ENTRY M0973 20181224 M099M097300000001 SUBENT M0973001 20181224 M099M097300100001 BIB 9 31 M097300100002 TITLE The new photoneutron reaction cross section data for M097300100003 76,78,80,82Se. M097300100004 AUTHOR (V.V.Varlamov,A.I.Davydov,B.S.Ishkhanov) M097300100005 REFERENCE (J,YF,82,16,2019) M097300100006 #doi:10.1134/S0044002719010197 M097300100007 (J,PAN,82,13,2019) M097300100008 English translation of YF,82,16,2019. M097300100009 #doi:10.1134/S1063778819010186 M097300100010 INSTITUTE (4RUSMOS) M097300100011 INC-SOURCE (QMPH,ARAD) M097300100012 ANALYSIS The joint analysis of data for total (g,xn) and M097300100013 partial (g,n), (g,2n) and (g,3n) reactions obtained M097300100014 in various experiments was carried out. The new M097300100015 approach to analysis of systematic disagreements M097300100016 between data was proposed on the base of new M097300100017 criteria of systematic uncertainties presence - M097300100018 specially proposed transitional multiplicity M097300100019 functions M097300100020 Fi-theor = SIG(g,in)/SIG(g,xn). M097300100021 Using these functions calculated in the frame of M097300100022 combined photonuclear reaction model new reliable M097300100023 and free from problems of neutron multiplicity M097300100024 sorting data for photoneutron partial reactions M097300100025 cross sections M097300100026 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M097300100027 were evaluated using experimental neutron yield M097300100028 reaction cross sections SIG-exp(g,xn). M097300100029 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M097300100030 STATUS (APRVD) Approved by V.Varlamov. M097300100031 HISTORY (20181224C) Data were compiled at the Russia MSU SINP M097300100032 CDFE by V.Varlamov. M097300100033 ENDBIB 31 0 M097300100034 NOCOMMON 0 0 M097300100035 ENDSUBENT 34 0 M097300199999 SUBENT M0973002 20180823 M099M097300200001 BIB 3 8 M097300200002 REACTION (34-SE-76(G,X)0-NN-1,UNW,SIG,,,EVAL) M097300200003 ANALYSIS The total neutron reaction cross section obtained as M097300200004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097300200005 STATUS (DEP,M0973003) M097300200006 Evaluated (g,1n) reaction cross section. M097300200007 (DEP,M0973004) M097300200008 Evaluated (g,2n) reaction cross section. M097300200009 (TABLE) Data presented in Fig. 4. M097300200010 ENDBIB 8 0 M097300200011 NOCOMMON 0 0 M097300200012 DATA 3 57 M097300200013 EN DATA DATA-ERR M097300200014 MEV MB MB M097300200015 11.28 16.10 5.20 M097300200016 11.55 21.60 5.61 M097300200017 11.82 23.40 5.78 M097300200018 12.09 32.10 6.42 M097300200019 12.36 33.90 6.58 M097300200020 12.63 46.10 7.47 M097300200021 12.91 41.20 7.16 M097300200022 13.18 51.30 7.90 M097300200023 13.45 61.20 8.63 M097300200024 13.72 72.30 9.44 M097300200025 13.99 72.20 9.46 M097300200026 14.26 89.00 10.68 M097300200027 14.53 88.70 10.69 M097300200028 14.80 100.90 11.58 M097300200029 15.07 105.50 11.94 M097300200030 15.34 108.20 12.16 M097300200031 15.62 102.20 11.77 M097300200032 15.89 104.80 12.00 M097300200033 16.16 97.50 11.52 M097300200034 16.43 104.90 12.06 M097300200035 16.70 107.10 12.26 M097300200036 16.97 94.10 11.38 M097300200037 17.24 100.70 11.88 M097300200038 17.51 105.80 12.27 M097300200039 17.78 100.30 11.92 M097300200040 18.05 105.50 12.32 M097300200041 18.33 104.90 12.31 M097300200042 18.60 98.30 11.88 M097300200043 18.87 96.40 12.61 M097300200044 19.14 94.15 12.46 M097300200045 19.41 91.63 12.28 M097300200046 19.68 82.84 11.20 M097300200047 19.95 80.99 10.17 M097300200048 20.22 73.46 8.93 M097300200049 20.49 74.26 8.35 M097300200050 20.76 73.26 7.78 M097300200051 21.04 71.33 7.36 M097300200052 21.31 66.53 6.84 M097300200053 21.58 62.38 6.39 M097300200054 21.85 59.83 6.15 M097300200055 22.12 57.68 5.98 M097300200056 22.39 58.87 6.06 M097300200057 22.66 50.21 5.52 M097300200058 22.93 49.48 5.49 M097300200059 23.20 45.42 5.38 M097300200060 23.47 45.20 5.35 M097300200061 23.75 44.83 5.33 M097300200062 24.02 40.38 5.14 