ENTRY M0973 20181224 M099M0973 0 1 SUBENT M0973001 20181224 M099M0973 1 1 BIB 9 31 M0973 1 2 TITLE The new photoneutron reaction cross section data for M0973 1 3 76,78,80,82Se. M0973 1 4 AUTHOR (V.V.Varlamov,A.I.Davydov,B.S.Ishkhanov) M0973 1 5 REFERENCE (J,YF,82,16,2019) M0973 1 6 #doi:10.1134/S0044002719010197 M0973 1 7 (J,PAN,82,13,2019) M0973 1 8 English translation of YF,82,16,2019. M0973 1 9 #doi:10.1134/S1063778819010186 M0973 1 10 INSTITUTE (4RUSMOS) M0973 1 11 INC-SOURCE (QMPH,ARAD) M0973 1 12 ANALYSIS The joint analysis of data for total (g,xn) and M0973 1 13 partial (g,n), (g,2n) and (g,3n) reactions obtained M0973 1 14 in various experiments was carried out. The new M0973 1 15 approach to analysis of systematic disagreements M0973 1 16 between data was proposed on the base of new M0973 1 17 criteria of systematic uncertainties presence - M0973 1 18 specially proposed transitional multiplicity M0973 1 19 functions M0973 1 20 Fi-theor = SIG(g,in)/SIG(g,xn). M0973 1 21 Using these functions calculated in the frame of M0973 1 22 combined photonuclear reaction model new reliable M0973 1 23 and free from problems of neutron multiplicity M0973 1 24 sorting data for photoneutron partial reactions M0973 1 25 cross sections M0973 1 26 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M0973 1 27 were evaluated using experimental neutron yield M0973 1 28 reaction cross sections SIG-exp(g,xn). M0973 1 29 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M0973 1 30 STATUS (APRVD) Approved by V.Varlamov. M0973 1 31 HISTORY (20181224C) Data were compiled at the Russia MSU SINP M0973 1 32 CDFE by V.Varlamov. M0973 1 33 ENDBIB 31 0 M0973 1 34 NOCOMMON 0 0 M0973 1 35 ENDSUBENT 34 0 M0973 199999 SUBENT M0973002 20180823 M099M0973 2 1 BIB 3 8 M0973 2 2 REACTION (34-SE-76(G,X)0-NN-1,UNW,SIG,,,EVAL) M0973 2 3 ANALYSIS The total neutron reaction cross section obtained as M0973 2 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0973 2 5 STATUS (DEP,M0973003) M0973 2 6 Evaluated (g,1n) reaction cross section. M0973 2 7 (DEP,M0973004) M0973 2 8 Evaluated (g,2n) reaction cross section. M0973 2 9 (TABLE) Data presented in Fig. 4. M0973 2 10 ENDBIB 8 0 M0973 2 11 NOCOMMON 0 0 M0973 2 12 DATA 3 57 M0973 2 13 EN DATA DATA-ERR M0973 2 14 MEV MB MB M0973 2 15 11.28 16.10 5.20 M0973 2 16 11.55 21.60 5.61 M0973 2 17 11.82 23.40 5.78 M0973 2 18 12.09 32.10 6.42 M0973 2 19 12.36 33.90 6.58 M0973 2 20 12.63 46.10 7.47 M0973 2 21 12.91 41.20 7.16 M0973 2 22 13.18 51.30 7.90 M0973 2 23 13.45 61.20 8.63 M0973 2 24 13.72 72.30 9.44 M0973 2 25 13.99 72.20 9.46 M0973 2 26 14.26 89.00 10.68 M0973 2 27 14.53 88.70 10.69 M0973 2 28 14.80 100.90 11.58 M0973 2 29 15.07 105.50 11.94 M0973 2 30 15.34 108.20 12.16 M0973 2 31 15.62 102.20 11.77 M0973 2 32 15.89 104.80 12.00 M0973 2 33 16.16 97.50 11.52 M0973 2 34 16.43 104.90 12.06 M0973 2 35 16.70 107.10 12.26 M0973 2 36 16.97 94.10 11.38 M0973 2 37 17.24 100.70 11.88 M0973 2 38 17.51 105.80 12.27 M0973 2 39 17.78 100.30 11.92 M0973 2 40 18.05 105.50 12.32 M0973 2 41 18.33 104.90 12.31 M0973 2 42 18.60 98.30 11.88 M0973 2 43 18.87 96.40 12.61 M0973 2 44 19.14 94.15 12.46 M0973 2 45 19.41 91.63 12.28 M0973 2 46 19.68 82.84 11.20 M0973 2 47 19.95 80.99 10.17 M0973 2 48 20.22 73.46 8.93 M0973 2 49 20.49 74.26 8.35 M0973 2 50 20.76 73.26 7.78 M0973 2 51 21.04 71.33 7.36 M0973 2 52 21.31 66.53 6.84 M0973 2 53 21.58 62.38 6.39 M0973 2 54 21.85 59.83 6.15 M0973 2 55 22.12 57.68 5.98 M0973 2 56 22.39 58.87 6.06 M0973 2 57 22.66 50.21 5.52 M0973 2 58 22.93 49.48 5.49 M0973 2 59 23.20 45.42 5.38 M0973 2 60 23.47 45.20 5.35 M0973 2 61 23.75 44.83 5.33 M0973 2 62 24.02 40.38 