ENTRY M0915 20150901 M080M091500000001 SUBENT M0915001 20150901 M080M091500100001 BIB 9 38 M091500100002 TITLE Photodesintegration of the isotopes M091500100003 186,188,189,190,192Os: similarities and M091500100004 distinctions. M091500100005 AUTHOR (V.V.Varlamov,M.A.Makarov,N.N.Peskov,M.E.Stepanov) M091500100006 REFERENCE (J,YF,78,(9),797,2015) M091500100007 #doi:10.7868/S0044002715090160 M091500100008 (J,PAN,78,(6),746,2015) M091500100009 #doi:10.1134/S1063778815060150 M091500100010 English translation of J,YF,78,(9),746,2015. M091500100011 (R,MSU-INP-2013-1/884,2013) In Russian. M091500100012 (J,IZV,78,(5),599,2014) M091500100013 #doi:10.7868/S0367676514050263 M091500100014 (J,BAS,78,(5),412,2014) M091500100015 #doi:10.3103/S1062873814050207 M091500100016 English translation of IZV,78,(5),599,2014. M091500100017 INSTITUTE (4RUSMOS) M091500100018 INC-SOURCE (QMPH,ARAD) M091500100019 ANALYSIS The joint analysis of data for total (g,xn) and M091500100020 partial (g,n), (g,2n) and (g,3n) reactions obtained M091500100021 in various experiments was carried out. The new M091500100022 approach to analysis of systematic disagreements M091500100023 between data was proposed on the base of new M091500100024 criteria of systematic uncertainties presence - M091500100025 specially proposed transitional multiplicity M091500100026 functions M091500100027 Fi-theor = SIG(g,in)/SIG(g,xn). M091500100028 Using these functions calculated in the frame of M091500100029 combined photonuclear reaction model new reliable M091500100030 and free from problems of neutron multiplicity M091500100031 sorting data for photoneutron partial reactions M091500100032 cross sections M091500100033 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M091500100034 were evaluated using experimental neutron yield M091500100035 reaction cross sections SIG-exp(g,xn). M091500100036 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M091500100037 STATUS (TABLE,APRVD) Approved by V.Varlamov. M091500100038 HISTORY (20150813C) Data were compiled at the Russia MSU SINP M091500100039 CDFE by V.Varlamov. M091500100040 ENDBIB 38 0 M091500100041 NOCOMMON 0 0 M091500100042 ENDSUBENT 41 0 M091500199999 SUBENT M0915002 20150901 M080M091500200001 BIB 3 8 M091500200002 REACTION (76-OS-186(G,X)0-NN-1,UNW,SIG,,,EVAL) M091500200003 ANALYSIS The total neutron reaction cross section obtained as M091500200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M091500200005 STATUS Data plotted in Fig. 7. M091500200006 (DEP,M0915003) M091500200007 Evaluated (g,n) reaction cross section. M091500200008 (DEP,M0915004) M091500200009 Evaluated (g,2n) reaction cross section. M091500200010 ENDBIB 8 0 M091500200011 NOCOMMON 0 0 M091500200012 DATA 3 45 M091500200013 EN DATA DATA-ERR M091500200014 MEV MB MB M091500200015 11.11 122.31 20.91 M091500200016 11.35 169.61 26.82 M091500200017 11.60 206.56 31.53 M091500200018 11.84 227.51 34.52 M091500200019 12.09 285.76 42.50 M091500200020 12.33 329.91 47.79 M091500200021 12.58 363.16 53.29 M091500200022 12.82 378.62 54.68 M091500200023 13.06 401.11 58.40 M091500200024 13.31 412.09 59.89 M091500200025 13.55 412.61 59.31 M091500200026 13.80 425.08 61.61 M091500200027 14.04 426.45 61.25 M091500200028 14.29 436.01 63.35 M091500200029 14.53 392.92 56.71 M091500200030 14.78 417.86 60.37 M091500200031 15.02 417.15 57.76 M091500200032 15.26 379.15 48.96 M091500200033 15.39 367.27 46.74 M091500200034 15.51 335.30 39.05 M091500200035 15.75 321.77 34.48 M091500200036 15.88 317.68 34.49 M091500200037 16.00 300.82 31.71 M091500200038 16.24 267.84 28.01 M091500200039 16.36 244.21 27.13 M091500200040 16.49 242.38 27.24 M091500200041 16.61 217.62 25.89 M091500200042 16.73 214.99 24.63 M091500200043 16.85 208.57 25.85 M091500200044 16.98 190.56 23.90 M091500200045 17.10 177.61 23.37 M091500200046 17.22 185.75 22.61 M091500200047 17.34 157.02 21.20 M091500200048 17.46 175.64 22.63 M091500200049 17.71 157.49 20.91 M091500200050 17.95 141.45 19.45 M091500200051 18.20 118.14 17.12 M091500200052 18.32 111.58 17.21 M091500200053 18.44 107.14 16.22 M091500200054 18.69 108.49 16.29 M091500200055 18.93 89.41 14.85 M091500200056 19.17 96.10 15.87 M091500200057 