M097300200063 24.29 33.79 4.82 M097300200064 24.56 35.34 4.87 M097300200065 24.83 35.01 4.86 M097300200066 25.10 32.45 4.77 M097300200067 25.37 29.40 4.60 M097300200068 25.64 36.66 4.96 M097300200069 25.91 25.19 4.42 M097300200070 26.18 23.85 4.36 M097300200071 26.46 26.60 4.52 M097300200072 ENDDATA 59 0 M097300200073 ENDSUBENT 72 0 M097300299999 SUBENT M0973003 20180823 M099M097300300001 BIB 4 23 M097300300002 REACTION ((34-SE-76(G,N)34-SE-75,,SIG,,,EVAL)+ M097300300003 (34-SE-76(G,N+P)33-AS-74,,SIG,,,EVAL)) M097300300004 ANALYSIS The contribution of partial reaction (g,n) cross M097300300005 section into the experimental total neutron yield M097300300006 reaction (g,xn) cross section obtained using M097300300007 quasimonoenergetic annihilation photons at Saclay M097300300008 was evaluated using specially theoretically M097300300009 calculated transitional multiplicity function - M097300300010 ratio M097300300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097300300012 by the way M097300300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097300300014 The neutron yield cross section was obtained at M097300300015 Saclay. M097300300016 REL-REF (R,L0043025,P.Carlos+,J,NP/A,258,365,1976) M097300300017 Experimental data for the total neutron yield M097300300018 reaction (g,xn) cross section. M097300300019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008). M097300300020 Theoretical preequilibrium model of photonuclear M097300300021 reactions based on the Fermi gas densities. M097300300022 STATUS (DEP,L0016002) M097300300023 The neutron yield reaction (g,xn) cross section. M097300300024 (TABLE) Data presented in Fig. 4. M097300300025 ENDBIB 23 0 M097300300026 NOCOMMON 0 0 M097300300027 DATA 3 57 M097300300028 EN DATA DATA-ERR M097300300029 MEV MB MB M097300300030 11.28 16.10 5.20 M097300300031 11.55 21.60 5.61 M097300300032 11.82 23.40 5.78 M097300300033 12.09 32.10 6.42 M097300300034 12.36 33.90 6.58 M097300300035 12.63 46.10 7.47 M097300300036 12.91 41.20 7.16 M097300300037 13.18 51.30 7.90 M097300300038 13.45 61.20 8.63 M097300300039 13.72 72.30 9.44 M097300300040 13.99 72.20 9.46 M097300300041 14.26 89.00 10.68 M097300300042 14.53 88.70 10.69 M097300300043 14.80 100.90 11.58 M097300300044 15.07 105.50 11.94 M097300300045 15.34 108.20 12.16 M097300300046 15.62 102.20 11.77 M097300300047 15.89 104.80 12.00 M097300300048 16.16 97.50 11.52 M097300300049 16.43 104.90 12.06 M097300300050 16.70 107.10 12.26 M097300300051 16.97 94.10 11.38 M097300300052 17.24 100.70 11.88 M097300300053 17.51 105.80 12.27 M097300300054 17.78 100.30 11.92 M097300300055 18.05 105.50 12.32 M097300300056 18.33 104.90 12.31 M097300300057 18.60 98.30 11.88 M097300300058 18.87 96.40 12.61 M097300300059 19.14 94.15 12.46 M097300300060 19.41 91.63 12.28 M097300300061 19.68 80.22 11.19 M097300300062 19.95 73.71 10.12 M097300300063 20.22 62.84 8.80 M097300300064 20.49 59.22 8.09 M097300300065 20.76 53.98 7.33 M097300300066 21.04 48.50 6.66 M097300300067 21.31 42.50 5.95 M097300300068 21.58 37.06 5.28 M097300300069 21.85 33.93 4.89 M097300300070 22.12 30.59 4.48 M097300300071 22.39 29.44 4.28 M097300300072 22.66 24.71 3.84 M097300300073 22.93 22.34 3.49 M097300300074 23.20 20.19 3.36 M097300300075 23.47 18.53 3.05 M097300300076 23.75 18.80 3.04 M097300300077 24.02 15.89 2.72 M097300300078 24.29 13.63 2.55 M097300300079 24.56 13.55 2.41 M097300300080 24.83 13.78 2.42 M097300300081 25.10 12.77 2.37 M097300300082 25.37 11.57 2.22 M097300300083 25.64 14.05 2.30 M097300300084 25.91 9.91 2.07 M097300300085 26.18 9.38 1.99 M097300300086 26.46 10.46 2.06 M097300300087 ENDDATA 59 0 M097300300088 ENDSUBENT 87 0 M097300399999 SUBENT M0973004 20180823 M099M097300400001 BIB 4 22 M097300400002 REACTION (34-SE-76(G,2N)34-SE-74,,SIG,,,EVAL) M097300400003 ANALYSIS The contribution of partial reaction (g,2n) cross M097300400004 section into the experimental total neutron yield M097300400005 reaction (g,xn) cross section obtained using