL) M092201000003 ANALYSIS The total neutron reaction cross section obtained as M092201000004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M092201000005 STATUS Data plotted in Fig. 7. M092201000006 (DEP,M0922011) M092201000007 Evaluated (g,n) reaction cross section. M092201000008 (DEP,M0922012) M092201000009 Evaluated (g,2n) reaction cross section. M092201000010 (DEP,M0922013) M092201000011 Evaluated (g,3n) reaction cross section. M092201000012 ENDBIB 10 0 M092201000013 NOCOMMON 0 0 M092201000014 DATA 3 109 M092201000015 EN DATA DATA-ERR M092201000016 MEV MB MB M092201000017 8.01 37.96 7.16 M092201000018 8.17 36.71 6.98 M092201000019 8.32 42.47 7.60 M092201000020 8.48 47.50 8.27 M092201000021 8.63 70.00 13.42 M092201000022 8.79 47.50 8.27 M092201000023 8.94 70.00 13.43 M092201000024 9.10 73.50 13.91 M092201000025 9.25 59.50 12.17 M092201000026 9.41 80.00 14.69 M092201000027 9.56 74.50 14.49 M092201000028 9.72 92.50 17.20 M092201000029 9.87 92.00 17.15 M092201000030 10.03 112.50 18.62 M092201000031 10.18 112.00 19.59 M092201000032 10.34 112.00 18.56 M092201000033 10.49 135.00 21.37 M092201000034 10.65 145.00 22.48 M092201000035 10.80 162.50 24.71 M092201000036 10.96 181.00 26.78 M092201000037 11.11 199.50 29.22 M092201000038 11.27 226.00 31.17 M092201000039 11.42 237.00 33.81 M092201000040 11.57 274.00 37.91 M092201000041 11.73 275.50 38.51 M092201000042 11.89 302.00 47.26 M092201000043 12.04 324.00 50.43 M092201000044 12.19 332.50 49.91 M092201000045 12.35 358.00 53.57 M092201000046 12.50 384.00 57.28 M092201000047 12.66 426.00 67.64 M092201000048 12.81 425.50 66.88 M092201000049 12.97 530.00 80.27 M092201000050 13.12 478.00 73.21 M092201000051 13.28 510.00 77.80 M092201000052 13.43 511.50 77.29 M092201000053 13.59 544.00 82.67 M092201000054 13.74 501.00 77.29 M092201000055 13.90 515.00 79.98 M092201000056 14.05 515.00 78.25 M092201000057 14.21 454.00 66.72 M092201000058 14.36 477.70 68.09 M092201000059 14.52 444.20 66.91 M092201000060 14.67 407.10 64.50 M092201000061 14.83 371.30 60.15 M092201000062 14.98 368.30 56.64 M092201000063 15.14 324.30 53.47 M092201000064 15.29 338.20 54.83 M092201000065 15.45 293.70 46.31 M092201000066 15.60 277.80 46.77 M092201000067 15.76 264.50 47.19 M092201000068 15.91 242.40 44.27 M092201000069 16.07 228.80 40.63 M092201000070 16.22 206.90 40.81 M092201000071 16.38 205.60 39.75 M092201000072 16.53 206.60 43.30 M092201000073 16.68 186.50 40.62 M092201000074 16.84 162.20 36.94 M092201000075 17.00 167.30 37.80 M092201000076 17.15 149.50 34.62 M092201000077 17.30 147.20 34.33 M092201000078 17.46 174.70 39.16 M092201000079 17.61 149.80 35.12 M092201000080 17.77 135.50 32.43 M092201000081 17.92 118.30 29.93 M092201000082 18.08 120.10 30.40 M092201000083 18.23 108.80 28.09 M092201000084 18.39 105.90 28.15 M092201000085 18.54 109.80 28.22 M092201000086 18.70 99.75 26.43 M092201000087 18.85 93.66 25.71 M092201000088 19.01 117.00 30.59 M092201000089 19.32 84.70 23.99 M092201000090 19.47 96.80 26.54 M092201000091 19.63 83.67 25.68 M092201000092 19.78 83.49 25.25 M092201000093 19.94 75.92 22.88 M092201000094 20.09 81.80 25.39 M092201000095 20.25 102.50 32.60 M092201000096 20.40 91.02 30.49 M092201000097 20.56 89.28 