19.42 97.28 15.99 M091500200058 19.54 70.64 14.67 M091500200059 19.66 87.11 14.80 M091500200060 ENDDATA 47 0 M091500200061 ENDSUBENT 60 0 M091500299999 SUBENT M0915003 20150901 M080M091500300001 BIB 4 21 M091500300002 REACTION ((76-OS-186(G,N)76-OS-185,,SIG,,,EVAL)+ M091500300003 (76-OS-186(G,N+P)75-RE-184,,SIG,,,EVAL)) M091500300004 ANALYSIS The contribution of partial reaction (g,n) cross M091500300005 section into the experimental total neutron yield M091500300006 reaction (g,xn) cross section obtained using M091500300007 quasimonoenergetic annihilation photons at Livermore M091500300008 (USA) was evaluated using specially theoretically M091500300009 calculated transitional multiplicity function - M091500300010 ratio M091500300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091500300012 by the way M091500300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M091500300014 REL-REF (R,L0046004,B.L.Berman+,J,PR/C,19,1205,1979) M091500300015 Experimental data for the total neutron yield M091500300016 reaction (g,xn) cross section. M091500300017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091500300018 Theoretical preequilibrium model of photonuclear M091500300019 reactions based on the Fermi gas densities. M091500300020 STATUS Data plotted in Fig. 7. M091500300021 (DEP,L0046004) M091500300022 The neutron yield reaction (g,xn) cross section. M091500300023 ENDBIB 21 0 M091500300024 NOCOMMON 0 0 M091500300025 DATA 3 45 M091500300026 EN DATA DATA-ERR M091500300027 MEV MB MB M091500300028 11.11 122.31 20.91 M091500300029 11.35 169.61 26.82 M091500300030 11.60 206.56 31.53 M091500300031 11.84 227.51 34.52 M091500300032 12.09 285.76 42.50 M091500300033 12.33 329.91 47.79 M091500300034 12.58 363.16 53.29 M091500300035 12.82 378.62 54.68 M091500300036 13.06 401.11 58.40 M091500300037 13.31 412.09 59.89 M091500300038 13.55 412.61 59.31 M091500300039 13.80 425.08 61.61 M091500300040 14.04 426.45 61.25 M091500300041 14.29 436.01 63.35 M091500300042 14.53 392.92 56.71 M091500300043 14.78 413.62 60.37 M091500300044 15.02 394.74 57.67 M091500300045 15.26 331.05 48.45 M091500300046 15.39 302.92 45.72 M091500300047 15.51 258.14 37.42 M091500300048 15.75 207.94 30.24 M091500300049 15.88 184.40 27.95 M091500300050 16.00 156.40 23.30 M091500300051 16.24 110.73 16.13 M091500300052 16.36 90.23 13.72 M091500300053 16.49 79.67 11.97 M091500300054 16.61 64.88 10.12 M091500300055 16.73 58.08 8.55 M091500300056 16.85 52.05 8.15 M091500300057 16.98 44.64 6.99 M091500300058 17.10 39.40 6.40 M091500300059 17.22 39.70 5.93 M091500300060 17.34 32.43 5.34 M091500300061 17.46 35.34 5.52 M091500300062 17.71 30.10 4.80 M091500300063 17.95 25.76 4.22 M091500300064 18.20 20.65 3.55 M091500300065 18.32 19.21 3.50 M091500300066 18.44 18.12 3.23 M091500300067 18.69 17.84 3.14 M091500300068 18.93 14.39 2.79 M091500300069 19.17 15.12 2.91 M091500300070 19.42 15.00 2.86 M091500300071 19.54 10.82 2.61 M091500300072 19.66 13.30 2.62 M091500300073 ENDDATA 47 0 M091500300074 ENDSUBENT 73 0 M091500399999 SUBENT M0915004 20150901 M080M091500400001 BIB 4 22 M091500400002 REACTION ((76-OS-190(G,N)76-OS-189,,SIG,,,EVAL)+ M091500400003 (76-OS-190(G,N+P)75-RE-188,,SIG,,,EVAL)) M091500400004 ANALYSIS The contribution of partial reaction (g,n) cross M091500400005 section into the experimental total neutron yield M091500400006 reaction (g,xn) cross section obtained using M091500400007 quasimonoenergetic annihilation photons at Livermore M091500400008 (USA) was evaluated using specially theoretically M091500400009 calculated transitional multiplicity function - M091500400010 ratio M091500400011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091500400012 by the way M091500400013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M091500400014 REL-REF (R,L0046016,B.L.Berman+,J,PR/C,19,1205,1979) M091500400015 Experimental data for the total neutron yield M091500400016 reaction (g,xn) cross section. M091500400017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091500400018 Theoretical preequilibrium model of photonuclear M091500400019 reactions based on the Fermi gas densities. M091500400020 STATUS Data plotted in Fig. 8. M091500400021 (DEP,L0011008) M091500400022 The total neutron yield reaction (g,xn) cross M091500400023 section. M091500400024 ENDBIB 22 0 M091500400025 NOCOMMON 0 0 M091500400026 DATA 3 84 M091500400027 EN DATA DATA-ERR M091500400028 MEV MB MB M091500400029 7.44 -0.19 1.18 M091500400030 7.93 18.93 3.15 M091500400031 8.42 34.47 5.19 M091500400032 8.91 46.62 6.85 M091500400033 9.40 61.05 8.68 M091500400034 9.89 80.37 11.58 M091500400035 10.13 92.41 13.16 M091500400036 10.38 102.25 14.54 M091500400037 10.62 125.67 17.83 M091500400038 10.87 151.29 21.40 M091500400039 11.11 166.84 23.56 M091500400040 11.35 198.19 27.95 M091500400041 11.60 239.77 33.79 M091500400042 11.84 287.12 40.41 M091500400043 12.09 344.88 48.51 M091500400044 12.33 376.35 52.97 M091500400045 12.58 409.1 57.54 M091500400046 12.82 447.52 62.83 M091500400047 13.06 468.63 65.81 M091500400048 13.31 476.74 66.92 M091500400049 13.55 491.57 69.01 M091500400050 13.80 469.31 65.90 M091500400051 14.04 443.47 62.27 M091500400052 14.29 406.77 57.13 M091500400053 14.53 360.14 50.58 M091500400054 14.78 298.36 41.85 M091500400055 15.02 246.12 34.54 M091500400056 15.26 196.36 27.71 M091500400057 15.51 159.26 22.51 M091500400058 15.75 126.38 17.89 M091500400059 16.00 103.01 14.60 M091500400060 16.12 90.29 12.80 M091500400061 16.24 80.25 11.40 M091500400062 16.36 73.57 10.43 M091500400063 16.49 65.59 9.34 M091500400064 16.61 62.16 8.83 M091500400065 16.73 55.31 7.88 M091500400066 16.85 53.03 7.55 M091500400067 16.98 47.00 6.72 M091500400068 17.10 44.07 6.31 M091500400069 17.22 38.80 5.58 M091500400070 17.34 36.95 5.34 M091500400071 17.46 32.09 4.67 M091500400072 17.71 27.89 4.12 M091500400073 17.95 24.17 3.65 M091500400074 18.20 23.03 3.51 M091500400075 18.44 19.57 3.06 M091500400076 18.69 18.75 2.94 M091500400077 18.93 16.13 2.58 M091500400078 19.17 15.71 2.51 M091500400079 19.42 14.88 2.41 M091500400080 19.66 13.19 2.20 M091500400081 19.91 12.23 2.06 M091500400082 20.15 11.72 1.83 M091500400083 20.40 10.52 1.93 M091500400084 20.64 11.34 2.03 M091500400085 20.89 12.17 2.12 M091500400086 21.13 10.93 2.03 M091500400087 21.37 11.29 2.08 M091500400088 21.62 10.90 2.07 M091500400089 21.86 11.28 2.18 M091500400090 22.11 12.12 2.30 M091500400091 22.35 12.12 2.45 M091500400092 22.60 11.77 2.13 M091500400093 22.84 13.03 2.71 M091500400094 23.09 14.31 2.88 M091500400095 23.33 12.52 2.77 M091500400096 23.57 13.93 2.92 M091500400097 23.82 11.92 2.21 M091500400098 24.06 10.95 2.08 M091500400099 24.31 11.88 2.55 M091500400100 24.55 11.99 2.49 M091500400101 25.04 8.07 1.99 M091500400102 25.53 6.24 1.76 M091500400103 26.02 4.49 1.59 M091500400104 26.51 3.86 1.55 M091500400105 27. 3.31 1.45 M091500400106 27.48 3.73 1.49 M091500400107 27.97 2.71 1.42 M091500400108 28.46 2.23 1.42 M091500400109 28.95 1.66 1.42 M091500400110 29.44 2.73 1.80 M091500400111 29.93 3.15 1.91 M091500400112 30.42 3.69 1.82 M091500400113 ENDDATA 86 0 M091500400114 ENDSUBENT 113 0 M091500499999 SUBENT M0915005 20150901 M080M091500500001 BIB 4 22 M091500500002 REACTION ((76-OS-190(G,2N)76-OS-188,,SIG,,,EVAL)+ M091500500003 (76-OS-190(G,2N+P)75-RE-187,,SIG,,,EVAL)) M091500500004 ANALYSIS The contribution of partial reaction (g,n) cross M091500500005 section into the experimental total neutron yield M091500500006 reaction (g,xn) cross section obtained using M091500500007 quasimonoenergetic annihilation photons at Livermore M091500500008 (USA) was evaluated using specially theoretically M091500500009 calculated transitional multiplicity function - M091500500010 ratio M091500500011 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M091500500012 by the way M091500500013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M091500500014 REL-REF (R,L0046016,B.L.Berman+,J,PR/C,19,1205,1979) M091500500015 Experimental data for the total neutron yield M091500500016 reaction (g,xn) cross section. M091500500017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091500500018 Theoretical preequilibrium model of photonuclear M091500500019 reactions based on the Fermi gas densities. M091500500020 STATUS Data plotted in Fig. 8. M091500500021 (DEP,L0011008) M091500500022 The total neutron yield reaction (g,xn) cross M091500500023 section. M091500500024 