ENTRY M0967 20180411 M096M096700000001 SUBENT M0967001 20180411 M096M096700100001 BIB 9 34 M096700100002 TITLE The reliability of photoneutron cross sections for M096700100003 90,91,92,94Zr. M096700100004 AUTHOR (V.V.Varlamov,A.I.Davydov,B.S.Ishkhanov,V.N.Orlin) M096700100005 REFERENCE (J,EPJ/A,54,74,2018) M096700100006 #doi:10.1140/epja/i2018-12508-4 M096700100007 (J,YF,78,(7),678,2015) M096700100008 #doi:10.7868/S0044002715030198 M096700100009 Data for 91,94Zr. M096700100010 (J,PAN,78,(5),634,2015) M096700100011 #doi:10.1134/S106377881505018X M096700100012 English translation of J,YF,78,(7),678,2015. M096700100013 INSTITUTE (4RUSMOS) M096700100014 INC-SOURCE (QMPH,ARAD) M096700100015 ANALYSIS The joint analysis of data for total (g,xn) and M096700100016 partial (g,n), (g,2n) and (g,3n) reactions obtained M096700100017 in various experiments was carried out. The new M096700100018 approach to analysis of systematic disagreements M096700100019 between data was proposed on the base of new M096700100020 criteria of systematic uncertainties presence - M096700100021 specially proposed transitional multiplicity M096700100022 functions M096700100023 Fi-theor = SIG(g,in)/SIG(g,xn). M096700100024 Using these functions calculated in the frame of M096700100025 combined photonuclear reaction model new reliable M096700100026 and free from problems of neutron multiplicity M096700100027 sorting data for photoneutron partial reactions M096700100028 cross sections M096700100029 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M096700100030 were evaluated using experimental neutron yield M096700100031 reaction cross sections SIG-exp(g,xn). M096700100032 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M096700100033 STATUS (APRVD) By V.Varlamov. M096700100034 HISTORY (20180411C) Data were compiled at the Russia MSU SINP M096700100035 CDFE by V.Varlamov. M096700100036 ENDBIB 34 0 M096700100037 NOCOMMON 0 0 M096700100038 ENDSUBENT 37 0 M096700199999 SUBENT M0967002 20180411 M096M096700200001 BIB 3 8 M096700200002 REACTION (40-ZR-90(G,X)0-NN-1,UNW,SIG,,,EVAL) M096700200003 ANALYSIS The total neutron reaction cross section obtained as M096700200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M096700200005 STATUS (TABLE) Data plotted in Fig. 6. M096700200006 (DEP,M0967003) M096700200007 Evaluated (g,n) reaction cross section. M096700200008 (DEP,M0967004) M096700200009 Evaluated (g,2n) reaction cross section. M096700200010 ENDBIB 8 0 M096700200011 NOCOMMON 0 0 M096700200012 DATA 3 102 M096700200013 EN DATA DATA-ERR M096700200014 MEV MB MB M096700200015 12.17 5.00 2.35 M096700200016 12.31 9.00 2.65 M096700200017 12.45 11.00 2.81 M096700200018 12.58 13.00 2.97 M096700200019 12.72 19.00 3.41 M096700200020 12.86 26.00 3.92 M096700200021 12.99 31.00 4.29 M096700200022 13.13 34.00 4.52 M096700200023 13.26 37.00 4.75 M096700200024 13.40 42.00 5.12 M096700200025 13.54 43.00 5.21 M096700200026 13.67 50.00 5.72 M096700200027 13.81 56.00 6.16 M096700200028 13.95 61.00 6.53 M096700200029 14.08 67.00 6.97 M096700200030 14.22 74.00 7.48 M096700200031 14.35 78.00 7.78 M096700200032 14.49 86.00 8.36 M096700200033 14.63 96.00 9.08 M096700200034 14.76 95.00 9.03 M096700200035 14.90 109.00 10.03 M096700200036 15.03 117.00 10.61 M096700200037 15.17 138.00 12.10 M096700200038 15.31 137.00 12.05 M096700200039 15.44 153.00 13.19 M096700200040 15.58 158.00 13.56 