ENTRY M0914 20150814 M080M091400000001 SUBENT M0914001 20150814 M080M091400100001 BIB 9 31 M091400100002 TITLE New data on cross sections for partial and total M091400100003 photoneutron reactions on the isotopes 91,94Zr. M091400100004 AUTHOR (V.V.Varlamov,M.A.Makarov,N.N.Peskov,M.E.Stepanov) M091400100005 REFERENCE (J,YF,78,(7),678,2015) M091400100006 #doi:10.7868/S0044002715030198 M091400100007 (J,PAN,78,(5),634,2015) M091400100008 #doi:10.1134/S106377881505018X M091400100009 English translation of J,YF,78,(7),678,2015. M091400100010 INSTITUTE (4RUSMOS) M091400100011 INC-SOURCE (QMPH,ARAD) M091400100012 ANALYSIS The joint analysis of data for total (g,xn) and M091400100013 partial (g,n), (g,2n) and (g,3n) reactions obtained M091400100014 in various experiments was carried out. The new M091400100015 approach to analysis of systematic disagreements M091400100016 between data was proposed on the base of new M091400100017 criteria of systematic uncertainties presence - M091400100018 specially proposed transitional multiplicity M091400100019 functions M091400100020 Fi-theor = SIG(g,in)/SIG(g,xn). M091400100021 Using these functions calculated in the frame of M091400100022 combined photonuclear reaction model new reliable M091400100023 and free from problems of neutron multiplicity M091400100024 sorting data for photoneutron partial reactions M091400100025 cross sections M091400100026 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M091400100027 were evaluated using experimental neutron yield M091400100028 reaction cross sections SIG-exp(g,xn). M091400100029 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M091400100030 STATUS (TABLE,APRVD) Approved by V.Varlamov. M091400100031 HISTORY (20150814C) Data were compiled at the Russia MSU SINP M091400100032 CDFE by V.Varlamov. M091400100033 ENDBIB 31 0 M091400100034 NOCOMMON 0 0 M091400100035 ENDSUBENT 34 0 M091400199999 SUBENT M0914002 20150814 M080M091400200001 BIB 3 8 M091400200002 REACTION (40-ZR-91(G,X)0-NN-1,UNW,SIG,,,EVAL) M091400200003 ANALYSIS The total neutron reaction cross section obtained as M091400200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M091400200005 STATUS Data plotted in Fig. 3. M091400200006 (DEP,M0914003) M091400200007 Evaluated (g,n) reaction cross section. M091400200008 (DEP,M0914004) M091400200009 Evaluated (g,2n) reaction cross section. M091400200010 ENDBIB 8 0 M091400200011 NOCOMMON 0 0 M091400200012 DATA 3 101 M091400200013 EN DATA DATA-ERR M091400200014 MEV MB MB M091400200015 10.80 14.72 4.29 M091400200016 10.96 15.57 4.36 M091400200017 11.11 14.52 4.19 M091400200018 11.27 13.15 3.95 M091400200019 11.42 14.36 3.90 M091400200020 11.57 18.68 4.54 M091400200021 11.73 20.95 5.01 M091400200022 11.89 21.30 4.64 M091400200023 12.04 28.01 5.25 M091400200024 12.19 26.65 5.11 M091400200025 12.35 29.74 5.54 M091400200026 12.50 27.97 5.41 M091400200027 12.66 26.31 5.93 M091400200028 12.81 31.04 6.54 M091400200029 12.97 39.55 7.85 M091400200030 13.12 36.85 7.53 M091400200031 13.28 36.20 7.48 M091400200032 13.43 44.75 8.85 M091400200033 13.59 42.79 8.44 M091400200034 13.74 49.93 9.55 M091400200035 13.90 54.74 10.12 M091400200036 14.05 63.53 11.44 M091400200037 14.21 65.79 11.80 M091400200038 14.36 76.85 13.44 M091400200039 14.52 88.81 15.18 M091400200040 14.67 98.74 16.62 M091400200041 14.83 104.30 17.46 M091400200042 14.98 117.50 