ENDBIB 22 0 M091500500025 NOCOMMON 0 0 M091500500026 DATA 3 63 M091500500027 EN DATA DATA-ERR M091500500028 MEV MB MB M091500500029 13.80 13.01 1.82 M091500500030 14.04 36.03 5.06 M091500500031 14.29 68.25 9.58 M091500500032 14.53 105.50 14.81 M091500500033 14.78 140.89 19.76 M091500500034 15.02 171.46 24.06 M091500500035 15.26 192.95 27.22 M091500500036 15.51 211.46 29.89 M091500500037 15.75 215.72 30.54 M091500500038 16.00 215.30 30.51 M091500500039 16.12 207.75 29.46 M091500500040 16.24 200.99 28.55 M091500500041 16.36 200.25 28.40 M091500500042 16.49 189.36 26.96 M091500500043 16.61 190.01 27.01 M091500500044 16.73 177.94 25.36 M091500500045 16.85 178.46 25.42 M091500500046 16.98 65.55 23.69 M091500500047 17.10 161.23 23.11 M091500500048 17.22 147.46 21.22 M091500500049 17.34 145.84 21.09 M091500500050 17.46 130.91 19.08 M091500500051 17.71 119.90 17.74 M091500500052 17.95 108.93 16.45 M091500500053 18.20 108.14 16.51 M091500500054 18.44 94.43 14.81 M091500500055 18.69 93.49 14.66 M091500500056 18.93 83.15 13.32 M091500500057 19.17 82.73 13.25 M091500500058 19.42 79.92 12.95 M091500500059 19.66 72.19 12.05 M091500500060 19.91 68.06 11.50 M091500500061 20.15 66.10 10.37 M091500500062 20.40 59.80 10.97 M091500500063 20.64 64.58 11.56 M091500500064 20.89 69.16 12.05 M091500500065 21.13 61.12 11.37 M091500500066 21.37 61.64 11.36 M091500500067 21.62 57.65 10.98 M091500500068 21.86 56.72 10.98 M091500500069 22.11 57.28 10.88 M091500500070 22.35 52.61 10.65 M091500500071 22.60 46.61 8.44 M091500500072 22.84 46.12 9.62 M091500500073 23.09 45.03 9.07 M091500500074 23.33 35.24 7.80 M091500500075 23.57 35.83 7.51 M091500500076 23.82 28.43 5.27 M091500500077 24.06 24.53 4.67 M091500500078 24.31 25.24 5.43 M091500500079 24.55 24.45 5.09 M091500500080 25.04 15.31 3.78 M091500500081 25.53 11.07 3.12 M091500500082 26.02 7.46 2.64 M091500500083 26.51 6.01 2.42 M091500500084 27. 4.86 2.13 M091500500085 27.48 5.18 2.07 M091500500086 27.97 3.57 1.87 M091500500087 28.46 2.84 1.81 M091500500088 28.95 2.05 1.76 M091500500089 29.44 3.32 2.19 M091500500090 29.93 3.75 2.28 M091500500091 30.42 4.29 2.12 M091500500092 ENDDATA 65 0 M091500500093 ENDSUBENT 92 0 M091500599999 SUBENT M0915006 20150901 M080M091500600001 BIB 4 22 M091500600002 REACTION ((76-OS-190(G,3N)76-OS-187,,SIG,,,EVAL)+ M091500600003 (76-OS-190(G,3N+P)75-RE-186,,SIG,,,EVAL)) M091500600004 ANALYSIS The contribution of partial reaction (g,n) cross M091500600005 section into the experimental total neutron yield M091500600006 reaction (g,xn) cross section obtained using M091500600007 quasimonoenergetic annihilation photons at Livermore M091500600008 (USA) was evaluated using specially theoretically M091500600009 calculated transitional multiplicity function - M091500600010 ratio M091500600011 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M091500600012 by the way M091500600013 SIG-eval(g,n) = (F3-theor)x(SIG-exp(g,xn)). M091500600014 REL-REF (R,L0046016,B.L.Berman+,J,PR/C,19,1205,1979) M091500600015 Experimental data for the total neutron yield M091500600016 reaction (g,xn) cross section. M091500600017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091500600018 Theoretical preequilibrium model of photonuclear M091500600019 reactions based on the Fermi gas densities. M091500600020 STATUS Data plotted in Fig. 8. M091500600021 (DEP,L0011008) M091500600022 The total neutron yield reaction (g,xn) cross M091500600023 section. M091500600024 ENDBIB 22 0 M091500600025 NOCOMMON 0 0 M091500600026 DATA 3 24 M091500600027 EN DATA DATA-ERR M091500600028 MEV MB MB M091500600029 21.86 0.15 0.03 M091500600030 22.11 0.92 0.17 M091500600031 22.35 2.27 0.46 M091500600032 22.60 4.03 0.73 M091500600033 22.84 6.77 1.41 M091500600034 23.09 10.31 2.08 M091500600035 23.33 11.61 2.57 M091500600036 23.57 15.97 3.35 M091500600037 23.82 16.65 3.08 M091500600038 24.06 18.29 3.48 M091500600039 24.31 23.21 4.99 M091500600040 24.55 26.89 5.59 M091500600041 25.04 22.90 5.66 M091500600042 25.53 21.32 6.01 M091500600043 26.02 17.85 6.31 M091500600044 26.51 17.21 6.93 M091500600045 27. 