M096700200041 15.72 162.00 13.86 M096700200042 15.85 184.00 15.42 M096700200043 15.99 198.00 16.41 M096700200044 16.12 204.00 16.85 M096700200045 16.26 206.00 17.01 M096700200046 16.40 204.00 16.89 M096700200047 16.53 208.00 17.19 M096700200048 16.67 215.00 17.70 M096700200049 16.81 206.00 17.09 M096700200050 16.94 202.00 16.83 M096700200051 17.08 202.00 16.85 M096700200052 17.21 196.00 16.45 M096700200053 17.35 190.00 16.05 M096700200054 17.49 179.00 15.30 M096700200055 17.62 171.00 14.76 M096700200056 17.76 178.00 15.27 M096700200057 17.90 171.00 14.80 M096700200058 18.03 160.00 14.05 M096700200059 18.17 146.00 13.09 M096700200060 18.30 139.00 12.62 M096700200061 18.44 130.00 12.01 M096700200062 18.58 127.00 11.82 M096700200063 18.71 119.00 11.28 M096700200064 18.85 123.00 11.58 M096700200065 18.98 117.00 11.18 M096700200066 19.12 111.00 10.78 M096700200067 19.26 109.00 10.66 M096700200068 19.39 98.00 9.91 M096700200069 19.53 101.00 10.14 M096700200070 19.67 101.00 10.16 M096700200071 19.80 97.00 9.90 M096700200072 19.94 94.00 9.71 M096700200073 20.07 90.00 9.45 M096700200074 20.21 78.00 8.63 M096700200075 20.35 78.00 8.65 M096700200076 20.48 81.18 8.86 M096700200077 20.62 81.18 8.88 M096700200078 20.76 69.30 8.07 M096700200079 20.89 77.22 8.64 M096700200080 21.03 78.21 8.73 M096700200081 21.16 69.30 8.13 M096700200082 21.30 73.26 8.42 M096700200083 21.44 68.31 8.10 M096700200084 21.57 67.32 8.59 M096700200085 21.71 67.62 8.59 M096700200086 21.84 72.96 8.90 M096700200087 21.98 63.92 7.86 M096700200088 22.12 47.70 6.34 M096700200089 22.25 59.34 6.63 M096700200090 22.39 54.12 5.93 M096700200091 22.53 60.83 6.00 M096700200092 22.66 49.40 5.07 M096700200093 22.80 56.21 5.21 M096700200094 22.93 41.89 4.30 M096700200095 23.07 54.51 4.81 M096700200096 23.21 42.90 4.09 M096700200097 23.34 51.48 4.50 M096700200098 23.48 43.52 4.03 M096700200099 23.62 42.84 3.98 M096700200100 23.75 42.16 3.94 M096700200101 23.89 43.92 4.03 M096700200102 24.02 37.21 3.67 M096700200103 24.16 30.00 3.31 M096700200104 24.30 39.00 3.79 M096700200105 24.43 35.40 3.64 M096700200106 24.57 34.22 3.59 M096700200107 24.71 28.91 3.29 M096700200108 24.84 26.10 3.19 M096700200109 24.98 27.26 3.25 M096700200110 25.11 21.66 2.97 M096700200111 25.25 30.16 3.43 M096700200112 25.39 24.94 3.17 M096700200113 25.52 25.08 3.19 M096700200114 25.66 24.94 3.17 M096700200115 25.79 26.10 3.24 M096700200116 25.93 27.26 3.29 M096700200117 ENDDATA 104 0 M096700200118 ENDSUBENT 117 0 M096700299999 SUBENT M0967003 20150813 M096M096700300001 BIB 4 21 M096700300002 REACTION ((40-ZR-90(G,N)40-ZR-89,,SIG,,,EVAL)+ M096700300003 (40-ZR-90(G,N+P)39-Y-88,,SIG,,,EVAL)) M096700300004 ANALYSIS The contribution of partial reaction (g,n) cross M096700300005 section into the experimental total neutron yield M096700300006 reaction (g,xn) cross section obtained using M096700300007 quasimonoenergetic annihilation photons at Livermore M096700300008 (USA) was evaluated using specially theoretically M096700300009 calculated transitional multiplicity function - M096700300010 ratio M096700300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M096700300012 by the way M096700300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M096700300014 REL-REF (R,L0027011,A.Lepretre+,J,NP/A,175,609,1971) M096700300015 Experimental data for the total neutron yield M096700300016 reaction (g,xn) cross