19.37 M091400200043 15.14 127.70 20.85 M091400200044 15.29 134.80 21.91 M091400200045 15.45 138.10 22.10 M091400200046 15.60 146.00 22.69 M091400200047 15.76 158.20 24.43 M091400200048 15.91 167.40 25.11 M091400200049 16.07 181.90 27.16 M091400200050 16.22 178.20 26.53 M091400200051 16.38 180.80 27.14 M091400200052 16.53 177.50 26.32 M091400200053 16.68 183.40 27.16 M091400200054 16.84 188.30 27.82 M091400200055 17.00 169.80 25.48 M091400200056 17.15 176.00 26.35 M091400200057 17.30 167.40 25.29 M091400200058 17.46 168.30 25.48 M091400200059 17.61 140.00 21.75 M091400200060 17.77 138.90 21.66 M091400200061 17.92 125.50 19.89 M091400200062 18.08 123.10 19.65 M091400200063 18.23 126.20 20.11 M091400200064 18.39 108.10 17.25 M091400200065 18.54 102.10 16.69 M091400200066 18.70 105.10 17.33 M091400200067 18.85 91.38 15.49 M091400200068 19.01 87.42 14.34 M091400200069 19.16 83.66 13.85 M091400200070 19.32 80.03 12.97 M091400200071 19.47 71.18 12.73 M091400200072 19.63 71.77 12.98 M091400200073 19.78 61.50 11.63 M091400200074 19.94 56.08 11.13 M091400200075 20.09 56.50 11.13 M091400200076 20.25 53.66 11.02 M091400200077 20.40 55.23 12.09 M091400200078 20.56 53.45 11.06 M091400200079 20.71 51.47 10.93 M091400200080 20.87 52.37 11.24 M091400200081 21.02 53.04 11.30 M091400200082 21.18 51.01 11.06 M091400200083 21.33 44.76 10.19 M091400200084 21.48 43.06 9.72 M091400200085 21.64 40.57 9.59 M091400200086 21.80 37.66 9.20 M091400200087 21.95 39.34 9.48 M091400200088 22.11 42.81 10.20 M091400200089 22.26 36.26 9.14 M091400200090 22.41 31.34 8.37 M091400200091 22.57 32.52 8.40 M091400200092 22.72 36.95 9.01 M091400200093 22.88 32.39 8.23 M091400200094 23.03 33.75 8.59 M091400200095 23.19 33.93 8.69 M091400200096 23.34 33.61 8.79 M091400200097 23.50 32.56 8.45 M091400200098 23.73 27.95 7.97 M091400200099 24.04 33.63 11.03 M091400200100 24.35 23.02 7.11 M091400200101 24.66 27.53 8.16 M091400200102 24.97 29.55 8.42 M091400200103 25.28 24.34 8.71 M091400200104 25.59 22.78 8.90 M091400200105 25.90 20.36 8.91 M091400200106 26.21 17.27 8.19 M091400200107 26.52 17.38 8.33 M091400200108 26.83 14.31 7.78 M091400200109 27.14 8.81 6.73 M091400200110 27.45 15.14 8.21 M091400200111 27.76 11.59 7.43 M091400200112 28.14 13.67 7.16 M091400200113 28.76 14.96 9.66 M091400200114 29.38 19.46 10.51 M091400200115 30.00 14.40 10.30 M091400200116 ENDDATA 103 0 M091400200117 ENDSUBENT 116 0 M091400299999 SUBENT M0914003 20150813 M080M091400300001 BIB 4 21 M091400300002 REACTION ((40-ZR-91(G,N)40-ZR-90,,SIG,,,EVAL)+ M091400300003 (40-ZR-91(G,N+P)39-Y-89,,SIG,,,EVAL)) M091400300004 ANALYSIS The contribution of partial reaction (g,n) cross M091400300005 section into the experimental total neutron yield M091400300006 reaction (g,xn) cross section obtained using M091400300007 quasimonoenergetic annihilation photons at Livermore M091400300008 (USA) was evaluated using specially theoretically M091400300009 calculated transitional multiplicity function - M091400300010 ratio M091400300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091400300012 by the way M091400300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M091400300014 REL-REF (R,L0011008,B.L.Berman+,J,PR,162,1098,1967) M091400300015 Experimental data for the total neutron yield M091400300016 reaction (g,xn) cross section. M091400300017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091400300018 