16.03 7.05 M091500600046 27.48 19.32 7.73 M091500600047 27.97 14.72 7.72 M091500600048 28.46 12.66 8.05 M091500600049 28.95 9.71 8.34 M091500600050 29.44 16.28 10.75 M091500600051 29.93 18.63 11.32 M091500600052 30.42 21.28 10.50 M091500600053 ENDDATA 26 0 M091500600054 ENDSUBENT 53 0 M091500699999 SUBENT M0915007 20150901 M080M091500700001 BIB 3 10 M091500700002 REACTION (76-OS-190(G,X)0-NN-1,UNW,SIG,,,EVAL) M091500700003 ANALYSIS The total neutron reaction cross section obtained M091500700004 as sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M091500700005 STATUS Data plotted in Fig. 8. M091500700006 (DEP,M0864017) M091500700007 Evaluated (g,n) reaction cross section. M091500700008 (DEP,M0864018) M091500700009 Evaluated (g,2n) reaction cross section. M091500700010 (DEP,M0864019) M091500700011 Evaluated (g,3n) reaction cross section. M091500700012 ENDBIB 10 0 M091500700013 NOCOMMON 0 0 M091500700014 DATA 3 84 M091500700015 EN DATA DATA-ERR M091500700016 MEV MB MB M091500700017 7.44 -0.19 1.18 M091500700018 7.93 18.93 3.15 M091500700019 8.42 34.47 5.19 M091500700020 8.91 46.62 6.85 M091500700021 9.40 61.05 8.68 M091500700022 9.89 80.37 11.58 M091500700023 10.13 92.41 13.16 M091500700024 10.38 102.25 14.54 M091500700025 10.62 125.67 17.83 M091500700026 10.87 151.29 21.40 M091500700027 11.11 166.84 23.56 M091500700028 11.35 198.19 27.95 M091500700029 11.60 239.77 33.79 M091500700030 11.84 287.12 40.41 M091500700031 12.09 344.88 48.51 M091500700032 12.33 376.35 52.97 M091500700033 12.58 409.1 57.54 M091500700034 12.82 447.52 62.83 M091500700035 13.06 468.63 65.81 M091500700036 13.31 476.74 66.92 M091500700037 13.55 491.57 69.01 M091500700038 13.80 482.33 65.92 M091500700039 14.04 479.51 62.48 M091500700040 14.29 475.03 57.93 M091500700041 14.53 465.64 52.70 M091500700042 14.78 439.26 46.28 M091500700043 15.02 417.58 42.10 M091500700044 15.26 389.32 38.84 M091500700045 15.51 370.73 37.42 M091500700046 15.75 342.11 35.40 M091500700047 16.00 318.32 33.83 M091500700048 16.12 298.05 32.12 M091500700049 16.24 281.24 30.74 M091500700050 16.36 273.83 30.26 M091500700051 16.49 254.96 28.53 M091500700052 16.61 252.17 28.42 M091500700053 16.73 233.26 26.56 M091500700054 16.85 231.50 26.52 M091500700055 16.98 212.55 24.63 M091500700056 17.10 205.31 23.95 M091500700057 17.22 186.26 21.94 M091500700058 17.34 182.79 21.75 M091500700059 17.46 163.01 19.65 M091500700060 17.71 147.80 18.21 M091500700061 17.95 133.11 16.85 M091500700062 18.20 131.18 16.88 M091500700063 18.44 114.01 15.12 M091500700064 18.69 112.24 14.95 M091500700065 18.93 99.29 13.57 M091500700066 19.17 98.44 13.49 M091500700067 19.42 94.81 13.18 M091500700068 19.66 85.39 12.25 M091500700069 19.91 80.30 11.68 M091500700070 20.15 77.82 10.53 M091500700071 20.40 70.33 11.14 M091500700072 20.64 75.93 11.74 M091500700073 20.89 81.33 12.23 M091500700074 21.13 72.05 11.55 M091500700075 21.37 72.94 11.55 M091500700076 21.62 68.55 11.17 M091500700077 21.86 68.16 11.19 M091500700078 22.11 70.34 11.13 M091500700079 22.35 67.00 10.94 M091500700080 22.60 62.42 8.73 M091500700081 22.84 65.93 10.09 M091500700082 23.09 69.67 9.75 M091500700083 23.33 59.38 8.67 M091500700084 23.57 65.74 8.73 M091500700085 23.82 57.01 6.49 M091500700086 24.06 53.78 6.19 M091500700087 24.31 60.34 7.81 M091500700088 24.55 63.34 7.96 M091500700089 25.04 46.29 7.10 M091500700090 25.53 38.63 7.00 M091500700091 26.02 29.81 7.03 M091500700092 26.51 27.09 7.50 M091500700093 27. 24.21 7.51 M091500700094 27.48 28.25 8.14 M091500700095 27.97 21.01 8.07 M091500700096 28.46 17.75 8.38 M091500700097 28.95 13.43 8.65 M091500700098 29.44 22.34 11.12 M091500700099 29.93 25.54 11.71 M091500700100 30.42 29.28 10.87 M091500700101 ENDDATA 86 0 M091500700102 ENDSUBENT 101 0 M091500799999 SUBENT M0915008 20150901 M080M091500800001 BIB 4 22 M091500800002 REACTION ((76-OS-192(G,N)76-OS-191,,SIG,,,EVAL)+ M091500800003 (76-OS-192(G,N+P)75-RE-190,,SIG,,,EVAL)) M091500800004 ANALYSIS The contribution of partial reaction (g,n) cross M091500800005 section into the experimental total neutron yield M091500800006 reaction (g,xn) cross section obtained using M091500800007 quasimonoenergetic annihilation photons at Livermore M091500800008 (USA) was evaluated using specially theoretically M091500800009 calculated