5.14 M0973 2 63 24.29 33.79 4.82 M0973 2 64 24.56 35.34 4.87 M0973 2 65 24.83 35.01 4.86 M0973 2 66 25.10 32.45 4.77 M0973 2 67 25.37 29.40 4.60 M0973 2 68 25.64 36.66 4.96 M0973 2 69 25.91 25.19 4.42 M0973 2 70 26.18 23.85 4.36 M0973 2 71 26.46 26.60 4.52 M0973 2 72 ENDDATA 59 0 M0973 2 73 ENDSUBENT 72 0 M0973 299999 SUBENT M0973003 20180823 M099M0973 3 1 BIB 4 23 M0973 3 2 REACTION ((34-SE-76(G,N)34-SE-75,,SIG,,,EVAL)+ M0973 3 3 (34-SE-76(G,N+P)33-AS-74,,SIG,,,EVAL)) M0973 3 4 ANALYSIS The contribution of partial reaction (g,n) cross M0973 3 5 section into the experimental total neutron yield M0973 3 6 reaction (g,xn) cross section obtained using M0973 3 7 quasimonoenergetic annihilation photons at Saclay M0973 3 8 was evaluated using specially theoretically M0973 3 9 calculated transitional multiplicity function - M0973 3 10 ratio M0973 3 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0973 3 12 by the way M0973 3 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0973 3 14 The neutron yield cross section was obtained at M0973 3 15 Saclay. M0973 3 16 REL-REF (R,L0043025,P.Carlos+,J,NP/A,258,365,1976) M0973 3 17 Experimental data for the total neutron yield M0973 3 18 reaction (g,xn) cross section. M0973 3 19 (E,,B.S.Ishkhanov+,J,YF,71,517,2008). M0973 3 20 Theoretical preequilibrium model of photonuclear M0973 3 21 reactions based on the Fermi gas densities. M0973 3 22 STATUS (DEP,L0016002) M0973 3 23 The neutron yield reaction (g,xn) cross section. M0973 3 24 (TABLE) Data presented in Fig. 4. M0973 3 25 ENDBIB 23 0 M0973 3 26 NOCOMMON 0 0 M0973 3 27 DATA 3 57 M0973 3 28 EN DATA DATA-ERR M0973 3 29 MEV MB MB M0973 3 30 11.28 16.10 5.20 M0973 3 31 11.55 21.60 5.61 M0973 3 32 11.82 23.40 5.78 M0973 3 33 12.09 32.10 6.42 M0973 3 34 12.36 33.90 6.58 M0973 3 35 12.63 46.10 7.47 M0973 3 36 12.91 41.20 7.16 M0973 3 37 13.18 51.30 7.90 M0973 3 38 13.45 61.20 8.63 M0973 3 39 13.72 72.30 9.44 M0973 3 40 13.99 72.20 9.46 M0973 3 41 14.26 89.00 10.68 M0973 3 42 14.53 88.70 10.69 M0973 3 43 14.80 100.90 11.58 M0973 3 44 15.07 105.50 11.94 M0973 3 45 15.34 108.20 12.16 M0973 3 46 15.62 102.20 11.77 M0973 3 47 15.89 104.80 12.00 M0973 3 48 16.16 97.50 11.52 M0973 3 49 16.43 104.90 12.06 M0973 3 50 16.70 107.10 12.26 M0973 3 51 16.97 94.10 11.38 M0973 3 52 17.24 100.70 11.88 M0973 3 53 17.51 105.80 12.27 M0973 3 54 17.78 100.30 11.92 M0973 3 55 18.05 105.50 12.32 M0973 3 56 18.33 104.90 12.31 M0973 3 57 18.60 98.30 11.88 M0973 3 58 18.87 96.40 12.61 M0973 3 59 19.14 94.15 12.46 M0973 3 60 19.41 91.63 12.28 M0973 3 61 19.68 80.22 11.19 M0973 3 62 19.95 73.71 10.12 M0973 3 63 20.22 62.84 8.80 M0973 3 64 20.49 59.22 8.09 M0973 3 65 20.76 53.98 7.33 M0973 3 66 21.04 48.50 6.66 M0973 3 67 21.31 42.50 5.95 M0973 3 68 21.58 37.06 5.28 M0973 3 69 21.85 33.93 4.89 M0973 3 70 22.12 30.59 4.48 M0973 3 71 22.39 29.44 4.28 M0973 3 72 22.66 24.71 3.84 M0973 3 73 22.93 22.34 3.49 M0973 3 74 23.20 20.19 3.36 M0973 3 75 23.47 18.53 3.05 M0973 3 76 23.75 18.80 3.04 M0973 3 77 24.02 15.89 2.72 M0973 3 78 24.29 13.63 2.55 M0973 3 79 24.56 13.55 2.41 M0973 3 80 24.83 13.78 2.42 M0973 3 81 25.10 12.77 2.37 M0973 3 82 25.37 11.57 2.22 M0973 3 83 25.64 14.05 2.30 M0973 3 84 25.91 9.91 2.07 M0973 3 85 26.18 9.38 1.99 M0973 3 86 26.46 10.46 2.06 M0973 3 87 ENDDATA 59 0 M0973 3 88 ENDSUBENT 87 0 M0973 399999 SUBENT M0973004 20180823 M099M0973 4 1 BIB 4 22 M0973 4 2 REACTION (34-SE-76(G,2N)34-SE-74,,SIG,,,EVAL) M0973 4 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0973 4 4 section into the experimental total neutron yield M0973 4 5 reaction (g,xn) cross section obtained using M0973 4 6 quasimonoenergetic