24.59 M092201000098 20.71 78.19 23.30 M092201000099 20.87 83.04 23.94 M092201000100 21.02 67.43 20.93 M092201000101 21.18 72.88 22.34 M092201000102 21.33 81.50 24.99 M092201000103 21.48 83.30 24.31 M092201000104 21.64 89.11 25.42 M092201000105 21.80 73.21 22.40 M092201000106 21.95 88.49 29.80 M092201000107 22.11 72.25 21.92 M092201000108 22.26 68.32 22.15 M092201000109 22.41 74.43 24.17 M092201000110 22.57 65.58 25.81 M092201000111 22.72 54.69 20.31 M092201000112 22.88 76.89 24.72 M092201000113 23.03 69.70 22.72 M092201000114 23.19 40.90 18.24 M092201000115 23.34 54.72 27.08 M092201000116 23.65 74.19 27.87 M092201000117 23.96 36.37 21.11 M092201000118 24.27 50.04 24.01 M092201000119 24.58 57.51 26.04 M092201000120 24.89 49.48 24.99 M092201000121 25.20 45.96 22.67 M092201000122 25.51 34.54 21.80 M092201000123 25.82 51.43 27.57 M092201000124 26.13 46.46 29.77 M092201000125 26.44 65.55 32.64 M092201000126 ENDDATA 111 0 M092201000127 ENDSUBENT 126 0 M092201099999 SUBENT M0922011 20190110 M099M092201100001 BIB 5 25 M092201100002 REACTION ((83-BI-209(G,N)83-BI-208,,SIG,,,EVAL)+ M092201100003 (83-BI-209(G,N+P)82-PB-207,,SIG,,,EVAL)) M092201100004 ANALYSIS The contribution of partial reaction (g,n) cross M092201100005 section into the experimental total neutron yield M092201100006 reaction (g,xn) = (g,n) + 2(g,2n) + 2(g,2n) cross M092201100007 section obtained using quasimonoenergetic M092201100008 annihilation photons at Livermore (USA) was evaluated M092201100009 using specially theoretically calculated transitional M092201100010 multiplicity function ratio M092201100011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092201100012 by the way M092201100013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M092201100014 REL-REF (R,L0007011,R.R.Harvey+,J,PR,136,B126,1964) M092201100015 Experimental data for the total neutron yield M092201100016 reaction (g,xn) = (g,n) + 2(g,2n) + 3(g,3n) M092201100017 cross section. M092201100018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092201100019 Theoretical preequilibrium model of photonuclear M092201100020 reactions based on the Fermi gas densities. M092201100021 STATUS (TABLE) Data plotted in Fig. 7. M092201100022 (DEP,L0007011) M092201100023 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092201100024 + 2(g,2n) cross section. M092201100025 (SPSDD,M0912008) M092201100026 HISTORY (20190110A) Corrected by V.Varlamov: STATUS. M092201100027 ENDBIB 25 0 M092201100028 NOCOMMON 0 0 M092201100029 DATA 3 109 M092201100030 EN DATA DATA-ERR M092201100031 MEV MB MB M092201100032 8.01 37.96 7.09 M092201100033 8.17 36.71 6.91 M092201100034 8.32 42.47 7.53 M092201100035 8.48 47.50 8.18 M092201100036 8.63 70.00 13.29 M092201100037 8.79 47.50 8.18 M092201100038 8.94 70.00 13.30 M092201100039 9.10 73.50 13.78 M092201100040 9.25 59.50 12.06 M092201100041 9.41 80.00 14.54 M092201100042 9.56 74.50 14.36 M092201100043 9.72 92.50 17.03 M092201100044 9.87 92.00 16.98 M092201100045 10.03 112.50 18.41 M092201100046 10.18 112.00 19.38 M092201100047 10.34 112.00 18.35 M092201100048 10.49 135.00 21.12 M092201100049 10.65 145.00 22.21 M092201100050 10.80 162.50 24.41 M092201100051 10.96 181.00 26.45 M092201100052 11.11 199.50 