section. M096700300017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M096700300018 Theoretical preequilibrium model of photonuclear M096700300019 reactions based on the Fermi gas densities. M096700300020 STATUS (TABLE) Data plotted in Fig. 6. M096700300021 (DEP,L0027011) M096700300022 The neutron yield reaction (g,xn) cross section. M096700300023 ENDBIB 21 0 M096700300024 NOCOMMON 0 0 M096700300025 DATA 3 102 M096700300026 EN DATA DATA-ERR M096700300027 MEV MB MB M096700300028 12.17 5.00 2.35 M096700300029 12.31 9.00 2.65 M096700300030 12.45 11.00 2.81 M096700300031 12.58 13.00 2.97 M096700300032 12.72 19.00 3.41 M096700300033 12.86 26.00 3.92 M096700300034 12.99 31.00 4.29 M096700300035 13.13 34.00 4.52 M096700300036 13.26 37.00 4.75 M096700300037 13.40 42.00 5.12 M096700300038 13.54 43.00 5.21 M096700300039 13.67 50.00 5.72 M096700300040 13.81 56.00 6.16 M096700300041 13.95 61.00 6.53 M096700300042 14.08 67.00 6.97 M096700300043 14.22 74.00 7.48 M096700300044 14.35 78.00 7.78 M096700300045 14.49 86.00 8.36 M096700300046 14.63 96.00 9.08 M096700300047 14.76 95.00 9.03 M096700300048 14.90 109.00 10.03 M096700300049 15.03 117.00 10.61 M096700300050 15.17 138.00 12.10 M096700300051 15.31 137.00 12.05 M096700300052 15.44 153.00 13.19 M096700300053 15.58 158.00 13.56 M096700300054 15.72 162.00 13.86 M096700300055 15.85 184.00 15.42 M096700300056 15.99 198.00 16.41 M096700300057 16.12 204.00 16.85 M096700300058 16.26 206.00 17.01 M096700300059 16.40 204.00 16.89 M096700300060 16.53 208.00 17.19 M096700300061 16.67 215.00 17.70 M096700300062 16.81 206.00 17.09 M096700300063 16.94 202.00 16.83 M096700300064 17.08 202.00 16.85 M096700300065 17.21 196.00 16.45 M096700300066 17.35 190.00 16.05 M096700300067 17.49 179.00 15.30 M096700300068 17.62 171.00 14.76 M096700300069 17.76 178.00 15.27 M096700300070 17.90 171.00 14.80 M096700300071 18.03 160.00 14.05 M096700300072 18.17 146.00 13.09 M096700300073 18.30 139.00 12.62 M096700300074 18.44 130.00 12.01 M096700300075 18.58 127.00 11.82 M096700300076 18.71 119.00 11.28 M096700300077 18.85 123.00 11.58 M096700300078 18.98 117.00 11.18 M096700300079 19.12 111.00 10.78 M096700300080 19.26 109.00 10.66 M096700300081 19.39 98.00 9.91 M096700300082 19.53 101.00 10.14 M096700300083 19.67 101.00 10.16 M096700300084 19.80 97.00 9.90 M096700300085 19.94 94.00 9.71 M096700300086 20.07 90.00 9.45 M096700300087 20.21 78.00 8.63 M096700300088 20.35 78.00 8.65 M096700300089 20.48 81.18 8.86 M096700300090 20.62 81.18 8.88 M096700300091 20.76 69.30 8.07 M096700300092 20.89 77.22 8.64 M096700300093 21.03 78.21 8.73 M096700300094 21.16 69.30 8.13 M096700300095 21.30 73.26 8.42 M096700300096 21.44 68.31 8.10 M096700300097 21.57 67.32 8.59 M096700300098 21.71 67.62 8.59 M096700300099 21.84 72.96 8.90 M096700300100 21.98 61.20 7.86 M096700300101 22.12 43.46 6.31 M096700300102 22.25 51.06 6.54 M096700300103 22.39 44.22 5.79 M096700300104 22.53 46.97 5.75 M096700300105 22.66 35.75 4.74 M096700300106 22.80 38.50 4.73 M096700300107 22.93 27.14 3.78 M096700300108 23.07 33.18 4.04 M096700300109 23.21 24.70 3.29 M096700300110 23.34 28.08 3.46 M096700300111 23.48 22.44 2.94 M096700300112 23.62 20.40 2.68 M096700300113 23.75 19.04 2.51 M096700300114 23.89 18.72 2.41 M096700300115 24.02 15.25 2.04 M096700300116 24.16 12.00 1.78 M096700300117 24.30 14.95 1.94 M096700300118 24.43 12.60 1.70 M096700300119 24.57 12.18 1.67 M096700300120 