annihilation photons at Saclay M0973 4 7 was evaluated using specially theoretically M0973 4 8 calculated transitional multiplicity function - M0973 4 9 ratio M0973 4 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0973 4 11 by the way M0973 4 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0973 4 13 The neutron yield cross section was obtained at M0973 4 14 Saclay. M0973 4 15 REL-REF (R,L0043025,P.Carlos+,J,NP/A,258,365,1976) M0973 4 16 Experimental data for the total neutron yield M0973 4 17 reaction (g,xn) cross section. M0973 4 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0973 4 19 Theoretical preequilibrium model of photonuclear M0973 4 20 reactions based on the Fermi gas densities. M0973 4 21 STATUS (DEP,L0016002) M0973 4 22 The neutron yield reaction (g,xn) cross section. M0973 4 23 (TABLE) Data presented in Fig. 4. M0973 4 24 ENDBIB 22 0 M0973 4 25 NOCOMMON 0 0 M0973 4 26 DATA 3 26 M0973 4 27 EN DATA DATA-ERR M0973 4 28 MEV MB MB M0973 4 29 19.68 2.62 0.36 M0973 4 30 19.95 7.28 1.00 M0973 4 31 20.22 10.62 1.49 M0973 4 32 20.49 15.04 2.05 M0973 4 33 20.76 19.28 2.62 M0973 4 34 21.04 22.82 3.13 M0973 4 35 21.31 24.02 3.36 M0973 4 36 21.58 25.31 3.60 M0973 4 37 21.85 25.90 3.73 M0973 4 38 22.12 27.09 3.97 M0973 4 39 22.39 29.44 4.28 M0973 4 40 22.66 25.50 3.97 M0973 4 41 22.93 27.13 4.24 M0973 4 42 23.20 25.24 4.20 M0973 4 43 23.47 26.68 4.39 M0973 4 44 23.75 26.03 4.38 M0973 4 45 24.02 24.49 4.37 M0973 4 46 24.29 20.17 4.09 M0973 4 47 24.56 21.79 4.23 M0973 4 48 24.83 21.24 4.22 M0973 4 49 25.10 19.68 4.13 M0973 4 50 25.37 17.83 4.03 M0973 4 51 25.64 22.61 4.39 M0973 4 52 25.91 15.28 3.91 M0973 4 53 26.18 14.47 3.88 M0973 4 54 26.46 16.13 4.02 M0973 4 55 ENDDATA 28 0 M0973 4 56 ENDSUBENT 55 0 M0973 499999 SUBENT M0973005 20181224 M099M0973 5 1 BIB 3 8 M0973 5 2 REACTION (34-SE-78(G,X)0-NN-1,UNW,SIG,,,EVAL) M0973 5 3 ANALYSIS The total neutron reaction cross section obtained as M0973 5 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0973 5 5 STATUS (DEP,M0973006) M0973 5 6 Evaluated (g,1n) reaction cross section. M0973 5 7 (DEP,M0973007) M0973 5 8 Evaluated (g,2n) reaction cross section. M0973 5 9 (TABLE) Data presentrd in Fig. 5. M0973 5 10 ENDBIB 8 0 M0973 5 11 NOCOMMON 0 0 M0973 5 12 DATA 3 61 M0973 5 13 EN DATA DATA-ERR M0973 5 14 MEV MB MB M0973 5 15 10.20 6.30 4.47 M0973 5 16 10.47 6.90 4.55 M0973 5 17 10.74 21.20 5.58 M0973 5 18 11.01 22.50 5.71 M0973 5 19 11.28 21.20 5.64 M0973 5 20 11.55 28.70 6.21 M0973 5 21 11.82 34.30 6.63 M0973 5 22 12.09 34.20 6.65 M0973 5 23 12.36 39.80 7.09 M0973 5 24 12.63 50.00 7.83 M0973 5 25 12.91 56.10 8.29 M0973 5 26 13.18 56.30 8.33 M0973 5 27 13.45 61.20 8.71 M0973 5 28 13.72 69.30 9.31 M0973 5 29 13.99 81.90 10.22 M0973 5 30 14.26 84.90 10.47 M0973 5 31 14.53 101.60 11.67 M0973 5 32 14.80 102.80 11.79 M0973 5 33 15.07 111.80 12.45 M0973 5 34 15.34 121.80 13.19 M0973 5 35 15.62 126.30 13.53 M0973 5 36 15.89 124.00 13.40 M0973 5 37 16.16 109.60 12.42 M0973 5 38 16.43 120.30 13.21 M0973 5 39 16.70 117.70 13.06 M0973 5 40 16.97 115.70 12.95 M0973 5 41 17.24 116.60 13.05 M0973 5 42 17.51 116.40 13.50 M0973 5 43 17.78 105.24 12.72 M0973 5 44 18.05 101.82 12.36 M0973 5 45 18.33 96.72 11.29 M0973 5 46 18.60 103.75 10.77 M0973 5 47 18.87 93.89 9.28 M0973 5 48 19.14 89.09 8.19 M0973 5 49 19.41 91.62 7.82 M0973 5 50 19.68 74.48 6.67 M0973 5 51 19.95 74.91 6.50 M0973 5 52 20.22 80.99 6.76 M0973 5 53 20.49 71.69 6.29 M0973 5 54 20.76 67.77 6.11 M0973 5 55 21.04 61.26 5.84 M0973 5 56 21.31 59.71 5.83 M0973 5 57 21.58 58.59 5.86 M0973 5 58 21.85 54.35 5.66 M0973 5 59 22.12 52.49 5.59 M0973 5 60 22.39 57.01 5.86 M0973 5 61 22.66 