M097300400006 quasimonoenergetic annihilation photons at Saclay M097300400007 was evaluated using specially theoretically M097300400008 calculated transitional multiplicity function - M097300400009 ratio M097300400010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097300400011 by the way M097300400012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097300400013 The neutron yield cross section was obtained at M097300400014 Saclay. M097300400015 REL-REF (R,L0043025,P.Carlos+,J,NP/A,258,365,1976) M097300400016 Experimental data for the total neutron yield M097300400017 reaction (g,xn) cross section. M097300400018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097300400019 Theoretical preequilibrium model of photonuclear M097300400020 reactions based on the Fermi gas densities. M097300400021 STATUS (DEP,L0016002) M097300400022 The neutron yield reaction (g,xn) cross section. M097300400023 (TABLE) Data presented in Fig. 4. M097300400024 ENDBIB 22 0 M097300400025 NOCOMMON 0 0 M097300400026 DATA 3 26 M097300400027 EN DATA DATA-ERR M097300400028 MEV MB MB M097300400029 19.68 2.62 0.36 M097300400030 19.95 7.28 1.00 M097300400031 20.22 10.62 1.49 M097300400032 20.49 15.04 2.05 M097300400033 20.76 19.28 2.62 M097300400034 21.04 22.82 3.13 M097300400035 21.31 24.02 3.36 M097300400036 21.58 25.31 3.60 M097300400037 21.85 25.90 3.73 M097300400038 22.12 27.09 3.97 M097300400039 22.39 29.44 4.28 M097300400040 22.66 25.50 3.97 M097300400041 22.93 27.13 4.24 M097300400042 23.20 25.24 4.20 M097300400043 23.47 26.68 4.39 M097300400044 23.75 26.03 4.38 M097300400045 24.02 24.49 4.37 M097300400046 24.29 20.17 4.09 M097300400047 24.56 21.79 4.23 M097300400048 24.83 21.24 4.22 M097300400049 25.10 19.68 4.13 M097300400050 25.37 17.83 4.03 M097300400051 25.64 22.61 4.39 M097300400052 25.91 15.28 3.91 M097300400053 26.18 14.47 3.88 M097300400054 26.46 16.13 4.02 M097300400055 ENDDATA 28 0 M097300400056 ENDSUBENT 55 0 M097300499999 SUBENT M0973005 20181224 M099M097300500001 BIB 3 8 M097300500002 REACTION (34-SE-78(G,X)0-NN-1,UNW,SIG,,,EVAL) M097300500003 ANALYSIS The total neutron reaction cross section obtained as M097300500004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097300500005 STATUS (DEP,M0973006) M097300500006 Evaluated (g,1n) reaction cross section. M097300500007 (DEP,M0973007) M097300500008 Evaluated (g,2n) reaction cross section. M097300500009 (TABLE) Data presentrd in Fig. 5. M097300500010 ENDBIB 8 0 M097300500011 NOCOMMON 0 0 M097300500012 DATA 3 61 M097300500013 EN DATA DATA-ERR M097300500014 MEV MB MB M097300500015 10.20 6.30 4.47 M097300500016 10.47 6.90 4.55 M097300500017 10.74 21.20 5.58 M097300500018 11.01 22.50 5.71 M097300500019 11.28 21.20 5.64 M097300500020 11.55 28.70 6.21 M097300500021 11.82 34.30 6.63 M097300500022 12.09 34.20 6.65 M097300500023 12.36 39.80 7.09 M097300500024 12.63 50.00 7.83 M097300500025 12.91 56.10 8.29 M097300500026 13.18 56.30 8.33 M097300500027 13.45 61.20 8.71 M097300500028 13.72 69.30 9.31 M097300500029 13.99 81.90 10.22 M097300500030 14.26 84.90 10.47 M097300500031 14.53 101.60 11.67 M097300500032 14.80 102.80 11.79 M097300500033 15.07 111.80 12.45 M097300500034 15.34 121.80 13.19 M097300500035 15.62 126.30 13.53 M097300500036 15.89 124.00 13.40 M097300500037 16.16 109.60 12.42 M097300500038 16.43 120.30 13.21 M097300500039 16.70 117.70 13.06 M097300500040 16.97 115.70 12.95 M097300500041 17.24 116.60 13.05 M097300500042 17.51 116.40 13.50 M097300500043 17.78 105.24 12.72 M097300500044 18.05 101.82 12.36 M097300500045 18.33 96.72 11.29 M097300500046 18.60 103.75 10.77 M097300500047 18.87 93.89 9.28 M097300500048 19.14 89.09 8.19 M097300500049 19.41 91.62 7.82 M097300500050 19.68 74.48 6.67 M097300500051 19.95 74.91 6.50 M097300500052 20.22 80.99 6.76 M097300500053 20.49 71.69 6.29 M097300500054 20.76 67.77 6.11 M097300500055 21.04 61.26 5.84 M097300500056 21.31 59.71 5.83 M097300500057 21.58 58.59 5.86 M097300500058 21.85 54.35 5.66 M097300500059 22.12 52.49 