Theoretical preequilibrium model of photonuclear M091400300019 reactions based on the Fermi gas densities. M091400300020 STATUS Data plotted in Fig. 3. M091400300021 (DEP,L0011008) M091400300022 The neutron yield reaction (g,xn) cross section. M091400300023 ENDBIB 21 0 M091400300024 NOCOMMON 0 0 M091400300025 DATA 3 101 M091400300026 EN DATA DATA-ERR M091400300027 MEV MB MB M091400300028 10.80 14.72 4.23 M091400300029 10.96 15.57 4.29 M091400300030 11.11 14.52 4.12 M091400300031 11.27 13.15 3.89 M091400300032 11.42 14.36 3.83 M091400300033 11.57 18.68 4.45 M091400300034 11.73 20.95 4.91 M091400300035 11.89 21.30 4.54 M091400300036 12.04 28.01 5.12 M091400300037 12.19 26.65 4.99 M091400300038 12.35 29.74 5.40 M091400300039 12.50 27.97 5.28 M091400300040 12.66 26.31 5.81 M091400300041 12.81 31.04 6.40 M091400300042 12.97 39.55 7.67 M091400300043 13.12 36.85 7.36 M091400300044 13.28 36.20 7.31 M091400300045 13.43 44.75 8.64 M091400300046 13.59 42.79 8.24 M091400300047 13.74 49.93 9.31 M091400300048 13.90 54.74 9.87 M091400300049 14.05 63.53 11.14 M091400300050 14.21 65.79 11.50 M091400300051 14.36 76.85 13.08 M091400300052 14.52 88.81 14.77 M091400300053 14.67 98.74 16.16 M091400300054 14.83 104.30 16.97 M091400300055 14.98 117.50 18.82 M091400300056 15.14 127.70 20.26 M091400300057 15.29 134.80 21.28 M091400300058 15.45 138.10 21.46 M091400300059 15.60 146.00 22.01 M091400300060 15.76 158.20 23.69 M091400300061 15.91 167.40 24.33 M091400300062 16.07 181.90 26.31 M091400300063 16.22 178.20 25.70 M091400300064 16.38 180.80 26.29 M091400300065 16.53 177.50 25.49 M091400300066 16.68 183.40 26.31 M091400300067 16.84 188.30 26.94 M091400300068 17.00 169.80 24.69 M091400300069 17.15 176.00 25.53 M091400300070 17.30 167.40 24.51 M091400300071 17.46 168.30 24.69 M091400300072 17.61 140.00 21.09 M091400300073 17.77 138.90 21.01 M091400300074 17.92 125.50 19.30 M091400300075 18.08 123.10 19.07 M091400300076 18.23 126.20 19.52 M091400300077 18.39 108.10 16.74 M091400300078 18.54 102.10 16.22 M091400300079 18.70 105.00 16.83 M091400300080 18.85 91.02 15.04 M091400300081 19.01 86.28 13.83 M091400300082 19.16 80.97 13.19 M091400300083 19.32 75.04 12.08 M091400300084 19.47 63.80 11.53 M091400300085 19.63 60.62 11.34 M091400300086 19.78 48.27 9.73 M091400300087 19.94 40.38 8.87 M091400300088 20.09 36.97 8.49 M091400300089 20.25 31.73 8.01 M091400300090 20.40 29.49 8.33 M091400300091 20.56 25.86 7.47 M091400300092 20.71 22.80 7.14 M091400300093 20.87 21.59 7.17 M091400300094 21.02 20.77 7.14 M091400300095 21.18 19.42 6.89 M091400300096 21.33 16.94 6.22 M091400300097 21.48 16.50 5.98 M091400300098 21.64 15.95 5.85 M091400300099 21.80 15.31 5.61 M091400300100 21.95 16.57 5.87 M091400300101 22.11 18.62 6.41 M091400300102 22.26 16.21 5.70 M091400300103 22.41 14.30 5.18 M091400300104 22.57 15.07 5.28 M091400300105 22.72 17.31 5.77 M091400300106 22.88 15.28 5.23 M091400300107 23.03 15.99 5.47 M091400300108 23.19 16.11 5.52 M091400300109 23.34 15.97 5.56 M091400300110 23.50 15.46 5.35 M091400300111 23.73 13.26 4.93 M091400300112 24.04 15.97 6.62 M091400300113 24.35 10.96 4.33 M091400300114 24.66 13.12 5.02 M091400300115 24.97 14.02 5.21 M091400300116 25.28 11.45 5.12 M091400300117 25.59 10.60 5.20 M091400300118 25.90 9.33 5.14 M091400300119 26.21 7.81 4.63 M091400300120 26.52 7.76 4.67 M091400300121 26.83 6.31 4.23 M091400300122 