49.53 5.49 M0973 5 62 22.93 40.66 5.05 M0973 5 63 23.20 45.41 5.33 M0973 5 64 23.47 41.64 5.17 M0973 5 65 23.75 42.86 5.26 M0973 5 66 24.02 38.02 5.02 M0973 5 67 24.29 35.68 4.93 M0973 5 68 24.56 33.57 4.84 M0973 5 69 24.83 35.23 5.02 M0973 5 70 25.10 34.26 5.00 M0973 5 71 25.37 29.29 4.73 M0973 5 72 25.64 29.52 4.78 M0973 5 73 25.91 25.54 4.58 M0973 5 74 26.18 24.97 4.58 M0973 5 75 26.46 23.60 4.54 M0973 5 76 ENDDATA 63 0 M0973 5 77 ENDSUBENT 76 0 M0973 599999 SUBENT M0973006 20181224 M099M0973 6 1 BIB 4 23 M0973 6 2 REACTION ((34-SE-78(G,N)34-SE-77,,SIG,,,EVAL)+ M0973 6 3 (34-SE-78(G,N+P)33-AS-76,,SIG,,,EVAL)) M0973 6 4 ANALYSIS The contribution of partial reaction (g,n) cross M0973 6 5 section into the experimental total neutron yield M0973 6 6 reaction (g,xn) cross section obtained using M0973 6 7 quasimonoenergetic annihilation photons at Saclay M0973 6 8 was evaluated using specially theoretically M0973 6 9 calculated transitional multiplicity function - M0973 6 10 ratio M0973 6 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0973 6 12 by the way M0973 6 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0973 6 14 The neutron yield cross section was obtained at M0973 6 15 Saclay. M0973 6 16 REL-REF (R,L0043028,P.Carlos+,J,NP/A,258,365,1976) M0973 6 17 Experimental data for the total neutron yield M0973 6 18 reaction (g,xn) cross section. M0973 6 19 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0973 6 20 Theoretical preequilibrium model of photonuclear M0973 6 21 reactions based on the Fermi gas densities. M0973 6 22 STATUS (DEP,L0012010) M0973 6 23 The neutron yield reaction (g,xn) cross section. M0973 6 24 (TABLE) Data presented in Fig. 5. M0973 6 25 ENDBIB 23 0 M0973 6 26 NOCOMMON 0 0 M0973 6 27 DATA 3 61 M0973 6 28 EN DATA DATA-ERR M0973 6 29 MEV MB MB M0973 6 30 10.20 6.30 4.47 M0973 6 31 10.47 6.90 4.55 M0973 6 32 10.74 21.20 5.58 M0973 6 33 11.01 22.50 5.71 M0973 6 34 11.28 21.20 5.64 M0973 6 35 11.55 28.70 6.21 M0973 6 36 11.82 34.30 6.63 M0973 6 37 12.09 34.20 6.65 M0973 6 38 12.36 39.80 7.09 M0973 6 39 12.63 50.00 7.83 M0973 6 40 12.91 56.10 8.29 M0973 6 41 13.18 56.30 8.33 M0973 6 42 13.45 61.20 8.71 M0973 6 43 13.72 69.30 9.31 M0973 6 44 13.99 81.90 10.22 M0973 6 45 14.26 84.90 10.47 M0973 6 46 14.53 101.60 11.67 M0973 6 47 14.80 102.80 11.79 M0973 6 48 15.07 111.80 12.45 M0973 6 49 15.34 121.80 13.19 M0973 6 50 15.62 126.30 13.53 M0973 6 51 15.89 124.00 13.40 M0973 6 52 16.16 109.60 12.42 M0973 6 53 16.43 120.30 13.21 M0973 6 54 16.70 117.70 13.06 M0973 6 55 16.97 115.70 12.95 M0973 6 56 17.24 116.60 13.05 M0973 6 57 17.51 116.40 13.50 M0973 6 58 17.78 105.24 12.72 M0973 6 59 18.05 100.78 12.36 M0973 6 60 18.33 91.52 11.27 M0973 6 61 18.60 90.78 10.66 M0973 6 62 18.87 75.57 9.02 M0973 6 63 19.14 63.64 7.60 M0973 6 64 19.41 58.99 6.84 M0973 6 65 19.68 43.62 5.44 M0973 6 66 19.95 39.13 4.80 M0973 6 67 20.22 38.63 4.55 M0973 6 68 20.49 30.73 3.78 M0973 6 69 20.76 26.66 3.33 M0973 6 70 21.04 22.46 2.93 M0973 6 71 21.31 20.24 2.66 M0973 6 72 21.58 18.87 2.51 M0973 6 73 21.85 16.87 2.32 M0973 6 74 22.12 16.29 2.30 M0973 6 75 22.39 17.69 2.40 M0973 6 76 22.66 15.37 2.25 M0973 6 77 22.93 12.62 2.07 M0973 6 78 23.20 14.09 2.19 M0973 6 79 23.47 12.92 2.12 M0973 6 80 23.75 13.30 2.16 M0973 6 81 24.02 11.34 1.97 M0973 6 82 24.29 10.64 1.93 M0973 6 83 24.56 10.01 1.89 M0973 6 84 24.83 9.89 1.82 M0973 6 85 25.10 9.62 1.82 M0973 6 86 25.37 8.59 1.72 M0973 6 87 25.64 8.65 1.74 M0973 6 88 25.91 7.17 1.58 M0973 6 89 26.18 7.01 1.58 M0973 6 90 26.46 6.62 1.56 M0973 6 91 ENDDATA 63 0 M0973 6 92 ENDSUBENT 91 0 M0973 699999 SUBENT M0973007 20181224 M099M0973 7 1 BIB 4 22 