5.59 M097300500060 22.39 57.01 5.86 M097300500061 22.66 49.53 5.49 M097300500062 22.93 40.66 5.05 M097300500063 23.20 45.41 5.33 M097300500064 23.47 41.64 5.17 M097300500065 23.75 42.86 5.26 M097300500066 24.02 38.02 5.02 M097300500067 24.29 35.68 4.93 M097300500068 24.56 33.57 4.84 M097300500069 24.83 35.23 5.02 M097300500070 25.10 34.26 5.00 M097300500071 25.37 29.29 4.73 M097300500072 25.64 29.52 4.78 M097300500073 25.91 25.54 4.58 M097300500074 26.18 24.97 4.58 M097300500075 26.46 23.60 4.54 M097300500076 ENDDATA 63 0 M097300500077 ENDSUBENT 76 0 M097300599999 SUBENT M0973006 20181224 M099M097300600001 BIB 4 23 M097300600002 REACTION ((34-SE-78(G,N)34-SE-77,,SIG,,,EVAL)+ M097300600003 (34-SE-78(G,N+P)33-AS-76,,SIG,,,EVAL)) M097300600004 ANALYSIS The contribution of partial reaction (g,n) cross M097300600005 section into the experimental total neutron yield M097300600006 reaction (g,xn) cross section obtained using M097300600007 quasimonoenergetic annihilation photons at Saclay M097300600008 was evaluated using specially theoretically M097300600009 calculated transitional multiplicity function - M097300600010 ratio M097300600011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097300600012 by the way M097300600013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097300600014 The neutron yield cross section was obtained at M097300600015 Saclay. M097300600016 REL-REF (R,L0043028,P.Carlos+,J,NP/A,258,365,1976) M097300600017 Experimental data for the total neutron yield M097300600018 reaction (g,xn) cross section. M097300600019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097300600020 Theoretical preequilibrium model of photonuclear M097300600021 reactions based on the Fermi gas densities. M097300600022 STATUS (DEP,L0012010) M097300600023 The neutron yield reaction (g,xn) cross section. M097300600024 (TABLE) Data presented in Fig. 5. M097300600025 ENDBIB 23 0 M097300600026 NOCOMMON 0 0 M097300600027 DATA 3 61 M097300600028 EN DATA DATA-ERR M097300600029 MEV MB MB M097300600030 10.20 6.30 4.47 M097300600031 10.47 6.90 4.55 M097300600032 10.74 21.20 5.58 M097300600033 11.01 22.50 5.71 M097300600034 11.28 21.20 5.64 M097300600035 11.55 28.70 6.21 M097300600036 11.82 34.30 6.63 M097300600037 12.09 34.20 6.65 M097300600038 12.36 39.80 7.09 M097300600039 12.63 50.00 7.83 M097300600040 12.91 56.10 8.29 M097300600041 13.18 56.30 8.33 M097300600042 13.45 61.20 8.71 M097300600043 13.72 69.30 9.31 M097300600044 13.99 81.90 10.22 M097300600045 14.26 84.90 10.47 M097300600046 14.53 101.60 11.67 M097300600047 14.80 102.80 11.79 M097300600048 15.07 111.80 12.45 M097300600049 15.34 121.80 13.19 M097300600050 15.62 126.30 13.53 M097300600051 15.89 124.00 13.40 M097300600052 16.16 109.60 12.42 M097300600053 16.43 120.30 13.21 M097300600054 16.70 117.70 13.06 M097300600055 16.97 115.70 12.95 M097300600056 17.24 116.60 13.05 M097300600057 17.51 116.40 13.50 M097300600058 17.78 105.24 12.72 M097300600059 18.05 100.78 12.36 M097300600060 18.33 91.52 11.27 M097300600061 18.60 90.78 10.66 M097300600062 18.87 75.57 9.02 M097300600063 19.14 63.64 7.60 M097300600064 19.41 58.99 6.84 M097300600065 19.68 43.62 5.44 M097300600066 19.95 39.13 4.80 M097300600067 20.22 38.63 4.55 M097300600068 20.49 30.73 3.78 M097300600069 20.76 26.66 3.33 M097300600070 21.04 22.46 2.93 M097300600071 21.31 20.24 2.66 M097300600072 21.58 18.87 2.51 M097300600073 21.85 16.87 2.32 M097300600074 22.12 16.29 2.30 M097300600075 22.39 17.69 2.40 M097300600076 22.66 15.37 2.25 M097300600077 22.93 12.62 2.07 M097300600078 23.20 14.09 2.19 M097300600079 23.47 12.92 2.12 M097300600080 23.75 13.30 2.16 M097300600081 24.02 11.34 1.97 M097300600082 24.29 10.64 1.93 M097300600083 24.56 10.01 1.89 M097300600084 24.83 9.89 1.82 M097300600085 25.10 9.62 1.82 M097300600086 25.37 8.59 1.72 M097300600087 25.64 8.65 1.74 M097300600088 25.91 7.17 1.58 M097300600089 26.18 7.01 1.58 M097300600090 26.46 6.62 1.56 M097300600091 ENDDATA 63 0 M097300600092 ENDSUBENT 