24.71 10.29 1.48 M096700300121 24.84 8.55 1.28 M096700300122 24.98 8.93 1.31 M096700300123 25.11 6.84 1.13 M096700300124 25.25 9.36 1.23 M096700300125 25.39 7.74 1.13 M096700300126 25.52 7.48 1.07 M096700300127 25.66 7.74 1.08 M096700300128 25.79 8.10 1.11 M096700300129 25.93 8.46 1.08 M096700300130 ENDDATA 104 0 M096700300131 ENDSUBENT 130 0 M096700399999 SUBENT M0967004 20050221 M096M096700400001 BIB 4 20 M096700400002 REACTION (40-ZR-90(G,2N)40-ZR-88,,SIG,,,EVAL) M096700400003 ANALYSIS The contribution of partial reaction (g,2n) cross M096700400004 section into the experimental total neutron yield M096700400005 reaction (g,xn) cross section obtained using M096700400006 quasimonoenergetic annihilation photons at Livermore M096700400007 (USA) was evaluated using specially theoretically M096700400008 calculated transitional multiplicity function - M096700400009 ratio M096700400010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M096700400011 by the way M096700400012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M096700400013 REL-REF (R,L0027011,A.Lepretre+,J,NP/A,175,609,1971) M096700400014 Experimental data for the total neutron yield M096700400015 reaction (g,xn) cross section. M096700400016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M096700400017 Theoretical preequilibrium model of photonuclear M096700400018 reactions based on the Fermi gas densities. M096700400019 STATUS (TABLE) Data plotted in Fig. 6. M096700400020 (DEP,L0027011) M096700400021 The neutron yield reaction (g,xn) cross section. M096700400022 ENDBIB 20 0 M096700400023 NOCOMMON 0 0 M096700400024 DATA 3 30 M096700400025 EN DATA DATA-ERR M096700400026 MEV MB MB M096700400027 21.98 2.72 0.43 M096700400028 22.12 4.24 0.74 M096700400029 22.25 8.28 1.31 M096700400030 22.39 9.90 1.59 M096700400031 22.53 13.86 2.11 M096700400032 22.66 13.65 2.22 M096700400033 22.80 17.71 2.71 M096700400034 22.93 14.75 2.50 M096700400035 23.07 21.33 3.24 M096700400036 23.21 18.20 2.97 M096700400037 23.34 23.40 3.58 M096700400038 23.48 21.08 3.39 M096700400039 23.62 22.44 3.62 M096700400040 23.75 23.12 3.74 M096700400041 23.89 25.20 3.99 M096700400042 24.02 21.96 3.72 M096700400043 24.16 18.00 3.33 M096700400044 24.30 24.05 3.98 M096700400045 24.43 22.80 3.91 M096700400046 24.57 22.04 3.83 M096700400047 24.71 18.62 3.50 M096700400048 24.84 17.55 3.44 M096700400049 24.98 18.33 3.53 M096700400050 25.11 14.82 3.19 M096700400051 25.25 20.80 3.83 M096700400052 25.39 17.20 3.48 M096700400053 25.52 17.60 3.53 M096700400054 25.66 17.20 3.50 M096700400055 25.79 18.00 3.58 M096700400056 25.93 18.80 3.67 M096700400057 ENDDATA 32 0 M096700400058 ENDSUBENT 57 0 M096700499999 SUBENT M0967005 20180411 M096M096700500001 BIB 3 8 M096700500002 REACTION (40-ZR-92(G,X)0-NN-1,UNW,SIG,,,EVAL) M096700500003 ANALYSIS The total neutron reaction cross section obtained as M096700500004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M096700500005 STATUS (TABLE) Data plotted in Fig. 9. M096700500006 (DEP,M0967006) M096700500007 Evaluated (g,n) reaction cross section. M096700500008 (DEP,M0967007) M096700500009 Evaluated (g,2n) reaction cross section. M096700500010 ENDBIB 8 0 M096700500011 NOCOMMON 0 0 M096700500012 DATA 3 99 M096700500013 EN DATA DATA-ERR M096700500014 MEV MB MB M096700500015 10.026 2.41 5.37 M096700500016 10.181 9.18 4.21 M096700500017 10.336 6.75 4.13 M096700500018 10.491 