M0973 7 2 REACTION (34-SE-78(G,2N)34-SE-76,,SIG,,,EVAL) M0973 7 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0973 7 4 section into the experimental total neutron yield M0973 7 5 reaction (g,xn) cross section obtained using M0973 7 6 quasimonoenergetic annihilation photons at Saclay M0973 7 7 was evaluated using specially theoretically M0973 7 8 calculated transitional multiplicity function - M0973 7 9 ratio M0973 7 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0973 7 11 by the way M0973 7 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0973 7 13 The neutron yield cross section was obtained at M0973 7 14 Saclay. M0973 7 15 REL-REF (R,L0043028,P.Carlos+,J,NP/A,258,365,1976) M0973 7 16 Experimental data for the total neutron yield M0973 7 17 reaction (g,xn) cross section. M0973 7 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0973 7 19 Theoretical preequilibrium model of photonuclear M0973 7 20 reactions based on the Fermi gas densities. M0973 7 21 STATUS (DEP,L0012010) M0973 7 22 The neutron yield reaction (g,xn) cross section. M0973 7 23 (TABLE) Data presented in Fig. 5. M0973 7 24 ENDBIB 22 0 M0973 7 25 NOCOMMON 0 0 M0973 7 26 DATA 3 26 M0973 7 27 EN DATA DATA-ERR M0973 7 28 MEV MB MB M0973 7 29 19.68 2.62 0.36 M0973 7 30 19.95 7.28 1.00 M0973 7 31 20.22 10.62 1.49 M0973 7 32 20.49 15.04 2.05 M0973 7 33 20.76 19.28 2.62 M0973 7 34 21.04 22.82 3.13 M0973 7 35 21.31 24.02 3.36 M0973 7 36 21.58 25.31 3.60 M0973 7 37 21.85 25.90 3.73 M0973 7 38 22.12 27.09 3.97 M0973 7 39 22.39 29.44 4.28 M0973 7 40 22.66 25.50 3.97 M0973 7 41 22.93 27.13 4.24 M0973 7 42 23.20 25.24 4.20 M0973 7 43 23.47 26.68 4.39 M0973 7 44 23.75 26.03 4.38 M0973 7 45 24.02 24.49 4.37 M0973 7 46 24.29 20.17 4.09 M0973 7 47 24.56 21.79 4.23 M0973 7 48 24.83 21.24 4.22 M0973 7 49 25.10 19.68 4.13 M0973 7 50 25.37 17.83 4.03 M0973 7 51 25.64 22.61 4.39 M0973 7 52 25.91 15.28 3.91 M0973 7 53 26.18 14.47 3.88 M0973 7 54 26.46 16.13 4.02 M0973 7 55 ENDDATA 28 0 M0973 7 56 ENDSUBENT 55 0 M0973 799999 SUBENT M0973008 20181224 M099M0973 8 1 BIB 3 8 M0973 8 2 REACTION (34-SE-82(G,X)0-NN-1,UNW,SIG,,,EVAL) M0973 8 3 ANALYSIS The total neutron reaction cross section obtained as M0973 8 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0973 8 5 STATUS (DEP,M0973009) M0973 8 6 Evaluated (g,1n) reaction cross section. M0973 8 7 (DEP,M0973010) M0973 8 8 Evaluated (g,2n) reaction cross section. M0973 8 9 (TABLE) Data presented in Fig. 6. M0973 8 10 ENDBIB 8 0 M0973 8 11 NOCOMMON 0 0 M0973 8 12 DATA 3 65 M0973 8 13 EN DATA DATA-ERR M0973 8 14 MEV MB MB M0973 8 15 9.11 5.80 4.41 M0973 8 16 9.38 20.20 5.46 M0973 8 17 9.65 19.60 5.46 M0973 8 18 9.92 18.10 5.41 M0973 8 19 10.20 23.30 5.82 M0973 8 20 10.47 18.40 5.53 M0973 8 21 10.74 23.80 5.95 M0973 8 22 11.01 21.50 5.84 M0973 8 23 11.28 24.70 6.11 M0973 8 24 11.55 20.10 5.83 M0973 8 25 11.82 32.70 6.76 M0973 8 26 12.09 35.80 7.03 M0973 8 27 12.36 34.60 6.98 M0973 8 28 12.63 30.60 6.75 M0973 8 29 12.91 43.00 7.67 M0973 8 30 13.18 48.60 8.10 M0973 8 31 13.45 54.50 8.57 M0973 8 32 13.72 64.80 9.34 M0973 8 33 13.99 69.40 9.70 M0973 8 34 14.26 81.40 10.59 M0973 8 35 14.53 94.90 11.58 M0973 8 36 14.80 107.40 12.50 M0973 8 37 15.07 112.60 12.91 M0973 8 38 15.34 123.70 13.74 M0973 8 39 15.62 138.80 16.23 M0973 8 40 15.89 145.23 16.66 M0973 8 41 16.16 145.73 16.55 M0973 8 42 16.43 153.92 16.26 M0973 8 43 16.70 140.18 13.74 M0973 8 44 16.97 139.44 12.37 M0973 8 45 17.24 132.90 10.93 M0973 8 46 17.51 121.59 9.72 M0973 8 47 17.78 122.14 9.41 M0973 8 48 18.05 122.18 9.20 M0973 8 49 18.33 109.80 8.58 M0973 8 50 18.60 103.70 8.37 M0973 8 51 18.87 94.05 7.94 M0973 8 52 19.14 83.52 