transitional multiplicity function - M091500800010 ratio M091500800011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091500800012 by the way M091500800013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M091500800014 REL-REF (R,L0046020,B.L.Berman+,J,PR/C,19,1205,1979) M091500800015 Experimental data for the total neutron yield M091500800016 reaction (g,xn) cross section. M091500800017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091500800018 Theoretical preequilibrium model of photonuclear M091500800019 reactions based on the Fermi gas densities. M091500800020 STATUS Data plotted in Fig. 9. M091500800021 (DEP,L0011008) M091500800022 The total neutron yield reaction (g,xn) cross M091500800023 section. M091500800024 ENDBIB 22 0 M091500800025 NOCOMMON 0 0 M091500800026 DATA 3 82 M091500800027 EN DATA DATA-ERR M091500800028 MEV MB MB M091500800029 7.44 -0.05 1.29 M091500800030 7.93 21.53 3.54 M091500800031 8.42 36.85 5.56 M091500800032 8.91 42.47 6.33 M091500800033 9.40 55.8 8.17 M091500800034 9.89 81.04 11.63 M091500800035 10.13 94.18 13.52 M091500800036 10.38 115.53 16.53 M091500800037 10.62 130.21 18.59 M091500800038 10.87 146.13 20.86 M091500800039 11.11 171.02 24.36 M091500800040 11.35 211.38 30.08 M091500800041 11.60 248.35 35.33 M091500800042 11.84 287.86 40.90 M091500800043 12.09 344.97 48.99 M091500800044 12.33 392.14 55.67 M091500800045 12.58 427.47 60.78 M091500800046 12.82 447.86 63.46 M091500800047 13.06 477.09 67.58 M091500800048 13.31 477.36 67.66 M091500800049 13.55 470.35 66.71 M091500800050 13.80 441.67 62.64 M091500800051 14.04 406.14 57.61 M091500800052 14.29 365.67 51.88 M091500800053 14.53 311.10 44.11 M091500800054 14.78 266.21 37.73 M091500800055 15.02 212.32 30.12 M091500800056 15.26 177.96 25.38 M091500800057 15.51 144.98 20.70 M091500800058 15.75 115.06 16.48 M091500800059 16.00 95.09 13.67 M091500800060 16.12 85.36 12.26 M091500800061 16.24 79.04 11.41 M091500800062 16.36 71.85 10.34 M091500800063 16.49 68.16 9.88 M091500800064 16.61 63.47 9.17 M091500800065 16.73 54.95 8.04 M091500800066 16.85 53.01 7.73 M091500800067 16.98 45.24 6.73 M091500800068 17.10 46.70 6.89 M091500800069 17.22 40.09 6.03 M091500800070 17.34 39.94 5.96 M091500800071 17.46 34.91 5.29 M091500800072 17.71 31.08 4.74 M091500800073 17.95 27.22 4.22 M091500800074 18.20 26.17 4.09 M091500800075 18.44 24.84 3.88 M091500800076 18.69 22.71 3.51 M091500800077 18.93 20.34 3.15 M091500800078 19.17 18.20 2.87 M091500800079 19.42 18.04 2.80 M091500800080 19.66 15.03 2.39 M091500800081 19.91 13.21 2.14 M091500800082 20.15 13.01 2.12 M091500800083 20.40 12.94 2.17 M091500800084 20.64 11.74 2.03 M091500800085 20.89 12.17 2.06 M091500800086 21.13 10.98 1.92 M091500800087 21.37 11.20 2.02 M091500800088 21.62 11.21 2.05 M091500800089 21.86 10.57 2.03 M091500800090 22.11 10.86 2.10 M091500800091 22.35 12.60 2.34 M091500800092 22.60 12.03 2.32 M091500800093 22.84 13.26 2.47 M091500800094 23.09 12.33 2.41 M091500800095 23.33 13.58 2.62 M091500800096 23.57 14.95 2.81 M091500800097 23.82 13.14 2.31 M091500800098 24.06 17.07 2.81 M091500800099 24.31 12.85 2.75 M091500800100 24.55 13.18 2.81 M091500800101 25.04 11.05 2.68 M091500800102 25.53 11.25 2.73 M091500800103 26.02 7.87 2.45 M091500800104 26.51 6.11 2.29 M091500800105 27. 5.93 2.13 M091500800106 27.48 4.90 2.10 M091500800107 27.97 3.25 2.00 M091500800108 28.46 3.71 1.95 M091500800109 28.95 2.36 1.85 M091500800110 29.90 -0.01 1.34 M091500800111 ENDDATA 84 0 M091500800112 ENDSUBENT 111 0 M091500899999 SUBENT M0915009 20150901 M080M091500900001 BIB 4 22 M091500900002 REACTION ((76-OS-192(G,2N)76-OS-190,,SIG,,,EVAL)+ M091500900003 (76-OS-192(G,2N+P)75-RE-189,,SIG,,,EVAL)) M091500900004 ANALYSIS The contribution of partial reaction (g,n) cross M091500900005 section into the experimental total neutron yield M091500900006 reaction (g,xn) cross section obtained using M091500900007 quasimonoenergetic annihilation photons at Livermore M091500900008 (USA) was evaluated using specially theoretically M091500900009 calculated transitional multiplicity function - M091500900010 ratio M091500900011 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M091500900012 by the way