9.21 4.14 M096700500019 10.646 9.54 3.94 M096700500020 10.801 13.25 4.13 M096700500021 10.955 12.06 3.88 M096700500022 11.11 13.32 3.99 M096700500023 11.265 20.16 4.42 M096700500024 11.42 20.62 4.23 M096700500025 11.575 17.17 3.82 M096700500026 11.73 26.57 4.44 M096700500027 11.885 29.81 4.66 M096700500028 12.039 29.46 4.56 M096700500029 12.194 30.70 4.70 M096700500030 12.349 44.58 5.39 M096700500031 12.504 39.21 3.69 M096700500032 12.659 41.73 5.37 M096700500033 12.814 44.67 5.58 M096700500034 12.969 52.49 6.07 M096700500035 13.123 49.00 6.01 M096700500036 13.278 51.51 5.25 M096700500037 13.433 50.28 5.29 M096700500038 13.588 65.99 5.93 M096700500039 13.743 64.78 5.93 M096700500040 13.898 72.07 6.26 M096700500041 14.053 75.34 6.41 M096700500042 14.207 85.79 6.52 M096700500043 14.362 96.52 7.21 M096700500044 14.517 95.39 7.26 M096700500045 14.672 105.64 7.62 M096700500046 14.827 116.12 7.28 M096700500047 14.982 120.05 8.19 M096700500048 15.136 138.91 8.80 M096700500049 15.291 149.84 9.22 M096700500050 15.446 156.69 9.48 M096700500051 15.601 154.22 9.49 M096700500052 15.756 169.52 10.43 M096700500053 15.911 180.94 11.26 M096700500054 16.066 156.63 10.57 M096700500055 16.22 177.04 11.74 M096700500056 16.375 167.75 12.26 M096700500057 16.53 162.45 7.33 M096700500058 16.685 170.27 7.85 M096700500059 16.84 160.31 7.66 M096700500060 16.995 158.53 7.99 M096700500061 17.15 157.65 8.48 M096700500062 17.304 146.39 10.44 M096700500063 17.459 148.55 10.65 M096700500064 17.614 132.07 10.60 M096700500065 17.769 133.15 10.84 M096700500066 17.924 119.13 10.84 M096700500067 18.079 122.57 9.16 M096700500068 18.233 108.92 8.97 M096700500069 18.388 106.89 9.30 M096700500070 18.543 101.99 9.30 M096700500071 18.698 93.99 9.32 M096700500072 18.853 82.56 9.18 M096700500073 19.008 84.28 9.04 M096700500074 19.163 81.93 9.60 M096700500075 19.317 78.59 9.53 M096700500076 19.472 80.79 9.84 M096700500077 19.627 71.40 9.99 M096700500078 19.782 74.75 10.23 M096700500079 19.937 72.33 10.25 M096700500080 20.092 72.64 10.60 M096700500081 20.247 67.76 7.45 M096700500082 20.401 66.84 10.72 M096700500083 20.556 63.50 10.29 M096700500084 20.711 59.59 11.03 M096700500085 20.866 56.44 11.24 M096700500086 21.021 61.98 13.20 M096700500087 21.176 57.29 11.66 M096700500088 21.33 48.50 12.37 M096700500089 21.485 51.57 12.80 M096700500090 21.64 49.08 13.16 M096700500091 21.795 47.68 12.31 M096700500092 21.95 42.82 13.52 M096700500093 22.105 45.64 13.97 M096700500094 22.26 39.34 14.20 M096700500095 22.414 36.30 12.97 M096700500096 22.647 35.67 10.87 M096700500097 22.957 35.57 11.50 M096700500098 23.267 29.66 11.50 M096700500099 23.576 34.72 13.49 M096700500100 23.886 30.22 8.92 M096700500101 24.196 28.82 9.45 M096700500102 24.505 26.78 9.37 M096700500103 24.815 21.78 9.45 M096700500104 25.125 23.16 13.57 M096700500105 25.434 22.25 14.11 M096700500106 25.744 21.37 14.35 M096700500107 26.054 18.40 14.27 M096700500108 26.364 24.11 15.36 M096700500109 26.673 23.58 15.45 M096700500110 26.983 21.94 14.61 M096700500111 27.293 23.45 14.67 M096700500112 27.602 24.78 13.66 M096700500113 27.834 24.35 21.66 M096700500114 ENDDATA 101 0 M096700500115 ENDSUBENT 114 0 M096700599999 SUBENT M0967006 20150813 M096M096700600001 BIB 4 21 M096700600002 REACTION ((40-ZR-92(G,N)40-ZR-91,,SIG,,,EVAL)+ M096700600003 (40-ZR-92(G,N+P)39-Y-90,,SIG,,,EVAL)) M096700600004 ANALYSIS The contribution of partial