7.49 M0973 8 53 19.41 81.57 7.50 M0973 8 54 19.68 77.29 7.39 M0973 8 55 19.95 75.54 7.33 M0973 8 56 20.22 64.74 6.85 M0973 8 57 20.49 70.56 7.20 M0973 8 58 20.76 63.03 6.82 M0973 8 59 21.04 54.32 6.44 M0973 8 60 21.31 55.94 6.56 M0973 8 61 21.58 49.73 6.23 M0973 8 62 21.85 54.56 6.54 M0973 8 63 22.12 49.06 6.25 M0973 8 64 22.39 43.12 5.94 M0973 8 65 22.66 44.17 6.02 M0973 8 66 22.93 39.00 5.75 M0973 8 67 23.20 42.57 5.98 M0973 8 68 23.47 36.74 5.67 M0973 8 69 23.75 36.91 5.70 M0973 8 70 24.02 38.23 5.80 M0973 8 71 24.29 32.73 5.52 M0973 8 72 24.56 32.07 5.50 M0973 8 73 24.83 33.99 5.63 M0973 8 74 25.10 34.32 5.67 M0973 8 75 25.37 26.84 5.27 M0973 8 76 25.64 22.22 5.03 M0973 8 77 25.91 22.03 5.04 M0973 8 78 26.18 21.23 5.10 M0973 8 79 26.46 20.02 5.06 M0973 8 80 ENDDATA 67 0 M0973 8 81 ENDSUBENT 80 0 M0973 899999 SUBENT M0973009 20181224 M099M0973 9 1 BIB 4 23 M0973 9 2 REACTION ((34-SE-82(G,N)34-SE-81,,SIG,,,EVAL)+ M0973 9 3 (34-SE-82(G,N+P)33-AS-80,,SIG,,,EVAL)) M0973 9 4 ANALYSIS The contribution of partial reaction (g,n) cross M0973 9 5 section into the experimental total neutron yield M0973 9 6 reaction (g,xn) cross section obtained using M0973 9 7 quasimonoenergetic annihilation photons at Saclay M0973 9 8 was evaluated using specially theoretically M0973 9 9 calculated transitional multiplicity function - M0973 9 10 ratio M0973 9 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0973 9 12 by the way M0973 9 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0973 9 14 The neutron yield cross section was obtained at M0973 9 15 Saclay. M0973 9 16 REL-REF (R,L0043035,P.Carlos+,J,NP/A,258,365,1976) M0973 9 17 Experimental data for the total neutron yield M0973 9 18 reaction (g,xn) cross section. M0973 9 19 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0973 9 20 Theoretical preequilibrium model of photonuclear M0973 9 21 reactions based on the Fermi gas densities. M0973 9 22 STATUS (DEP,L0012010) M0973 9 23 The neutron yield reaction (g,xn) cross section. M0973 9 24 (TABLE) Data presentede in Fig. 6. M0973 9 25 ENDBIB 23 0 M0973 9 26 NOCOMMON 0 0 M0973 9 27 DATA 3 65 M0973 9 28 EN DATA DATA-ERR M0973 9 29 MEV MB MB M0973 9 30 9.11 5.80 4.41 M0973 9 31 9.38 20.20 5.46 M0973 9 32 9.65 19.61 5.46 M0973 9 33 9.92 18.10 5.41 M0973 9 34 10.2 23.32 5.82 M0973 9 35 10.47 18.40 5.53 M0973 9 36 10.74 23.81 5.95 M0973 9 37 11.01 21.50 5.84 M0973 9 38 11.28 24.70 6.11 M0973 9 39 11.55 20.10 5.83 M0973 9 40 11.82 32.72 6.76 M0973 9 41 12.09 35.82 7.03 M0973 9 42 12.36 34.61 6.98 M0973 9 43 12.63 30.61 6.75 M0973 9 44 12.91 43.01 7.67 M0973 9 45 13.18 48.6 8.1 M0973 9 46 13.45 54.50 8.57 M0973 9 47 13.72 64.80 9.34 M0973 9 48 13.99 69.4 9.7 M0973 9 49 14.26 81.20 10.59 M0973 9 50 14.53 94.92 11.58 M0973 9 51 14.8 107.4 12.5 M0973 9 52 15.07 112.61 12.91 M0973 9 53 15.34 123.70 13.74 M0973 9 54 15.62 138.80 16.23 M0973 9 55 15.89 145.23 16.66 M0973 9 56 16.16 145.73 16.55 M0973 9 57 16.43 147.30 16.25 M0973 9 58 16.7 122.25 13.59 M0973 9 59 16.97 109.81 11.95 M0973 9 60 17.24 92.14 10.00 M0973 9 61 17.51 76.43 8.37 M0973 9 62 17.78 69.27 7.48 M0973 9 63 18.05 61.09 6.51 M0973 9 64 18.33 47.82 5.24 M0973 9 65 18.6 40.80 4.56 M0973 9 66 18.87 33.47 3.84 M0973 9 67 19.14 27.36 3.28 M0973 9 68 19.41 24.33 2.93 M0973 9 69 19.68 21.70 2.69 M0973 9 70 19.95 20.24 2.52 M0973 9 71 20.22 16.18 2.17 M0973 9 72 20.49 17.64 2.28 M0973 9 73 20.76 14.9 2.02 M0973 9 74 21.04 12.61 1.86 M0973 9 75 21.31 12.99 1.90 M0973 9 76 21.58 11.54 1.80 M0973 9 77 21.85 11.90 1.76 M0973 9 78 22.12 10.70 1.68 M0973 9 79 22.39 9.41 1.60 M0973 9 80 22.66 9.64 1.62 M0973 9 81 22.93 8.51 1.54 M0973 9 82 23.2 9.29 