27.14 3.84 3.43 M091400300123 27.45 6.53 4.41 M091400300124 27.76 4.96 3.85 M091400300125 28.14 5.80 3.83 M091400300126 28.76 6.27 4.92 M091400300127 29.38 8.06 5.51 M091400300128 30.00 5.86 5.08 M091400300129 ENDDATA 103 0 M091400300130 ENDSUBENT 129 0 M091400399999 SUBENT M0914004 20150813 M080M091400400001 BIB 4 21 M091400400002 REACTION ((40-ZR-91(G,2N)40-ZR-89,,SIG,,,EVAL)+ M091400400003 (40-ZR-91(G,2N+P)39-Y-88,,SIG,,,EVAL)) M091400400004 ANALYSIS The contribution of partial reaction (g,n) cross M091400400005 section into the experimental total neutron yield M091400400006 reaction (g,xn) cross section obtained using M091400400007 quasimonoenergetic annihilation photons at Livermore M091400400008 (USA) was evaluated using specially theoretically M091400400009 calculated transitional multiplicity function - M091400400010 ratio M091400400011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091400400012 by the way M091400400013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M091400400014 REL-REF (R,L0011008,B.L.Berman+,J,PR,162,1098,1967) M091400400015 Experimental data for the total neutron yield M091400400016 reaction (g,xn) cross section. M091400400017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091400400018 Theoretical preequilibrium model of photonuclear M091400400019 reactions based on the Fermi gas densities. M091400400020 STATUS Data plotted in Fig. 3. M091400400021 (DEP,L0046004) M091400400022 The neutron yield reaction (g,xn) cross section. M091400400023 ENDBIB 21 0 M091400400024 NOCOMMON 0 0 M091400400025 DATA 3 51 M091400400026 EN DATA DATA-ERR M091400400027 MEV MB MB M091400400028 18.54 0.01 0.44 M091400400029 18.70 0.08 0.46 M091400400030 18.85 0.35 0.42 M091400400031 19.01 1.14 0.48 M091400400032 19.16 2.68 0.64 M091400400033 19.32 4.98 0.86 M091400400034 19.47 7.38 1.18 M091400400035 19.63 11.15 1.61 M091400400036 19.78 13.23 1.87 M091400400037 19.94 15.70 2.23 M091400400038 20.09 19.53 2.61 M091400400039 20.25 21.93 2.99 M091400400040 20.40 25.74 3.73 M091400400041 20.56 27.59 3.56 M091400400042 20.71 28.67 3.76 M091400400043 20.87 30.78 4.03 M091400400044 21.02 32.27 4.13 M091400400045 21.18 31.59 4.13 M091400400046 21.33 27.82 3.94 M091400400047 21.48 26.57 3.72 M091400400048 21.64 24.62 3.72 M091400400049 21.80 22.35 3.58 M091400400050 21.95 22.78 3.59 M091400400051 22.11 24.18 3.77 M091400400052 22.26 20.05 3.42 M091400400053 22.41 17.03 3.17 M091400400054 22.57 17.45 3.11 M091400400055 22.72 19.65 3.22 M091400400056 22.88 17.11 2.98 M091400400057 23.03 17.76 3.11 M091400400058 23.19 17.82 3.15 M091400400059 23.34 17.65 3.21 M091400400060 23.50 17.10 3.08 M091400400061 23.73 14.68 3.02 M091400400062 24.04 17.67 4.39 M091400400063 24.35 12.06 2.77 M091400400064 24.66 14.42 3.13 M091400400065 24.97 15.54 3.19 M091400400066 25.28 12.89 3.57 M091400400067 25.59 12.17 3.69 M091400400068 25.90 11.03 3.76 M091400400069 26.21 9.46 3.54 M091400400070 26.52 9.61 3.64 M091400400071 26.83 7.99 3.54 M091400400072 27.14 4.97 3.29 M091400400073 27.45 8.60 3.79 M091400400074 27.76 6.63 3.58 M091400400075 28.14 7.86 3.32 M091400400076 28.76 8.67 4.72 M091400400077 29.38 11.27 4.92 M091400400078 30.00 8.08 4.94 M091400400079 ENDDATA 53 0 M091400400080 ENDSUBENT 79 0 M091400499999 SUBENT M0914005 20150814 M080M091400500001 BIB 3 10 M091400500002 REACTION (40-ZR-94(G,X)0-NN-1,UNW,SIG,,,EVAL) M091400500003 