reaction (g,n) cross M096700600005 section into the experimental total neutron yield M096700600006 reaction (g,xn) cross section obtained using M096700600007 quasimonoenergetic annihilation photons at Livermore M096700600008 (USA) was evaluated using specially theoretically M096700600009 calculated transitional multiplicity function - M096700600010 ratio M096700600011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M096700600012 by the way M096700600013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M096700600014 REL-REF (R,L0011011,B.L.Berman+,J,PR,162,1098,1967) M096700600015 Experimental data for the total neutron yield M096700600016 reaction (g,xn) cross section. M096700600017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M096700600018 Theoretical preequilibrium model of photonuclear M096700600019 reactions based on the Fermi gas densities. M096700600020 STATUS (TABLE) Data plotted in Fig. 9. M096700600021 (DEP,L0011011) M096700600022 The neutron yield reaction (g,xn) cross section. M096700600023 ENDBIB 21 0 M096700600024 NOCOMMON 0 0 M096700600025 DATA 3 102 M096700600026 EN DATA DATA-ERR M096700600027 MEV MB MB M096700600028 12.17 5.00 2.35 M096700600029 12.31 9.00 2.65 M096700600030 12.45 11.00 2.81 M096700600031 12.58 13.00 2.97 M096700600032 12.72 19.00 3.41 M096700600033 12.86 26.00 3.92 M096700600034 12.99 31.00 4.29 M096700600035 13.13 34.00 4.52 M096700600036 13.26 37.00 4.75 M096700600037 13.40 42.00 5.12 M096700600038 13.54 43.00 5.21 M096700600039 13.67 50.00 5.72 M096700600040 13.81 56.00 6.16 M096700600041 13.95 61.00 6.53 M096700600042 14.08 67.00 6.97 M096700600043 14.22 74.00 7.48 M096700600044 14.35 78.00 7.78 M096700600045 14.49 86.00 8.36 M096700600046 14.63 96.00 9.08 M096700600047 14.76 95.00 9.03 M096700600048 14.90 109.00 10.03 M096700600049 15.03 117.00 10.61 M096700600050 15.17 138.00 12.10 M096700600051 15.31 137.00 12.05 M096700600052 15.44 153.00 13.19 M096700600053 15.58 158.00 13.56 M096700600054 15.72 162.00 13.86 M096700600055 15.85 184.00 15.42 M096700600056 15.99 198.00 16.41 M096700600057 16.12 204.00 16.85 M096700600058 16.26 206.00 17.01 M096700600059 16.40 204.00 16.89 M096700600060 16.53 208.00 17.19 M096700600061 16.67 215.00 17.70 M096700600062 16.81 206.00 17.09 M096700600063 16.94 202.00 16.83 M096700600064 17.08 202.00 16.85 M096700600065 17.21 196.00 16.45 M096700600066 17.35 190.00 16.05 M096700600067 17.49 179.00 15.30 M096700600068 17.62 171.00 14.76 M096700600069 17.76 178.00 15.27 M096700600070 17.90 171.00 14.80 M096700600071 18.03 160.00 14.05 M096700600072 18.17 146.00 13.09 M096700600073 18.30 139.00 12.62 M096700600074 18.44 130.00 12.01 M096700600075 18.58 127.00 11.82 M096700600076 18.71 119.00 11.28 M096700600077 18.85 123.00 11.58 M096700600078 18.98 117.00 11.18 M096700600079 19.12 111.00 10.78 M096700600080 19.26 109.00 10.66 M096700600081 19.39 98.00 9.91 M096700600082 19.53 101.00 10.14 M096700600083 19.67 101.00 10.16 M096700600084 19.80 97.00 9.90 M096700600085 19.94 94.00 9.71 M096700600086 20.07 90.00 9.45 M096700600087 20.21 78.00 8.63 M096700600088 20.35 78.00 8.65 M096700600089 20.48 81.18 8.86 M096700600090 20.62 81.18 8.88 M096700600091 20.76 69.30 8.07 M096700600092 20.89 77.22 8.64 M096700600093 21.03 78.21 8.73 M096700600094 21.16 69.30 8.13 M096700600095 21.30 73.26 8.42 M096700600096 21.44 68.31 8.10 M096700600097 21.57 67.32 8.59 