28.85 M092201100053 11.27 226.00 30.75 M092201100054 11.42 237.00 33.36 M092201100055 11.57 274.00 37.41 M092201100056 11.73 275.50 38.00 M092201100057 11.89 302.00 46.70 M092201100058 12.04 324.00 49.82 M092201100059 12.19 332.50 49.29 M092201100060 12.35 358.00 52.90 M092201100061 12.50 384.00 56.58 M092201100062 12.66 426.00 66.84 M092201100063 12.81 425.50 66.09 M092201100064 12.97 530.00 79.28 M092201100065 13.12 478.00 72.33 M092201100066 13.28 510.00 76.85 M092201100067 13.43 511.50 76.34 M092201100068 13.59 544.00 81.66 M092201100069 13.74 501.00 76.36 M092201100070 13.90 515.00 79.02 M092201100071 14.05 515.00 77.30 M092201100072 14.21 453.90 65.87 M092201100073 14.36 477.50 67.19 M092201100074 14.52 443.30 66.01 M092201100075 14.67 404.80 63.50 M092201100076 14.83 364.60 58.80 M092201100077 14.98 352.00 54.14 M092201100078 15.14 301.60 50.23 M092201100079 15.29 307.30 50.81 M092201100080 15.45 258.90 41.98 M092201100081 15.60 234.70 41.14 M092201100082 15.76 212.90 40.33 M092201100083 15.91 185.80 36.72 M092201100084 16.07 166.70 32.85 M092201100085 16.22 142.90 31.72 M092201100086 16.38 134.20 30.05 M092201100087 16.53 127.10 31.44 M092201100088 16.68 108.00 28.39 M092201100089 16.84 88.29 24.89 M092201100090 17.00 85.68 24.72 M092201100091 17.15 72.03 21.98 M092201100092 17.30 66.80 21.13 M092201100093 17.46 74.79 23.89 M092201100094 17.61 60.64 20.61 M092201100095 17.77 51.96 18.60 M092201100096 17.92 43.12 16.46 M092201100097 18.08 41.73 16.50 M092201100098 18.23 36.16 14.83 M092201100099 18.39 33.74 14.54 M092201100100 18.54 33.66 14.52 M092201100101 18.70 29.50 13.32 M092201100102 18.85 26.82 12.59 M092201100103 19.01 32.53 15.19 M092201100104 19.32 22.40 11.31 M092201100105 19.47 25.11 12.61 M092201100106 19.63 21.34 11.54 M092201100107 19.78 20.98 11.37 M092201100108 19.94 18.84 10.26 M092201100109 20.09 20.09 11.22 M092201100110 20.25 24.97 14.18 M092201100111 20.40 22.05 12.98 M092201100112 20.56 21.56 11.39 M092201100113 20.71 18.88 10.44 M092201100114 20.87 20.08 10.85 M092201100115 21.02 16.36 9.23 M092201100116 21.18 17.77 9.87 M092201100117 21.33 19.99 11.12 M092201100118 21.48 20.59 11.03 M092201100119 21.64 22.22 11.75 M092201100120 21.80 18.43 10.01 M092201100121 21.95 22.48 12.90 M092201100122 22.11 18.51 9.89 M092201100123 22.26 17.64 9.80 M092201100124 22.41 19.35 10.66 M092201100125 22.57 17.16 10.65 M092201100126 22.72 14.38 8.54 M092201100127 22.88 20.29 11.06 M092201100128 23.03 18.43 10.07 M092201100129 23.19 10.83 7.24 M092201100130 23.34 14.51 10.37 M092201100131 23.65 19.66 11.72 M092201100132 23.96 9.56 7.70 M092201100133 24.27 12.94 9.21 M092201100134 24.58 14.58 10.47 M092201100135 24.89 12.23 9.48 M092201100136 25.20 11.07 9.15 M092201100137 25.51 8.15 8.07 M092201100138 25.82 11.93 10.27 M092201100139 26.13 10.58 11.63 M092201100140 26.44 14.76 12.49 M092201100141 ENDDATA 111 0 M092201100142 ENDSUBENT 141 0 M092201199999 SUBENT M0922012 20190110 M099M092201200001 BIB 5 25 M092201200002 REACTION ((83-BI-209(G,2N)83-BI-207,,SIG,,,EVAL)+ M092201200003 (83-BI-209(G,2N+P)82-PB-206,,SIG,,,EVAL)) M092201200004 ANALYSIS The contribution of partial reaction (g,n) cross M092201200005 section into the experimental