ANALYSIS The total neutron reaction cross section obtained as M091400500004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M091400500005 STATUS Data plotted in Fig. 5. M091400500006 (DEP,M0914006) M091400500007 Evaluated (g,n) reaction cross section. M091400500008 (DEP,M0914007) M091400500009 Evaluated (g,2n) reaction cross section. M091400500010 (DEP,M0914008) M091400500011 Evaluated (g,3n) reaction cross section. M091400500012 ENDBIB 10 0 M091400500013 NOCOMMON 0 0 M091400500014 DATA 3 92 M091400500015 EN DATA DATA-ERR M091400500016 MEV MB MB M091400500017 7.85 0.02 0.04 M091400500018 8.16 1.70 0.52 M091400500019 8.47 8.51 1.73 M091400500020 8.80 11.47 2.14 M091400500021 9.10 10.00 1.98 M091400500022 9.40 13.80 2.49 M091400500023 9.72 14.90 2.61 M091400500024 10.03 18.30 3.28 M091400500025 10.32 19.30 3.49 M091400500026 10.63 22.25 3.91 M091400500027 10.95 24.40 4.24 M091400500028 11.22 29.80 4.83 M091400500029 11.57 32.00 5.47 M091400500030 11.89 35.00 5.69 M091400500031 12.19 38.75 6.20 M091400500032 12.51 45.00 6.28 M091400500033 12.81 53.50 7.30 M091400500034 12.98 53.50 7.40 M091400500035 13.13 61.75 8.40 M091400500036 13.28 64.60 8.71 M091400500037 13.43 71.20 9.22 M091400500038 13.60 77.00 10.26 M091400500039 13.75 81.05 10.90 M091400500040 14.05 88.60 11.92 M091400500041 14.36 104.70 13.37 M091400500042 14.67 116.10 15.44 M091400500043 15.00 130.40 17.40 M091400500044 15.13 133.90 19.07 M091400500045 15.30 136.40 17.97 M091400500046 15.45 155.50 22.67 M091400500047 15.61 153.10 20.36 M091400500048 15.76 164.30 25.49 M091400500049 15.90 161.30 22.67 M091400500050 16.06 176.20 25.53 M091400500051 16.22 169.70 26.04 M091400500052 16.37 162.50 25.22 M091400500053 16.54 167.80 26.40 M091400500054 16.68 179.00 28.30 M091400500055 16.84 163.10 26.38 M091400500056 16.99 161.90 26.39 M091400500057 17.16 150.00 24.98 M091400500058 17.26 143.30 24.13 M091400500059 17.45 149.60 25.24 M091400500060 17.60 140.80 23.80 M091400500061 17.77 138.30 24.09 M091400500062 17.92 131.50 22.40 M091400500063 18.07 122.10 21.23 M091400500064 18.23 120.10 20.87 M091400500065 18.38 106.60 19.09 M091400500066 18.55 110.00 19.77 M091400500067 18.70 98.83 16.99 M091400500068 18.85 94.09 17.53 M091400500069 19.00 82.85 16.03 M091400500070 19.15 83.09 16.02 M091400500071 19.31 76.50 15.16 M091400500072 19.47 76.08 15.28 M091400500073 19.70 70.52 13.64 M091400500074 20.02 64.27 12.59 M091400500075 20.32 60.40 12.10 M091400500076 20.63 67.31 13.38 M091400500077 20.95 57.18 11.83 M091400500078 21.25 50.35 11.08 M091400500079 21.56 45.82 10.38 M091400500080 21.88 42.09 9.61 M091400500081 22.19 49.45 11.75 M091400500082 22.50 39.72 10.38 M091400500083 22.80 35.47 9.72 M091400500084 23.11 37.06 10.95 M091400500085 23.43 25.80 10.02 M091400500086 23.73 24.32 9.90 M091400500087 24.05 18.81 9.51 M091400500088 24.35 19.46 9.68 M091400500089 24.68 13.95 8.66 M091400500090 24.98 21.23 8.90 M091400500091 25.28 19.77 10.20 M091400500092 25.60 21.93 9.79 M091400500093 25.89 24.23 9.79 M091400500094 26.23 11.86 7.62 M091400500095 26.53 19.66 8.80 M091400500096 26.85 14.75 8.93 M091400500097 27.14 16.77 8.72 M091400500098 27.45 20.91 10.15 M091400500099 27.75 16.74 9.71 M091400500100 28.15 25.95 11.27 M091400500101 28.54 11.15 8.42 M091400500102 28.84 12.37 8.60 M091400500103 29.15 16.19 9.29 M091400500104 29.55 9.35 7.91 