M091500900013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M091500900014 REL-REF (R,L0046020,B.L.Berman+,J,PR/C,19,1205,1979) M091500900015 Experimental data for the total neutron yield M091500900016 reaction (g,xn) cross section. M091500900017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091500900018 Theoretical preequilibrium model of photonuclear M091500900019 reactions based on the Fermi gas densities. M091500900020 STATUS Data plotted in Fig. 9. M091500900021 (DEP,L0011008) M091500900022 The total neutron yield reaction (g,xn) cross M091500900023 section. M091500900024 ENDBIB 22 0 M091500900025 NOCOMMON 0 0 M091500900026 DATA 3 63 M091500900027 EN DATA DATA-ERR M091500900028 MEV MB MB M091500900029 13.31 1.34 0.19 M091500900030 13.55 16.73 2.37 M091500900031 13.80 41.01 5.81 M091500900032 14.04 75.21 10.66 M091500900033 14.29 115.56 16.39 M091500900034 14.53 153.91 21.82 M091500900035 14.78 188.70 26.74 M091500900036 15.02 206.13 29.24 M091500900037 15.26 226.73 32.34 M091500900038 15.51 231.46 33.06 M091500900039 15.75 222.72 31.90 M091500900040 16.00 217.17 31.23 M091500900041 16.12 209.56 30.10 M091500900042 16.24 205.82 29.72 M091500900043 16.36 197.44 28.42 M091500900044 16.49 196.74 28.51 M091500900045 16.61 192.13 27.76 M091500900046 16.73 174.34 25.52 M091500900047 16.85 175.68 25.64 M091500900048 16.98 156.62 23.32 M091500900049 17.10 168.87 24.93 M091500900050 17.22 149.83 22.55 M091500900051 17.34 153.86 22.98 M091500900052 17.46 137.77 20.90 M091500900053 17.71 128.30 19.60 M091500900054 17.95 117.19 18.20 M091500900055 18.20 116.65 18.24 M091500900056 18.44 114.33 17.85 M091500900057 18.69 108.09 16.73 M091500900058 18.93 99.48 15.43 M091500900059 19.17 91.37 14.40 M091500900060 19.42 92.31 14.33 M091500900061 19.66 78.54 12.49 M091500900062 19.91 70.16 11.39 M091500900063 20.15 70.28 11.48 M091500900064 20.40 70.50 11.86 M091500900065 20.64 64.65 11.17 M091500900066 20.89 67.11 11.37 M091500900067 21.13 60.67 10.63 M091500900068 21.37 61.53 11.09 M091500900069 21.62 60.60 11.09 M091500900070 21.86 55.51 10.66 M091500900071 22.11 54.85 10.61 M091500900072 22.35 60.69 11.30 M091500900073 22.60 54.45 10.51 M091500900074 22.84 56.03 10.47 M091500900075 23.09 48.56 9.50 M091500900076 23.33 49.50 9.58 M091500900077 23.57 50.47 9.49 M091500900078 23.82 40.99 7.22 M091500900079 24.06 48.85 8.05 M091500900080 24.31 33.56 7.20 M091500900081 24.55 31.41 6.69 M091500900082 25.04 22.07 5.36 M091500900083 25.53 19.82 4.80 M091500900084 26.02 13.03 4.06 M091500900085 26.51 9.76 3.66 M091500900086 27. 9.06 3.26 M091500900087 27.48 7.17 3.08 M091500900088 27.97 4.58 2.83 M091500900089 28.46 5.10 2.68 M091500900090 28.95 3.19 2.50 M091500900091 29.90 -0.02 1.77 M091500900092 ENDDATA 65 0 M091500900093 ENDSUBENT 92 0 M091500999999 SUBENT M0915010 20150901 M080M091501000001 BIB 4 22 M091501000002 REACTION ((76-OS-192(G,3N)76-OS-189,,SIG,,,EVAL)+ M091501000003 (76-OS-192(G,3N+P)75-RE-188,,SIG,,,EVAL)) M091501000004 ANALYSIS The contribution of partial reaction (g,n) cross M091501000005 section into the experimental total neutron yield M091501000006 reaction (g,xn) cross section obtained using M091501000007 quasimonoenergetic annihilation photons at Livermore M091501000008 (USA) was evaluated using specially theoretically M091501000009 calculated transitional multiplicity function - M091501000010 ratio M091501000011 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M091501000012 by the way M091501000013 SIG-eval(g,n) = (F3-theor)x(SIG-exp(g,xn)). M091501000014 REL-REF (R,L0046020,B.L.Berman+,J,PR/C,19,1205,1979) M091501000015 Experimental data for the total neutron yield M091501000016 reaction (g,xn) cross section. M091501000017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091501000018 Theoretical preequilibrium model of photonuclear M091501000019 reactions based on the Fermi gas densities. M091501000020 STATUS Data plotted in Fig. 9. M091501000021 (DEP,L0011008) M091501000022 The total neutron yield reaction (g,xn) cross M091501000023 section. M091501000024 ENDBIB 22 0 M091501000025 NOCOMMON 0 0 M091501000026 DATA 3 23 M091501000027 EN DATA DATA-ERR M091501000028 MEV MB MB M091501000029 21.62 0.07 0.01 M091501000030 21.86 0.50 0.09 M091501000031 22.11 1.39 0.27 M091501000032 22.35 3.11 0.57 M091501000033 22.60 4.80 0.92 M091501000034 22.84 7.68 1.43 M091501000035 23.09 9.71 1.90 M091501000036 23.33 13.50 2.61 M091501000037 23.57 18.15 3.41 M091501000038 23.82 18.97 3.34 M091501000039 24.06 28.13 4.64 M091501000040 24.31 23.43 5.02 M091501000041 24.55 26.19 5.58 M091501000042 25.04 24.94 6.06 M091501000043 25.53 29.29 7.10 M091501000044 26.02 24.07 7.49 M091501000045 26.51 21.80 8.18 M091501000046 27. 