total neutron yield M092201200006 reaction (g,xn) = (g,n) + 2(g,2n) + 3(g,3n) M092201200007 cross section obtained using M092201200008 quasimonoenergetic annihilation photons at Livermore M092201200009 (USA)was evaluated using specially theoretically M092201200010 calculated transitional multiplicity function - M092201200011 ratio M092201200012 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092201200013 by the way M092201200014 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092201200015 REL-REF (R,L0007011,R.R.Harvey+,J,PR,136,B126,1964) M092201200016 Experimental data for the total neutron yield M092201200017 reaction (g,xn) cross section. M092201200018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092201200019 Theoretical preequilibrium model of photonuclear M092201200020 reactions based on the Fermi gas densities. M092201200021 STATUS (TABLE) Data plotted in Fig. 7. M092201200022 (DEP,L0007011) M092201200023 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092201200024 cross section. M092201200025 (SPSDD,M0912009) M092201200026 HISTORY (20190110A) Corrected by V.Varlamov: STATUS. M092201200027 ENDBIB 25 0 M092201200028 NOCOMMON 0 0 M092201200029 DATA 3 71 M092201200030 EN DATA DATA-ERR M092201200031 MEV MB MB M092201200032 14.05 0.01 0.94 M092201200033 14.21 0.05 0.84 M092201200034 14.36 0.26 0.89 M092201200035 14.52 0.84 0.90 M092201200036 14.67 2.36 0.99 M092201200037 14.83 6.70 1.33 M092201200038 14.98 16.24 2.49 M092201200039 15.14 22.71 3.23 M092201200040 15.29 30.84 4.01 M092201200041 15.45 34.80 4.32 M092201200042 15.60 43.17 5.63 M092201200043 15.76 51.54 6.86 M092201200044 15.91 56.61 7.55 M092201200045 16.07 62.17 7.77 M092201200046 16.22 64.06 9.09 M092201200047 16.38 71.42 9.69 M092201200048 16.53 79.45 11.86 M092201200049 16.68 78.49 12.22 M092201200050 16.84 73.86 12.04 M092201200051 17.00 81.66 13.07 M092201200052 17.15 77.49 12.64 M092201200053 17.30 80.36 13.20 M092201200054 17.46 99.86 15.26 M092201200055 17.61 89.18 14.51 M092201200056 17.77 83.52 13.82 M092201200057 17.92 75.19 13.47 M092201200058 18.08 78.39 13.90 M092201200059 18.23 72.67 13.26 M092201200060 18.39 72.14 13.61 M092201200061 18.54 76.17 13.70 M092201200062 18.70 70.25 13.11 M092201200063 18.85 66.84 13.12 M092201200064 19.01 84.49 15.40 M092201200065 19.32 62.30 12.67 M092201200066 19.47 71.70 13.93 M092201200067 19.63 62.33 14.13 M092201200068 19.78 62.52 13.88 M092201200069 19.94 57.08 12.61 M092201200070 20.09 61.71 14.16 M092201200071 20.25 77.51 18.42 M092201200072 20.40 68.97 17.51 M092201200073 20.56 67.72 13.20 M092201200074 20.71 59.31 12.85 M092201200075 20.87 62.96 13.08 M092201200076 21.02 51.07 11.70 M092201200077 21.18 55.11 12.47 M092201200078 21.33 61.50 13.87 M092201200079 21.48 62.71 13.28 M092201200080 21.64 66.90 13.66 M092201200081 21.80 54.79 12.39 M092201200082 21.95 66.01 16.89 M092201200083 22.11 53.74 12.03 M092201200084 22.26 50.68 12.35 M092201200085 22.41 55.07 13.51 M092201200086 22.57 48.42 15.17 M092201200087 22.72 40.31 11.77 M092201200088 22.88 56.60 13.65 M092201200089 23.03 51.26 12.64 M092201200090 23.19 30.05 11.00 M092201200091 23.34 40.15 16.68 M092201200092 23.65 54.26 16.06 M092201200093 