M091400500105 29.77 10.72 8.13 M091400500106 30.24 1.17 6.16 M091400500107 30.75 18.96 9.64 M091400500108 31.00 17.80 9.39 M091400500109 ENDDATA 94 0 M091400500110 ENDSUBENT 109 0 M091400599999 SUBENT M0914006 20150813 M080M091400600001 BIB 4 21 M091400600002 REACTION ((40-ZR-94(G,N)40-ZR-93,,SIG,,,EVAL)+ M091400600003 (40-ZR-94(G,N+P)39-Y-92,,SIG,,,EVAL)) M091400600004 ANALYSIS The contribution of partial reaction (g,n) cross M091400600005 section into the experimental total neutron yield M091400600006 reaction (g,xn) cross section obtained using M091400600007 quasimonoenergetic annihilation photons at Livermore M091400600008 (USA) was evaluated using specially theoretically M091400600009 calculated transitional multiplicity function - M091400600010 ratio M091400600011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091400600012 by the way M091400600013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M091400600014 REL-REF (R,L0011014,B.L.Berman+,J,PR,162,1098,1967) M091400600015 Experimental data for the total neutron yield M091400600016 reaction (g,xn) cross section. M091400600017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091400600018 Theoretical preequilibrium model of photonuclear M091400600019 reactions based on the Fermi gas densities. M091400600020 STATUS Data plotted in Fig. 5. M091400600021 (DEP,L0011008) M091400600022 The neutron yield reaction (g,xn) cross section. M091400600023 ENDBIB 21 0 M091400600024 NOCOMMON 0 0 M091400600025 DATA 3 92 M091400600026 EN DATA DATA-ERR M091400600027 MEV MB MB M091400600028 7.85 0.02 0.03 M091400600029 8.16 1.70 0.43 M091400600030 8.47 8.51 1.55 M091400600031 8.80 11.47 1.92 M091400600032 9.10 10.00 1.79 M091400600033 9.40 13.80 2.23 M091400600034 9.72 14.90 2.32 M091400600035 10.03 18.30 2.93 M091400600036 10.32 19.30 3.12 M091400600037 10.63 22.25 3.48 M091400600038 10.95 24.40 3.77 M091400600039 11.22 29.80 4.25 M091400600040 11.57 32.00 4.85 M091400600041 11.89 35.00 5.01 M091400600042 12.19 38.75 5.45 M091400600043 12.51 45.00 5.41 M091400600044 12.81 53.50 6.26 M091400600045 12.98 53.50 6.36 M091400600046 13.13 61.75 7.20 M091400600047 13.28 64.60 7.45 M091400600048 13.43 71.20 7.84 M091400600049 13.60 77.00 8.76 M091400600050 13.75 81.05 9.32 M091400600051 14.05 88.60 10.20 M091400600052 14.36 104.70 11.34 M091400600053 14.67 115.10 13.10 M091400600054 15.00 125.10 14.32 M091400600055 15.13 125.70 15.54 M091400600056 15.30 123.40 13.99 M091400600057 15.45 135.10 17.30 M091400600058 15.61 127.00 14.75 M091400600059 15.76 129.50 18.08 M091400600060 15.90 120.40 15.26 M091400600061 16.06 124.10 16.51 M091400600062 16.22 112.00 16.19 M091400600063 16.37 101.00 15.07 M091400600064 16.54 97.51 15.12 M091400600065 16.68 98.23 15.66 M091400600066 16.84 84.24 14.09 M091400600067 16.99 79.39 13.69 M091400600068 17.16 69.70 12.59 M091400600069 17.26 64.44 11.95 M091400600070 17.45 63.63 12.16 M091400600071 17.60 57.40 11.23 M091400600072 17.77 53.81 11.07 M091400600073 17.92 49.21 10.15 M091400600074 18.07 44.01 9.43 M091400600075 18.23 41.80 9.13 M091400600076 18.38 35.80 8.18 M091400600077 18.55 35.67 8.34 M091400600078 18.70 31.06 7.16 M091400600079 18.85 28.68 7.15 M091400600080 19.00 24.51 6.40 M091400600081 19.15 23.94 6.33 M091400600082 19.31 21.49 5.89 M091400600083 19.47 20.85 5.86 M091400600084 19.70 18.79 5.23 M091400600085 20.02 16.54 4.75 