91 0 M097300699999 SUBENT M0973007 20181224 M099M097300700001 BIB 4 22 M097300700002 REACTION (34-SE-78(G,2N)34-SE-76,,SIG,,,EVAL) M097300700003 ANALYSIS The contribution of partial reaction (g,2n) cross M097300700004 section into the experimental total neutron yield M097300700005 reaction (g,xn) cross section obtained using M097300700006 quasimonoenergetic annihilation photons at Saclay M097300700007 was evaluated using specially theoretically M097300700008 calculated transitional multiplicity function - M097300700009 ratio M097300700010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097300700011 by the way M097300700012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097300700013 The neutron yield cross section was obtained at M097300700014 Saclay. M097300700015 REL-REF (R,L0043028,P.Carlos+,J,NP/A,258,365,1976) M097300700016 Experimental data for the total neutron yield M097300700017 reaction (g,xn) cross section. M097300700018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097300700019 Theoretical preequilibrium model of photonuclear M097300700020 reactions based on the Fermi gas densities. M097300700021 STATUS (DEP,L0012010) M097300700022 The neutron yield reaction (g,xn) cross section. M097300700023 (TABLE) Data presented in Fig. 5. M097300700024 ENDBIB 22 0 M097300700025 NOCOMMON 0 0 M097300700026 DATA 3 26 M097300700027 EN DATA DATA-ERR M097300700028 MEV MB MB M097300700029 19.68 2.62 0.36 M097300700030 19.95 7.28 1.00 M097300700031 20.22 10.62 1.49 M097300700032 20.49 15.04 2.05 M097300700033 20.76 19.28 2.62 M097300700034 21.04 22.82 3.13 M097300700035 21.31 24.02 3.36 M097300700036 21.58 25.31 3.60 M097300700037 21.85 25.90 3.73 M097300700038 22.12 27.09 3.97 M097300700039 22.39 29.44 4.28 M097300700040 22.66 25.50 3.97 M097300700041 22.93 27.13 4.24 M097300700042 23.20 25.24 4.20 M097300700043 23.47 26.68 4.39 M097300700044 23.75 26.03 4.38 M097300700045 24.02 24.49 4.37 M097300700046 24.29 20.17 4.09 M097300700047 24.56 21.79 4.23 M097300700048 24.83 21.24 4.22 M097300700049 25.10 19.68 4.13 M097300700050 25.37 17.83 4.03 M097300700051 25.64 22.61 4.39 M097300700052 25.91 15.28 3.91 M097300700053 26.18 14.47 3.88 M097300700054 26.46 16.13 4.02 M097300700055 ENDDATA 28 0 M097300700056 ENDSUBENT 55 0 M097300799999 SUBENT M0973008 20181224 M099M097300800001 BIB 3 8 M097300800002 REACTION (34-SE-82(G,X)0-NN-1,UNW,SIG,,,EVAL) M097300800003 ANALYSIS The total neutron reaction cross section obtained as M097300800004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097300800005 STATUS (DEP,M0973009) M097300800006 Evaluated (g,1n) reaction cross section. M097300800007 (DEP,M0973010) M097300800008 Evaluated (g,2n) reaction cross section. M097300800009 (TABLE) Data presented in Fig. 6. M097300800010 ENDBIB 8 0 M097300800011 NOCOMMON 0 0 M097300800012 DATA 3 65 M097300800013 EN DATA DATA-ERR M097300800014 MEV MB MB M097300800015 9.11 5.80 4.41 M097300800016 9.38 20.20 5.46 M097300800017 9.65 19.60 5.46 M097300800018 9.92 18.10 5.41 M097300800019 10.20 23.30 5.82 M097300800020 10.47 18.40 5.53 M097300800021 10.74 23.80 5.95 M097300800022 11.01 21.50 5.84 M097300800023 11.28 24.70 6.11 M097300800024 11.55 20.10 5.83 M097300800025 11.82 32.70 6.76 M097300800026 12.09 35.80 7.03 M097300800027 12.36 34.60 6.98 M097300800028 12.63 30.60 6.75 M097300800029 12.91 43.00 7.67 M097300800030 13.18 48.60 8.10 M097300800031 13.45 54.50 8.57 M097300800032 13.72 64.80 9.34 M097300800033 13.99 69.40 9.70 M097300800034 14.26 81.40 10.59 M097300800035 14.53 94.90 11.58 M097300800036 14.80 107.40 12.50 M097300800037 15.07 112.60 12.91 M097300800038 15.34 123.70 13.74 M097300800039 15.62 138.80 16.23 M097300800040 15.89 145.23 16.66 M097300800041 16.16 145.73 16.55 M097300800042 16.43 153.92 16.26 M097300800043 16.70 140.18 13.74 M097300800044 16.97 139.44 12.37 M097300800045 17.24 132.90 10.93 M097300800046 17.51 121.59 9.72 M097300800047 17.78 122.14 9.41 M097300800048 18.05 122.18 9.20 M097300800049 