1.61 M0973 9 83 23.47 8.02 1.52 M0973 9 84 23.75 8.05 1.53 M0973 9 85 24.02 8.34 1.56 M0973 9 86 24.29 7.14 1.48 M0973 9 87 24.56 7.00 1.48 M0973 9 88 24.83 7.42 1.51 M0973 9 89 25.1 7.49 1.52 M0973 9 90 25.37 5.86 1.42 M0973 9 91 25.64 4.85 1.35 M0973 9 92 25.91 4.49 1.25 M0973 9 93 26.18 4.25 1.24 M0973 9 94 26.46 4.00 1.23 M0973 9 95 ENDDATA 67 0 M0973 9 96 ENDSUBENT 95 0 M0973 999999 SUBENT M0973010 20181224 M099M0973 10 1 BIB 4 22 M0973 10 2 REACTION (34-SE-82(G,2N)34-SE-80,,SIG,,,EVAL) M0973 10 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0973 10 4 section into the experimental total neutron yield M0973 10 5 reaction (g,xn) cross section obtained using M0973 10 6 quasimonoenergetic annihilation photons at Saclay M0973 10 7 was evaluated using specially theoretically M0973 10 8 calculated transitional multiplicity function - M0973 10 9 ratio M0973 10 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0973 10 11 by the way M0973 10 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0973 10 13 The neutron yield cross section was obtained at M0973 10 14 Saclay. M0973 10 15 REL-REF (R,L0043035,P.Carlos+,J,NP/A,258,365,1976) M0973 10 16 Experimental data for the total neutron yield M0973 10 17 reaction (g,xn) cross section. M0973 10 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0973 10 19 Theoretical preequilibrium model of photonuclear M0973 10 20 reactions based on the Fermi gas densities. M0973 10 21 STATUS (DEP,L0012010) M0973 10 22 The neutron yield reaction (g,xn) cross section. M0973 10 23 (TABLE) Data presentred in Fig. 6. M0973 10 24 ENDBIB 22 0 M0973 10 25 NOCOMMON 0 0 M0973 10 26 DATA 3 26 M0973 10 27 EN DATA DATA-ERR M0973 10 28 MEV MB MB M0973 10 29 19.68 2.62 0.36 M0973 10 30 19.95 7.28 1.00 M0973 10 31 20.22 10.62 1.49 M0973 10 32 20.49 15.04 2.05 M0973 10 33 20.76 19.28 2.62 M0973 10 34 21.04 22.82 3.13 M0973 10 35 21.31 24.02 3.36 M0973 10 36 21.58 25.31 3.60 M0973 10 37 21.85 25.90 3.73 M0973 10 38 22.12 27.09 3.97 M0973 10 39 22.39 29.44 4.28 M0973 10 40 22.66 25.50 3.97 M0973 10 41 22.93 27.13 4.24 M0973 10 42 23.20 25.24 4.20 M0973 10 43 23.47 26.68 4.39 M0973 10 44 23.75 26.03 4.38 M0973 10 45 24.02 24.49 4.37 M0973 10 46 24.29 20.17 4.09 M0973 10 47 24.56 21.79 4.23 M0973 10 48 24.83 21.24 4.22 M0973 10 49 25.10 19.68 4.13 M0973 10 50 25.37 17.83 4.03 M0973 10 51 25.64 22.61 4.39 M0973 10 52 25.91 15.28 3.91 M0973 10 53 26.18 14.47 3.88 M0973 10 54 26.46 16.13 4.02 M0973 10 55 ENDDATA 28 0 M0973 10 56 ENDSUBENT 55 0 M0973 1099999 SUBENT M0973011 20181224 M099M0973 11 1 BIB 3 4 M0973 11 2 REACTION (34-SE-76(G,X)0-NN-1,UNW,INT,,,EVAL) M0973 11 3 ANALYSIS Integration of evaluated cross section. M0973 11 4 STATUS (DEP,M0973002) Evaluated cross section. M0973 11 5 (TABLE) Data presented in Table 1. M0973 11 6 ENDBIB 4 0 M0973 11 7 NOCOMMON 0 0 M0973 11 8 DATA 3 29 M0973 11 9 EN-MAX DATA DATA-ERR M0973 11 10 MEV MB*MEV MB*MEV M0973 11 11 19.18 632.5 10.9 M0973 11 12 26.46 1022.9 12.8 M0973 11 13 ENDDATA 4 0 M0973 11 14 ENDSUBENT 13 0 M0973 1199999 SUBENT M0973012 20181224 M099M0973 12 1 BIB 3 5 M0973 12 2 REACTION ((34-SE-76(G,N)34-SE-75,,INT,,,EVAL)+ M0973 12 3 (34-SE-76(G,N+P)33-AS-74,,INT,,,EVAL)) M0973 12 4 ANALYSIS Integration of evaluated cross section. M0973 12 5 STATUS (DEP,M0973003) Evaluated cross section. M0973 12 6 (TABLE) Data presented in Table 1. M0973 12 7 ENDBIB 5 0 M0973 12 8 NOCOMMON 0 0 M0973 12 9 DATA 3 29 M0973 12 10 EN-MAX DATA DATA-ERR M0973 12 11 MEV MB*MEV MB*MEV M0973 12 12 19.18 632.5 10.9 M0973 12 13 26.46 880.4 12.3 M0973 12 14 ENDDATA 4 0 M0973 12 15 ENDSUBENT 14 0 M0973 1299999 SUBENT M0973013 20181224 M099M0973 13 1 