M091400600086 20.32 15.05 4.48 M091400600087 20.63 16.25 4.90 M091400600088 20.95 13.44 4.24 M091400600089 21.25 11.65 3.86 M091400600090 21.56 10.59 3.58 M091400600091 21.88 9.87 3.33 M091400600092 22.19 12.00 4.07 M091400600093 22.50 10.04 3.57 M091400600094 22.80 9.30 3.37 M091400600095 23.11 10.07 3.79 M091400600096 23.43 7.26 3.37 M091400600097 23.73 7.10 3.38 M091400600098 24.05 5.73 3.26 M091400600099 24.35 6.13 3.41 M091400600100 24.68 4.49 3.04 M091400600101 24.98 6.86 3.26 M091400600102 25.28 6.36 3.68 M091400600103 25.60 6.96 3.61 M091400600104 25.89 7.59 3.65 M091400600105 26.23 3.65 2.65 M091400600106 26.53 5.99 3.20 M091400600107 26.85 4.44 3.09 M091400600108 27.14 5.01 3.07 M091400600109 27.45 6.20 3.60 M091400600110 27.75 4.93 3.34 M091400600111 28.15 7.56 4.05 M091400600112 28.54 3.20 2.76 M091400600113 28.84 3.51 2.83 M091400600114 29.15 4.52 3.12 M091400600115 29.55 2.55 2.47 M091400600116 29.77 2.88 2.56 M091400600117 30.24 0.30 1.65 M091400600118 30.75 4.78 3.14 M091400600119 31.00 4.42 3.01 M091400600120 ENDDATA 94 0 M091400600121 ENDSUBENT 120 0 M091400699999 SUBENT M0914007 20150813 M080M091400700001 BIB 4 21 M091400700002 REACTION ((40-ZR-94(G,2N)40-ZR-92,,SIG,,,EVAL)+ M091400700003 (40-ZR-94(G,2N+P)39-Y-91,,SIG,,,EVAL)) M091400700004 ANALYSIS The contribution of partial reaction (g,n) cross M091400700005 section into the experimental total neutron yield M091400700006 reaction (g,xn) cross section obtained using M091400700007 quasimonoenergetic annihilation photons at Livermore M091400700008 (USA) was evaluated using specially theoretically M091400700009 calculated transitional multiplicity function - M091400700010 ratio M091400700011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091400700012 by the way M091400700013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M091400700014 REL-REF (R,L0011014,B.L.Berman+,J,PR,162,1098,1967) M091400700015 Experimental data for the total neutron yield M091400700016 reaction (g,xn) cross section. M091400700017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091400700018 Theoretical preequilibrium model of photonuclear M091400700019 reactions based on the Fermi gas densities. M091400700020 STATUS Data plotted in Fig. 5. M091400700021 (DEP,L0046004) M091400700022 The neutron yield reaction (g,xn) cross section. M091400700023 ENDBIB 21 0 M091400700024 NOCOMMON 0 0 M091400700025 DATA 3 68 M091400700026 EN DATA DATA-ERR M091400700027 MEV MB MB M091400700028 14.36 0.07 1.98 M091400700029 14.67 0.99 2.28 M091400700030 15.00 5.29 3.01 M091400700031 15.13 8.18 3.45 M091400700032 15.30 13.07 3.91 M091400700033 15.45 20.39 5.28 M091400700034 15.61 26.17 5.52 M091400700035 15.76 34.78 7.31 M091400700036 15.90 40.84 7.32 M091400700037 16.06 52.15 8.90 M091400700038 16.22 57.63 9.75 M091400700039 16.37 61.48 10.05 M091400700040 16.54 70.32 11.17 M091400700041 16.68 80.75 12.52 M091400700042 16.84 78.88 12.18 M091400700043 16.99 82.55 12.58 M091400700044 17.16 80.34 12.29 M091400700045 17.26 78.82 12.08 M091400700046 17.45 85.93 12.97 M091400700047 17.60 83.35 12.46 M091400700048 17.77 84.47 12.91 M091400700049 17.92 82.28 12.14 M091400700050 18.07 78.12 11.70 M091400700051 18.23 78.35 11.63 M091400700052 18.38 70.80 10.82 M091400700053 18.55 74.36 11.33 M091400700054 18.70 67.77 9.74 M091400700055 18.85 65.41 10.30 M091400700056 19.00 58.34 9.56 M091400700057 