23.96 26.49 13.25 M092201200094 24.27 36.24 14.45 M092201200095 24.58 41.36 14.99 M092201200096 24.89 34.99 14.57 M092201200097 25.20 31.76 12.33 M092201200098 25.51 23.30 12.13 M092201200099 25.82 33.42 14.68 M092201200100 26.13 28.72 14.56 M092201200101 26.44 38.64 15.39 M092201200102 28.08 18.01 6.00 M092201200103 ENDDATA 73 0 M092201200104 ENDSUBENT 103 0 M092201299999 SUBENT M0922013 20160322 M084M092201300001 BIB 4 23 M092201300002 REACTION ((83-BI-209(G,3N)83-BI-206,,SIG,,,EVAL)+ M092201300003 (83-BI-209(G,3N+P)82-PB-205,,SIG,,,EVAL)) M092201300004 ANALYSIS The contribution of partial reaction (g,n) cross M092201300005 section into the experimental total neutron yield M092201300006 reaction (g,xn) = (g,n) + 2(g,2n) + 3(g,3n) M092201300007 cross section obtained using M092201300008 quasimonoenergetic annihilation photons at Livermore M092201300009 (USA)was evaluated using specially theoretically M092201300010 calculated transitional multiplicity function - M092201300011 ratio M092201300012 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092201300013 by the way M092201300014 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092201300015 REL-REF (R,L0007011,R.R.Harvey+,J,PR,136,B126,1964) M092201300016 Experimental data for the total neutron yield M092201300017 reaction (g,xn) cross section. M092201300018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092201300019 Theoretical preequilibrium model of photonuclear M092201300020 reactions based on the Fermi gas densities. M092201300021 STATUS Data plotted in Fig. 7. M092201300022 (DEP,L0007011) M092201300023 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092201300024 cross section. M092201300025 ENDBIB 23 0 M092201300026 NOCOMMON 0 0 M092201300027 DATA 3 13 M092201300028 EN DATA DATA-ERR M092201300029 MEV MB MB M092201300030 23.03 0.01 0.01 M092201300031 23.19 0.02 0.01 M092201300032 23.34 0.06 0.03 M092201300033 23.65 0.27 0.08 M092201300034 23.96 0.32 0.16 M092201300035 24.27 0.86 0.34 M092201300036 24.58 1.57 0.57 M092201300037 24.89 2.26 0.94 M092201300038 25.20 3.14 1.19 M092201300039 25.51 3.08 1.60 M092201300040 25.82 6.08 2.62 M092201300041 26.13 7.16 3.57 M092201300042 26.44 12.16 4.76 M092201300043 ENDDATA 15 0 M092201300044 ENDSUBENT 43 0 M092201399999 SUBENT M0922014 20160322 M084M092201400001 BIB 3 4 M092201400002 REACTION (55-CS-133(G,X)0-NN-1,UNW,INT,,,EVAL) M092201400003 ANALYSIS Integration of evaluated cross section. M092201400004 STATUS (DEP,M0922002) Evaluated cross section. M092201400005 Data from the Table 1. M092201400006 ENDBIB 4 0 M092201400007 NOCOMMON 0 0 M092201400008 DATA 3 3 M092201400009 EN-MAX DATA DATA-ERR M092201400010 MEV MB*MEV MB*MEV M092201400011 16.2 1107.8 36.2 M092201400012 25.4 1919.0 42.8 M092201400013 29.5 2009.5 43.0 M092201400014 ENDDATA 5 0 M092201400015 ENDSUBENT 14 0 M092201499999 SUBENT M0922015 20160322 M084M092201500001 BIB 3 5 M092201500002 REACTION ((55-CS-133(G,N)55-CS-132,,INT,,,EVAL)+ M092201500003 (55-CS-133(G,N+P)54-XE-131,,INT,,,EVAL)) M092201500004 ANALYSIS Integration of evaluated cross section. M092201500005 STATUS (DEP,M0922003) Evaluated cross section. M092201500006 Data from the Table 1. M092201500007 ENDBIB 5 0 