BIB 3 4 M0973 13 2 REACTION (34-SE-76(G,2N)34-SE-74,,INT,,,EVAL) M0973 13 3 ANALYSIS Integration of evaluated cross section. M0973 13 4 STATUS (DEP,M0973004) Evaluated cross section. M0973 13 5 (TABLE) Data presented in Table 1. M0973 13 6 ENDBIB 4 0 M0973 13 7 NOCOMMON 0 0 M0973 13 8 DATA 3 19 M0973 13 9 EN-MAX DATA DATA-ERR M0973 13 10 MEV MB*MEV MB*MEV M0973 13 11 26.46 142.5 3.6 M0973 13 12 ENDDATA 3 0 M0973 13 13 ENDSUBENT 12 0 M0973 1399999 SUBENT M0973014 20181224 M099M0973 14 1 BIB 3 4 M0973 14 2 REACTION (34-SE-78(G,X)0-NN-1,UNW,INT,,,EVAL) M0973 14 3 ANALYSIS Integration of evaluated cross section. M0973 14 4 STATUS (DEP,M0973005) Evaluated cross section. M0973 14 5 (TABLE) Data presented in Table 1. M0973 14 6 ENDBIB 4 0 M0973 14 7 NOCOMMON 0 0 M0973 14 8 DATA 3 29 M0973 14 9 EN-MAX DATA DATA-ERR M0973 14 10 MEV MB*MEV MB*MEV M0973 14 11 17.92 586.3 10.5 M0973 14 12 26.46 1076.7 12.7 M0973 14 13 ENDDATA 4 0 M0973 14 14 ENDSUBENT 13 0 M0973 1499999 SUBENT M0973015 20181224 M099M0973 15 1 BIB 3 5 M0973 15 2 REACTION ((34-SE-78(G,N)34-SE-77,,INT,,,EVAL)+ M0973 15 3 (34-SE-78(G,N+P)33-AS-76,,INT,,,EVAL)) M0973 15 4 ANALYSIS Integration of evaluated cross section. M0973 15 5 STATUS (DEP,M0973006) Evaluated cross section. M0973 15 6 (TABLE) Data presented in Table 1. M0973 15 7 ENDBIB 5 0 M0973 15 8 NOCOMMON 0 0 M0973 15 9 DATA 3 29 M0973 15 10 EN-MAX DATA DATA-ERR M0973 15 11 MEV MB*MEV MB*MEV M0973 15 12 17.92 586.6 10.5 M0973 15 13 26.46 838.0 11.8 M0973 15 14 ENDDATA 4 0 M0973 15 15 ENDSUBENT 14 0 M0973 1599999 SUBENT M0973016 20181224 M099M0973 16 1 BIB 3 4 M0973 16 2 REACTION (34-SE-78(G,2N)34-SE-76,,INT,,,EVAL) M0973 16 3 ANALYSIS Integration of evaluated cross section. M0973 16 4 STATUS (DEP,M0973007) Evaluated cross section. M0973 16 5 (TABLE) Data presented in Table 1. M0973 16 6 ENDBIB 4 0 M0973 16 7 NOCOMMON 0 0 M0973 16 8 DATA 3 19 M0973 16 9 EN-MAX DATA DATA-ERR M0973 16 10 MEV MB*MEV MB*MEV M0973 16 11 26.46 238.8 4.7 M0973 16 12 ENDDATA 3 0 M0973 16 13 ENDSUBENT 12 0 M0973 1699999 SUBENT M0973017 20181224 M099M0973 17 1 BIB 3 4 M0973 17 2 REACTION (34-SE-82(G,X)0-NN-1,UNW,INT,,,EVAL) M0973 17 3 ANALYSIS Integration of evaluated cross section. M0973 17 4 STATUS (DEP,M0973008) Evaluated cross section. M0973 17 5 (TABLE) Data presented in Table 1. M0973 17 6 ENDBIB 4 0 M0973 17 7 NOCOMMON 0 0 M0973 17 8 DATA 3 29 M0973 17 9 EN-MAX DATA DATA-ERR M0973 17 10 MEV MB*MEV MB*MEV M0973 17 11 15.98 363.2 8.7 M0973 17 12 26.46 1190.1 13.1 M0973 17 13 ENDDATA 4 0 M0973 17 14 ENDSUBENT 13 0 M0973 1799999 SUBENT M0973018 20181224 M099M0973 18 1 BIB 3 5 M0973 18 2 REACTION ((34-SE-82(G,N)34-SE-81,,INT,,,EVAL)+ M0973 18 3 (34-SE-82(G,N+P)33-AS-80,,INT,,,EVAL)) M0973 18 4 ANALYSIS Integration of evaluated cross section. M0973 18 5 STATUS (DEP,M0973009) Evaluated cross section. M0973 18 6 (TABLE) Data presented in Table 1. M0973 18 7 ENDBIB 5 0 M0973 18 8 NOCOMMON 0 0 M0973 18 9 DATA 3 29 M0973 18 10 EN-MAX DATA DATA-ERR M0973 18 11 MEV MB*MEV MB*MEV M0973 18 12 15.98 363.2 8.7 M0973 18 13 26.46 723.7 11.3 M0973 18 14 ENDDATA 4 0 M0973 18 15 ENDSUBENT 14 0 M0973 1899999 SUBENT M0973019 20181224 M099M0973 19 1 BIB 3 4 M0973 19 2 REACTION (34-SE-82(G,2N)34-SE-80,,INT,,,EVAL) M0973 19 3 ANALYSIS Integration of evaluated cross section. M0973 19 4 STATUS (DEP,M0973010) Evaluated cross section. M0973 19 5 (TABLE) Data presented in Table 1. M0973 19 6 ENDBIB 4 0 M0973 19 7 NOCOMMON 0 0 M0973 19 8 DATA 3 19 M0973 19 9 EN-MAX DATA DATA-ERR M0973 19 10 MEV MB*MEV MB*MEV M0973 19 11 26.46 385.4 6.7 M0973 19 12 ENDDATA 3 0 M0973 19 13 ENDSUBENT 12 0 M0973 1999999 ENDENTRY 19 0 M097399999999