M096700600098 21.71 67.62 8.59 M096700600099 21.84 72.96 8.90 M096700600100 21.98 61.20 7.86 M096700600101 22.12 43.46 6.31 M096700600102 22.25 51.06 6.54 M096700600103 22.39 44.22 5.79 M096700600104 22.53 46.97 5.75 M096700600105 22.66 35.75 4.74 M096700600106 22.80 38.50 4.73 M096700600107 22.93 27.14 3.78 M096700600108 23.07 33.18 4.04 M096700600109 23.21 24.70 3.29 M096700600110 23.34 28.08 3.46 M096700600111 23.48 22.44 2.94 M096700600112 23.62 20.40 2.68 M096700600113 23.75 19.04 2.51 M096700600114 23.89 18.72 2.41 M096700600115 24.02 15.25 2.04 M096700600116 24.16 12.00 1.78 M096700600117 24.30 14.95 1.94 M096700600118 24.43 12.60 1.70 M096700600119 24.57 12.18 1.67 M096700600120 24.71 10.29 1.48 M096700600121 24.84 8.55 1.28 M096700600122 24.98 8.93 1.31 M096700600123 25.11 6.84 1.13 M096700600124 25.25 9.36 1.23 M096700600125 25.39 7.74 1.13 M096700600126 25.52 7.48 1.07 M096700600127 25.66 7.74 1.08 M096700600128 25.79 8.10 1.11 M096700600129 25.93 8.46 1.08 M096700600130 ENDDATA 104 0 M096700600131 ENDSUBENT 130 0 M096700699999 SUBENT M0967007 20050221 M096M096700700001 BIB 4 20 M096700700002 REACTION (40-ZR-92(G,2N)40-ZR-90,,SIG,,,EVAL) M096700700003 ANALYSIS The contribution of partial reaction (g,2n) cross M096700700004 section into the experimental total neutron yield M096700700005 reaction (g,xn) cross section obtained using M096700700006 quasimonoenergetic annihilation photons at Livermore M096700700007 (USA) was evaluated using specially theoretically M096700700008 calculated transitional multiplicity function - M096700700009 ratio M096700700010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M096700700011 by the way M096700700012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M096700700013 REL-REF (R,L0011011,B.L.Berman+,J,PR,162,1098,1967) M096700700014 Experimental data for the total neutron yield M096700700015 reaction (g,xn) cross section. M096700700016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M096700700017 Theoretical preequilibrium model of photonuclear M096700700018 reactions based on the Fermi gas densities. M096700700019 STATUS (TABLE) Data plotted in Fig. 9. M096700700020 (DEP,L0011011) M096700700021 The neutron yield reaction (g,xn) cross section. M096700700022 ENDBIB 20 0 M096700700023 NOCOMMON 0 0 M096700700024 DATA 3 30 M096700700025 EN DATA DATA-ERR M096700700026 MEV MB MB M096700700027 21.98 2.72 0.43 M096700700028 22.12 4.24 0.74 M096700700029 22.25 8.28 1.31 M096700700030 22.39 9.90 1.59 M096700700031 22.53 13.86 2.11 M096700700032 22.66 13.65 2.22 M096700700033 22.80 17.71 2.71 M096700700034 22.93 14.75 2.50 M096700700035 23.07 21.33 3.24 M096700700036 23.21 18.20 2.97 M096700700037 23.34 23.40 3.58 M096700700038 23.48 21.08 3.39 M096700700039 23.62 22.44 3.62 M096700700040 23.75 23.12 3.74 M096700700041 23.89 25.20 3.99 M096700700042 24.02 21.96 3.72 M096700700043 24.16 18.00 3.33 M096700700044 24.30 24.05 3.98 M096700700045 24.43 22.80 3.91 M096700700046 24.57 22.04 3.83 M096700700047 24.71 18.62 3.50 M096700700048 24.84 17.55 3.44 M096700700049 24.98 18.33 3.53 M096700700050 25.11 14.82 3.19 M096700700051 25.25 20.80 3.83 M096700700052 25.39 17.20 3.48 M096700700053 25.52 17.60 3.53 M096700700054 25.66 17.20 3.50 M096700700055 25.79 18.00 3.58 M096700700056 25.93 18.80 3.67 M096700700057 ENDDATA 32 0 M096700700058 ENDSUBENT 57 0 M096700799999 ENDENTRY 7 0 M096799999999