18.33 109.80 8.58 M097300800050 18.60 103.70 8.37 M097300800051 18.87 94.05 7.94 M097300800052 19.14 83.52 7.49 M097300800053 19.41 81.57 7.50 M097300800054 19.68 77.29 7.39 M097300800055 19.95 75.54 7.33 M097300800056 20.22 64.74 6.85 M097300800057 20.49 70.56 7.20 M097300800058 20.76 63.03 6.82 M097300800059 21.04 54.32 6.44 M097300800060 21.31 55.94 6.56 M097300800061 21.58 49.73 6.23 M097300800062 21.85 54.56 6.54 M097300800063 22.12 49.06 6.25 M097300800064 22.39 43.12 5.94 M097300800065 22.66 44.17 6.02 M097300800066 22.93 39.00 5.75 M097300800067 23.20 42.57 5.98 M097300800068 23.47 36.74 5.67 M097300800069 23.75 36.91 5.70 M097300800070 24.02 38.23 5.80 M097300800071 24.29 32.73 5.52 M097300800072 24.56 32.07 5.50 M097300800073 24.83 33.99 5.63 M097300800074 25.10 34.32 5.67 M097300800075 25.37 26.84 5.27 M097300800076 25.64 22.22 5.03 M097300800077 25.91 22.03 5.04 M097300800078 26.18 21.23 5.10 M097300800079 26.46 20.02 5.06 M097300800080 ENDDATA 67 0 M097300800081 ENDSUBENT 80 0 M097300899999 SUBENT M0973009 20181224 M099M097300900001 BIB 4 23 M097300900002 REACTION ((34-SE-82(G,N)34-SE-81,,SIG,,,EVAL)+ M097300900003 (34-SE-82(G,N+P)33-AS-80,,SIG,,,EVAL)) M097300900004 ANALYSIS The contribution of partial reaction (g,n) cross M097300900005 section into the experimental total neutron yield M097300900006 reaction (g,xn) cross section obtained using M097300900007 quasimonoenergetic annihilation photons at Saclay M097300900008 was evaluated using specially theoretically M097300900009 calculated transitional multiplicity function - M097300900010 ratio M097300900011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097300900012 by the way M097300900013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097300900014 The neutron yield cross section was obtained at M097300900015 Saclay. M097300900016 REL-REF (R,L0043035,P.Carlos+,J,NP/A,258,365,1976) M097300900017 Experimental data for the total neutron yield M097300900018 reaction (g,xn) cross section. M097300900019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097300900020 Theoretical preequilibrium model of photonuclear M097300900021 reactions based on the Fermi gas densities. M097300900022 STATUS (DEP,L0012010) M097300900023 The neutron yield reaction (g,xn) cross section. M097300900024 (TABLE) Data presentede in Fig. 6. M097300900025 ENDBIB 23 0 M097300900026 NOCOMMON 0 0 M097300900027 DATA 3 65 M097300900028 EN DATA DATA-ERR M097300900029 MEV MB MB M097300900030 9.11 5.80 4.41 M097300900031 9.38 20.20 5.46 M097300900032 9.65 19.61 5.46 M097300900033 9.92 18.10 5.41 M097300900034 10.2 23.32 5.82 M097300900035 10.47 18.40 5.53 M097300900036 10.74 23.81 5.95 M097300900037 11.01 21.50 5.84 M097300900038 11.28 24.70 6.11 M097300900039 11.55 20.10 5.83 M097300900040 11.82 32.72 6.76 M097300900041 12.09 35.82 7.03 M097300900042 12.36 34.61 6.98 M097300900043 12.63 30.61 6.75 M097300900044 12.91 43.01 7.67 M097300900045 13.18 48.6 8.1 M097300900046 13.45 54.50 8.57 M097300900047 13.72 64.80 9.34 M097300900048 13.99 69.4 9.7 M097300900049 14.26 81.20 10.59 M097300900050 14.53 94.92 11.58 M097300900051 14.8 107.4 12.5 M097300900052 15.07 112.61 12.91 M097300900053 15.34 123.70 13.74 M097300900054 15.62 138.80 16.23 M097300900055 15.89 145.23 16.66 M097300900056 16.16 145.73 16.55 M097300900057 16.43 147.30 16.25 M097300900058 16.7 122.25 13.59 M097300900059 16.97 109.81 11.95 M097300900060 17.24 92.14 10.00 M097300900061 17.51 76.43 8.37 M097300900062 17.78 69.27 7.48 M097300900063 18.05 61.09 6.51 M097300900064 18.33 47.82 5.24 M097300900065 18.6 40.80 4.56 M097300900066 18.87 33.47 3.84 M097300900067 19.14 27.36 3.28 M097300900068 19.41 24.33 2.93 M097300900069 19.68 21.70 2.69 M097300900070 19.95 20.24 2.52 M097300900071 20.22 16.18 2.17 M097300900072 20.49 17.64 2.28 M097300900073 20.76 14.9 2.02 M097300900074 21.04 12.61 1.86 M097300900075 21.31 12.99 1.90 M097300900076 21.58 11.54 1.80 M097300900077 21.85 11.90 1.76 M097300900078 