M092201500008 NOCOMMON 0 0 M092201500009 DATA 3 3 M092201500010 EN-MAX DATA DATA-ERR M092201500011 MEV MB*MEV MB*MEV M092201500012 16.2 1110.1 36.3 M092201500013 25.4 1543.9 39.8 M092201500014 29.5 1568.2 39.8 M092201500015 ENDDATA 5 0 M092201500016 ENDSUBENT 15 0 M092201599999 SUBENT M0922016 20160322 M084M092201600001 BIB 3 5 M092201600002 REACTION ((55-CS-133(G,2N)55-CS-131,,INT,,,EVAL)+ M092201600003 (55-CS-133(G,2N+P)54-XE-130,,INT,,,EVAL)) M092201600004 ANALYSIS Integration of evaluated cross section. M092201600005 STATUS (DEP,M0922004) Evaluated cross section. M092201600006 Data from the Table 1. M092201600007 ENDBIB 5 0 M092201600008 NOCOMMON 0 0 M092201600009 DATA 3 2 M092201600010 EN-MAX DATA DATA-ERR M092201600011 MEV MB*MEV MB*MEV M092201600012 25.4 375.1 9.5 M092201600013 29.5 429.2 9.8 M092201600014 ENDDATA 4 0 M092201600015 ENDSUBENT 14 0 M092201699999 SUBENT M0922017 20160322 M084M092201700001 BIB 3 5 M092201700002 REACTION ((55-CS-133(G,3N)55-CS-130,,INT,,,EVAL)+ M092201700003 (55-CS-133(G,3N+P)54-XE-129,,INT,,,EVAL)) M092201700004 ANALYSIS Integration of evaluated cross section. M092201700005 STATUS (DEP,M0922004) Evaluated cross section. M092201700006 Data from the Table 1. M092201700007 ENDBIB 5 0 M092201700008 NOCOMMON 0 0 M092201700009 DATA 3 1 M092201700010 EN-MAX DATA DATA-ERR M092201700011 MEV MB*MEV MB*MEV M092201700012 29.5 11.9 0.7 M092201700013 ENDDATA 3 0 M092201700014 ENDSUBENT 13 0 M092201799999 SUBENT M0922018 20160322 M084M092201800001 BIB 3 4 M092201800002 REACTION (56-BA-138(G,X)0-NN-1,UNW,INT,,,EVAL) M092201800003 ANALYSIS Integration of evaluated cross section. M092201800004 STATUS (DEP,M0922006) Evaluated cross section. M092201800005 Data from the Table 2. M092201800006 ENDBIB 4 0 M092201800007 NOCOMMON 0 0 M092201800008 DATA 3 3 M092201800009 EN-MAX DATA DATA-ERR M092201800010 MEV MB*MEV MB*MEV M092201800011 15.5 957.4 28.9 M092201800012 24.6 1940.1 43.5 M092201800013 27.1 2036.1 44.1 M092201800014 ENDDATA 5 0 M092201800015 ENDSUBENT 14 0 M092201899999 SUBENT M0922019 20160322 M084M092201900001 BIB 3 5 M092201900002 REACTION ((56-BA-138(G,N)56-BA-137,,INT,,,EVAL)+ M092201900003 (56-BA-138(G,N+P)55-CS-136,,INT,,,EVAL)) M092201900004 ANALYSIS Integration of evaluated cross section. M092201900005 STATUS (DEP,M0922007) Evaluated cross section. M092201900006 Data from the Table 2. M092201900007 ENDBIB 5 0 M092201900008 NOCOMMON 0 0 M092201900009 DATA 3 3 M092201900010 EN-MAX DATA DATA-ERR M092201900011 MEV MB*MEV MB*MEV M092201900012 15.5 956.3 28.9 M092201900013 24.6 1442.7 33.7 M092201900014 27.1 1459.8 33.7 M092201900015 ENDDATA 5 0 M092201900016 ENDSUBENT 15 0 M092201999999 SUBENT M0922020 20160322 M084M092202000001 BIB 3 5 M092202000002 REACTION ((56-BA-138(G,2N)56-BA-136,,INT,,,EVAL)+ M092202000003 (56-BA-138(G,2N+P)55-CS-135,,INT,,,EVAL)) M092202000004 ANALYSIS Integration of evaluated cross section. M092202000005 STATUS (DEP,M0922008) Evaluated cross section. M092202000006 Data from the Table 2. M092202000007 ENDBIB 5 0 M092202000008 NOCOMMON 0 0 M092202000009 DATA 3 2 M092202000010 EN-MAX DATA DATA-ERR M092202000011 MEV MB*MEV MB*MEV M092202000012 24.6 492.1 10.9 M092202000013 27.1 564.0 11.4 M092202000014 