23.98 8.63 M091501000047 27.48 21.75 9.34 M091501000048 27.97 15.47 9.55 M091501000049 28.46 18.67 9.83 M091501000050 28.95 12.29 9.63 M091501000051 29.90 -0.08 6.95 M091501000052 ENDDATA 25 0 M091501000053 ENDSUBENT 52 0 M091501099999 SUBENT M0915011 20150901 M080M091501100001 BIB 3 10 M091501100002 REACTION (76-OS-192(G,X)0-NN-1,UNW,SIG,,,EVAL) M091501100003 ANALYSIS The total neutron reaction cross section obtained M091501100004 as sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M091501100005 STATUS Data plotted in Fig. 9. M091501100006 (DEP,M0915008) M091501100007 Evaluated (g,n) reaction cross section. M091501100008 (DEP,M0915009) M091501100009 Evaluated (g,2n) reaction cross section. M091501100010 (DEP,M0915010) M091501100011 Evaluated (g,3n) reaction cross section. M091501100012 ENDBIB 10 0 M091501100013 NOCOMMON 0 0 M091501100014 DATA 3 82 M091501100015 EN DATA DATA-ERR M091501100016 MEV MB MB M091501100017 7.44 -0.05 1.29 M091501100018 7.93 21.53 3.54 M091501100019 8.42 36.85 5.56 M091501100020 8.91 42.47 6.33 M091501100021 9.40 55.8 8.17 M091501100022 9.89 81.04 11.63 M091501100023 10.13 94.18 13.52 M091501100024 10.38 115.53 16.53 M091501100025 10.62 130.21 18.59 M091501100026 10.87 146.13 20.86 M091501100027 11.11 171.02 24.36 M091501100028 11.35 211.38 30.08 M091501100029 11.60 248.35 35.33 M091501100030 11.84 287.86 40.90 M091501100031 12.09 344.97 48.99 M091501100032 12.33 392.14 55.67 M091501100033 12.58 427.47 60.78 M091501100034 12.82 447.86 63.46 M091501100035 13.06 477.09 67.58 M091501100036 13.31 478.70 67.66 M091501100037 13.55 487.08 66.75 M091501100038 13.80 482.69 62.91 M091501100039 14.04 481.35 58.58 M091501100040 14.29 481.24 54.41 M091501100041 14.53 465.02 49.21 M091501100042 14.78 454.91 46.24 M091501100043 15.02 418.45 41.98 M091501100044 15.26 404.70 41.11 M091501100045 15.51 376.45 39.01 M091501100046 15.75 337.78 35.91 M091501100047 16.00 312.26 34.09 M091501100048 16.12 294.92 32.50 M091501100049 16.24 284.86 31.83 M091501100050 16.36 269.29 30.24 M091501100051 16.49 264.90 30.18 M091501100052 16.61 255.61 29.24 M091501100053 16.73 229.29 26.76 M091501100054 16.85 228.69 26.79 M091501100055 16.98 201.87 24.27 M091501100056 17.10 215.57 25.87 M091501100057 17.22 189.92 23.34 M091501100058 17.34 193.81 23.74 M091501100059 17.46 172.69 21.56 M091501100060 17.71 159.38 20.16 M091501100061 17.95 144.41 18.68 M091501100062 18.20 142.83 18.69 M091501100063 18.44 139.17 18.27 M091501100064 18.69 130.81 17.09 M091501100065 18.93 119.83 15.75 M091501100066 19.17 109.58 14.69 M091501100067 19.42 110.35 14.60 M091501100068 19.66 93.58 12.72 M091501100069 19.91 83.38 11.59 M091501100070 20.15 83.29 11.67 M091501100071 20.40 83.44 12.06 M091501100072 20.64 76.39 11.36 M091501100073 20.89 79.29 11.56 M091501100074 21.13 71.66 10.80 M091501100075 21.37 72.73 11.27 M091501100076 21.62 71.89 11.28 M091501100077 21.86 66.59 10.86 M091501100078 22.11 67.11 10.82 M091501100079 22.35 76.41 11.55 M091501100080 22.60 71.28 10.81 M091501100081 22.84 76.97 10.85 M091501100082 23.09 70.61 9.98 M091501100083 23.33 76.59 10.27 M091501100084 23.57 83.58 10.47 M091501100085 23.82 73.12 8.29 M091501100086 24.06 94.05 9.71 M091501100087 24.31 69.84 9.20 M091501100088 24.55 70.79 9.15 M091501100089 25.04 58.07 8.52 M091501100090 25.53 60.37 9.00 M091501100091 26.02 44.99 8.87 M091501100092 26.51 37.68 9.25 M091501100093 27. 38.99 9.47 M091501100094 27.48 33.84 10.06 M091501100095 27.97 23.30 10.17 M091501100096 28.46 27.48 10.37 M091501100097 28.95 17.84 10.12 M091501100098 29.90 -0.11 7.30 M091501100099 ENDDATA 84 0 M091501100100 ENDSUBENT 99 0 M091501199999 ENDENTRY 11 0 M091599999999