22.12 10.70 1.68 M097300900079 22.39 9.41 1.60 M097300900080 22.66 9.64 1.62 M097300900081 22.93 8.51 1.54 M097300900082 23.2 9.29 1.61 M097300900083 23.47 8.02 1.52 M097300900084 23.75 8.05 1.53 M097300900085 24.02 8.34 1.56 M097300900086 24.29 7.14 1.48 M097300900087 24.56 7.00 1.48 M097300900088 24.83 7.42 1.51 M097300900089 25.1 7.49 1.52 M097300900090 25.37 5.86 1.42 M097300900091 25.64 4.85 1.35 M097300900092 25.91 4.49 1.25 M097300900093 26.18 4.25 1.24 M097300900094 26.46 4.00 1.23 M097300900095 ENDDATA 67 0 M097300900096 ENDSUBENT 95 0 M097300999999 SUBENT M0973010 20181224 M099M097301000001 BIB 4 22 M097301000002 REACTION (34-SE-82(G,2N)34-SE-80,,SIG,,,EVAL) M097301000003 ANALYSIS The contribution of partial reaction (g,2n) cross M097301000004 section into the experimental total neutron yield M097301000005 reaction (g,xn) cross section obtained using M097301000006 quasimonoenergetic annihilation photons at Saclay M097301000007 was evaluated using specially theoretically M097301000008 calculated transitional multiplicity function - M097301000009 ratio M097301000010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097301000011 by the way M097301000012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097301000013 The neutron yield cross section was obtained at M097301000014 Saclay. M097301000015 REL-REF (R,L0043035,P.Carlos+,J,NP/A,258,365,1976) M097301000016 Experimental data for the total neutron yield M097301000017 reaction (g,xn) cross section. M097301000018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097301000019 Theoretical preequilibrium model of photonuclear M097301000020 reactions based on the Fermi gas densities. M097301000021 STATUS (DEP,L0012010) M097301000022 The neutron yield reaction (g,xn) cross section. M097301000023 (TABLE) Data presentred in Fig. 6. M097301000024 ENDBIB 22 0 M097301000025 NOCOMMON 0 0 M097301000026 DATA 3 26 M097301000027 EN DATA DATA-ERR M097301000028 MEV MB MB M097301000029 19.68 2.62 0.36 M097301000030 19.95 7.28 1.00 M097301000031 20.22 10.62 1.49 M097301000032 20.49 15.04 2.05 M097301000033 20.76 19.28 2.62 M097301000034 21.04 22.82 3.13 M097301000035 21.31 24.02 3.36 M097301000036 21.58 25.31 3.60 M097301000037 21.85 25.90 3.73 M097301000038 22.12 27.09 3.97 M097301000039 22.39 29.44 4.28 M097301000040 22.66 25.50 3.97 M097301000041 22.93 27.13 4.24 M097301000042 23.20 25.24 4.20 M097301000043 23.47 26.68 4.39 M097301000044 23.75 26.03 4.38 M097301000045 24.02 24.49 4.37 M097301000046 24.29 20.17 4.09 M097301000047 24.56 21.79 4.23 M097301000048 24.83 21.24 4.22 M097301000049 25.10 19.68 4.13 M097301000050 25.37 17.83 4.03 M097301000051 25.64 22.61 4.39 M097301000052 25.91 15.28 3.91 M097301000053 26.18 14.47 3.88 M097301000054 26.46 16.13 4.02 M097301000055 ENDDATA 28 0 M097301000056 ENDSUBENT 55 0 M097301099999 SUBENT M0973011 20181224 M099M097301100001 BIB 3 4 M097301100002 REACTION (34-SE-76(G,X)0-NN-1,UNW,INT,,,EVAL) M097301100003 ANALYSIS Integration of evaluated cross section. M097301100004 STATUS (DEP,M0973002) Evaluated cross section. M097301100005 (TABLE) Data presented in Table 1. M097301100006 ENDBIB 4 0 M097301100007 NOCOMMON 0 0 M097301100008 DATA 3 29 M097301100009 EN-MAX DATA DATA-ERR M097301100010 MEV MB*MEV MB*MEV M097301100011 19.18 632.5 10.9 M097301100012 26.46 1022.9 12.8 M097301100013 ENDDATA 4 0 M097301100014 ENDSUBENT 13 0 M097301199999 SUBENT M0973012 20181224 M099M097301200001 BIB 3 5 M097301200002 REACTION ((34-SE-76(G,N)34-SE-75,,INT,,,EVAL)+ M097301200003 (34-SE-76(G,N+P)33-AS-74,,INT,,,EVAL)) M097301200004 ANALYSIS Integration of evaluated cross section. M097301200005 STATUS (DEP,M0973003) Evaluated cross section. M097301200006 (TABLE) Data presented in Table 1. M097301200007 ENDBIB 5 0 M097301200008 NOCOMMON 0 0 M097301200009 DATA 3 29 M097301200010 EN-MAX DATA DATA-ERR M097301200011 MEV MB*MEV MB*MEV M097301200012 19.18 632.5 10.9 M097301200013 26.46 880.4 12.3 M097301200014 ENDDATA 4 0 M097301200015 