ENDDATA 4 0 M092202000015 ENDSUBENT 14 0 M092202099999 SUBENT M0922021 20160322 M084M092202100001 BIB 3 5 M092202100002 REACTION ((56-BA-138(G,3N)56-BA-135,,INT,,,EVAL)+ M092202100003 (56-BA-138(G,3N+P)55-CS-134,,INT,,,EVAL)) M092202100004 ANALYSIS Integration of evaluated cross section. M092202100005 STATUS (DEP,M0922009) Evaluated cross section. M092202100006 Data from the Table 2. M092202100007 ENDBIB 5 0 M092202100008 NOCOMMON 0 0 M092202100009 DATA 3 1 M092202100010 EN-MAX DATA DATA-ERR M092202100011 MEV MB*MEV MB*MEV M092202100012 27.1 4.0 0.3 M092202100013 ENDDATA 3 0 M092202100014 ENDSUBENT 13 0 M092202199999 SUBENT M0922022 20160322 M084M092202200001 BIB 4 7 M092202200002 CRITIQUE Integrated cross section calculated up to EN-MAX = M092202200003 14.4 MeV is 2816.4 mb*MeV, not 1816.4 mb*MeV as in M092202200004 article. M092202200005 REACTION (83-BI-209(G,X)0-NN-1,UNW,INT,,,EVAL) M092202200006 ANALYSIS Integration of evaluated cross section. M092202200007 STATUS (DEP,M0922010) Evaluated cross section. M092202200008 Data from the Table 3. M092202200009 ENDBIB 7 0 M092202200010 NOCOMMON 0 0 M092202200011 DATA 3 3 M092202200012 EN-MAX DATA DATA-ERR M092202200013 MEV MB*MEV MB*MEV M092202200014 14.4 2816.4 53.9 M092202200015 22.4 2841.7 58.2 M092202200016 26.4 3110.0 58.2 M092202200017 ENDDATA 5 0 M092202200018 ENDSUBENT 17 0 M092202299999 SUBENT M0922023 20160322 M084M092202300001 BIB 3 5 M092202300002 REACTION ((83-BI-209(G,N)83-BI-208,,INT,,,EVAL)+ M092202300003 (83-BI-209(G,N+P)82-PB-207,,INT,,,EVAL)) M092202300004 ANALYSIS Integration of evaluated cross section. M092202300005 STATUS (DEP,M0922011) Evaluated cross section. M092202300006 Data from the Table 3. M092202300007 ENDBIB 5 0 M092202300008 NOCOMMON 0 0 M092202300009 DATA 3 3 M092202300010 EN-MAX DATA DATA-ERR M092202300011 MEV MB*MEV MB*MEV M092202300012 14.4 1815.5 61.9 M092202300013 22.4 2421.6 33.7 M092202300014 26.4 2482.9 66.8 M092202300015 ENDDATA 5 0 M092202300016 ENDSUBENT 15 0 M092202399999 SUBENT M0922024 20160322 M084M092202400001 BIB 3 5 M092202400002 REACTION ((83-BI-209(G,2N)83-BI-207,,INT,,,EVAL)+ M092202400003 (83-BI-209(G,2N+P)82-PB-206,,INT,,,EVAL)) M092202400004 ANALYSIS Integration of evaluated cross section. M092202400005 STATUS (DEP,M0922012) Evaluated cross section. M092202400006 Data from the Table 3. M092202400007 ENDBIB 5 0 M092202400008 NOCOMMON 0 0 M092202400009 DATA 3 2 M092202400010 EN-MAX DATA DATA-ERR M092202400011 MEV MB*MEV MB*MEV M092202400012 22.4 418.8 12.1 M092202400013 26.4 611.0 13.9 M092202400014 ENDDATA 4 0 M092202400015 ENDSUBENT 14 0 M092202499999 SUBENT M0922025 20160322 M084M092202500001 BIB 3 5 M092202500002 REACTION ((83-BI-209(G,3N)83-BI-206,,INT,,,EVAL)+ M092202500003 (83-BI-209(G,3N+P)82-PB-205,,INT,,,EVAL)) M092202500004 ANALYSIS Integration of evaluated cross section. M092202500005 STATUS (DEP,M0922013) Evaluated cross section. M092202500006 Data from the Table 3. M092202500007 ENDBIB 5 0 M092202500008 NOCOMMON 0 0 M092202500009 DATA 3 1 M092202500010 EN-MAX DATA DATA-ERR M092202500011 MEV MB*MEV MB*MEV M092202500012 26.4 8.2 0.6 M092202500013 ENDDATA 3 0 M092202500014 ENDSUBENT 13 0 M092202599999 ENDENTRY 25 0 M092299999999