19.15 59.15 9.61 M091400700058 19.31 55.01 9.20 M091400700059 19.47 55.23 9.35 M091400700060 19.70 51.73 8.34 M091400700061 20.02 47.73 7.78 M091400700062 20.32 45.35 7.57 M091400700063 20.63 51.06 8.41 M091400700064 20.95 43.74 7.53 M091400700065 21.25 38.70 7.17 M091400700066 21.56 35.23 6.75 M091400700067 21.88 32.21 6.25 M091400700068 22.19 37.45 7.62 M091400700069 22.50 29.68 6.76 M091400700070 22.80 26.16 6.32 M091400700071 23.11 26.99 7.11 M091400700072 23.43 18.53 6.62 M091400700073 23.73 17.22 6.49 M091400700074 24.05 13.04 6.22 M091400700075 24.35 13.17 6.18 M091400700076 24.68 9.17 5.45 M091400700077 24.98 13.61 5.36 M091400700078 25.28 12.34 6.03 M091400700079 25.60 13.16 5.52 M091400700080 25.89 13.96 5.29 M091400700081 26.23 6.47 4.02 M091400700082 26.53 10.19 4.37 M091400700083 26.85 7.21 4.27 M091400700084 27.14 7.78 3.98 M091400700085 27.45 9.15 4.42 M091400700086 27.75 6.94 4.05 M091400700087 28.15 10.02 4.46 M091400700088 28.54 4.03 3.13 M091400700089 28.84 4.27 3.08 M091400700090 29.15 5.36 3.25 M091400700091 29.55 2.93 2.60 M091400700092 29.77 3.26 2.63 M091400700093 30.24 0.33 1.79 M091400700094 30.75 5.14 2.97 M091400700095 31.00 4.71 2.83 M091400700096 ENDDATA 70 0 M091400700097 ENDSUBENT 96 0 M091400799999 SUBENT M0914008 20150813 M080M091400800001 BIB 4 21 M091400800002 REACTION ((40-ZR-94(G,3N)40-ZR-91,,SIG,,,EVAL)+ M091400800003 (40-ZR-94(G,3N+P)39-Y-90,,SIG,,,EVAL)) M091400800004 ANALYSIS The contribution of partial reaction (g,n) cross M091400800005 section into the experimental total neutron yield M091400800006 reaction (g,xn) cross section obtained using M091400800007 quasimonoenergetic annihilation photons at Livermore M091400800008 (USA) was evaluated using specially theoretically M091400800009 calculated transitional multiplicity function - M091400800010 ratio M091400800011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M091400800012 by the way M091400800013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M091400800014 REL-REF (R,L0011014,B.L.Berman+,J,PR,162,1098,1967) M091400800015 Experimental data for the total neutron yield M091400800016 reaction (g,xn) cross section. M091400800017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M091400800018 Theoretical preequilibrium model of photonuclear M091400800019 reactions based on the Fermi gas densities. M091400800020 STATUS Data plotted in Fig. 5. M091400800021 (DEP,L0046004) M091400800022 The neutron yield reaction (g,xn) cross section. M091400800023 ENDBIB 21 0 M091400800024 NOCOMMON 0 0 M091400800025 DATA 3 22 M091400800026 EN DATA DATA-ERR M091400800027 MEV MB MB M091400800028 24.05 0.04 0.03 M091400800029 24.35 0.15 0.08 M091400800030 24.68 0.27 0.16 M091400800031 24.98 0.75 0.27 M091400800032 25.28 1.07 0.48 M091400800033 25.60 1.80 0.66 M091400800034 25.89 2.67 0.84 M091400800035 26.23 1.72 0.95 M091400800036 26.53 3.47 1.22 M091400800037 26.85 3.09 1.56 M091400800038 27.14 3.97 1.66 M091400800039 27.45 5.54 2.12 M091400800040 27.75 4.86 2.31 M091400800041 28.15 8.36 2.74 M091400800042 28.54 3.90 2.52 M091400800043 28.84 4.58 2.68 M091400800044 29.15 6.30 2.91 M091400800045 29.55 3.85 2.82 M091400800046 29.77 4.55 2.94 M091400800047 30.24 0.52 2.71 M091400800048 30.75 9.02 3.52 M091400800049 31.00 8.66 3.53 M091400800050 ENDDATA 24 0 M091400800051 ENDSUBENT 50 0 M091400899999 ENDENTRY 8 0 M091499999999