ENDSUBENT 14 0 M097301299999 SUBENT M0973013 20181224 M099M097301300001 BIB 3 4 M097301300002 REACTION (34-SE-76(G,2N)34-SE-74,,INT,,,EVAL) M097301300003 ANALYSIS Integration of evaluated cross section. M097301300004 STATUS (DEP,M0973004) Evaluated cross section. M097301300005 (TABLE) Data presented in Table 1. M097301300006 ENDBIB 4 0 M097301300007 NOCOMMON 0 0 M097301300008 DATA 3 19 M097301300009 EN-MAX DATA DATA-ERR M097301300010 MEV MB*MEV MB*MEV M097301300011 26.46 142.5 3.6 M097301300012 ENDDATA 3 0 M097301300013 ENDSUBENT 12 0 M097301399999 SUBENT M0973014 20181224 M099M097301400001 BIB 3 4 M097301400002 REACTION (34-SE-78(G,X)0-NN-1,UNW,INT,,,EVAL) M097301400003 ANALYSIS Integration of evaluated cross section. M097301400004 STATUS (DEP,M0973005) Evaluated cross section. M097301400005 (TABLE) Data presented in Table 1. M097301400006 ENDBIB 4 0 M097301400007 NOCOMMON 0 0 M097301400008 DATA 3 29 M097301400009 EN-MAX DATA DATA-ERR M097301400010 MEV MB*MEV MB*MEV M097301400011 17.92 586.3 10.5 M097301400012 26.46 1076.7 12.7 M097301400013 ENDDATA 4 0 M097301400014 ENDSUBENT 13 0 M097301499999 SUBENT M0973015 20181224 M099M097301500001 BIB 3 5 M097301500002 REACTION ((34-SE-78(G,N)34-SE-77,,INT,,,EVAL)+ M097301500003 (34-SE-78(G,N+P)33-AS-76,,INT,,,EVAL)) M097301500004 ANALYSIS Integration of evaluated cross section. M097301500005 STATUS (DEP,M0973006) Evaluated cross section. M097301500006 (TABLE) Data presented in Table 1. M097301500007 ENDBIB 5 0 M097301500008 NOCOMMON 0 0 M097301500009 DATA 3 29 M097301500010 EN-MAX DATA DATA-ERR M097301500011 MEV MB*MEV MB*MEV M097301500012 17.92 586.6 10.5 M097301500013 26.46 838.0 11.8 M097301500014 ENDDATA 4 0 M097301500015 ENDSUBENT 14 0 M097301599999 SUBENT M0973016 20181224 M099M097301600001 BIB 3 4 M097301600002 REACTION (34-SE-78(G,2N)34-SE-76,,INT,,,EVAL) M097301600003 ANALYSIS Integration of evaluated cross section. M097301600004 STATUS (DEP,M0973007) Evaluated cross section. M097301600005 (TABLE) Data presented in Table 1. M097301600006 ENDBIB 4 0 M097301600007 NOCOMMON 0 0 M097301600008 DATA 3 19 M097301600009 EN-MAX DATA DATA-ERR M097301600010 MEV MB*MEV MB*MEV M097301600011 26.46 238.8 4.7 M097301600012 ENDDATA 3 0 M097301600013 ENDSUBENT 12 0 M097301699999 SUBENT M0973017 20181224 M099M097301700001 BIB 3 4 M097301700002 REACTION (34-SE-82(G,X)0-NN-1,UNW,INT,,,EVAL) M097301700003 ANALYSIS Integration of evaluated cross section. M097301700004 STATUS (DEP,M0973008) Evaluated cross section. M097301700005 (TABLE) Data presented in Table 1. M097301700006 ENDBIB 4 0 M097301700007 NOCOMMON 0 0 M097301700008 DATA 3 29 M097301700009 EN-MAX DATA DATA-ERR M097301700010 MEV MB*MEV MB*MEV M097301700011 15.98 363.2 8.7 M097301700012 26.46 1190.1 13.1 M097301700013 ENDDATA 4 0 M097301700014 ENDSUBENT 13 0 M097301799999 SUBENT M0973018 20181224 M099M097301800001 BIB 3 5 M097301800002 REACTION ((34-SE-82(G,N)34-SE-81,,INT,,,EVAL)+ M097301800003 (34-SE-82(G,N+P)33-AS-80,,INT,,,EVAL)) M097301800004 ANALYSIS Integration of evaluated cross section. M097301800005 STATUS (DEP,M0973009) Evaluated cross section. M097301800006 (TABLE) Data presented in Table 1. M097301800007 ENDBIB 5 0 M097301800008 NOCOMMON 0 0 M097301800009 DATA 3 29 M097301800010 EN-MAX DATA DATA-ERR M097301800011 MEV MB*MEV MB*MEV M097301800012 15.98 363.2 8.7 M097301800013 26.46 723.7 11.3 M097301800014 ENDDATA 4 0 M097301800015 ENDSUBENT 14 0 M097301899999 SUBENT M0973019 20181224 M099M097301900001 BIB 3 4 M097301900002 REACTION (34-SE-82(G,2N)34-SE-80,,INT,,,EVAL) M097301900003 ANALYSIS Integration of evaluated cross section. M097301900004 STATUS (DEP,M0973010) Evaluated cross section. M097301900005 (TABLE) Data presented in Table 1. M097301900006 ENDBIB 4 0 M097301900007 NOCOMMON 0 0 M097301900008 DATA 3 19 M097301900009 EN-MAX DATA DATA-ERR M097301900010 MEV MB*MEV MB*MEV M097301900011 26.46 385.4 6.7 M097301900012 ENDDATA 3 0 M097301900013 ENDSUBENT 12 0 M097301999999 ENDENTRY 19 0 M097399999999