ENTRY M0972 20180923 M098M0972 0 1 SUBENT M0972001 20180823 M098M0972 1 1 BIB 9 27 M0972 1 2 TITLE Comparison of partial photoneutron reaction cross M0972 1 3 sections reliability for 140,142Ce. M0972 1 4 AUTHOR (V.V.Varlamov,V.A.Barbaryan,N.N.Peskov) M0972 1 5 REFERENCE (C,2017ALMATY,,26,2017) M0972 1 6 INSTITUTE (4RUSMOS) M0972 1 7 INC-SOURCE (QMPH,ARAD) M0972 1 8 ANALYSIS The joint analysis of data for total (g,xn) and M0972 1 9 partial (g,n), (g,2n) and (g,3n) reactions obtained M0972 1 10 in various experiments was carried out. The new M0972 1 11 approach to analysis of systematic disagreements M0972 1 12 between data was proposed on the base of new M0972 1 13 criteria of systematic uncertainties presence - M0972 1 14 specially proposed transitional multiplicity M0972 1 15 functions M0972 1 16 Fi-theor = SIG(g,in)/SIG(g,xn). M0972 1 17 Using these functions calculated in the frame of M0972 1 18 combined photonuclear reaction model new reliable M0972 1 19 and free from problems of neutron multiplicity M0972 1 20 sorting data for photoneutron partial reactions M0972 1 21 cross sections M0972 1 22 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M0972 1 23 were evaluated using experimental neutron yield M0972 1 24 reaction cross sections SIG-exp(g,xn). M0972 1 25 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M0972 1 26 STATUS (APRVD) Approved by V.Varlamov. M0972 1 27 HISTORY (20180823C) Data were compiled at the Russia MSU SINP M0972 1 28 CDFE by V.Varlamov. M0972 1 29 ENDBIB 27 0 M0972 1 30 NOCOMMON 0 0 M0972 1 31 ENDSUBENT 30 0 M0972 199999 SUBENT M0972002 20180823 M098M0972 2 1 BIB 3 8 M0972 2 2 REACTION (58-CE-140(G,X)0-NN-1,UNW,SIG,,,EVAL) M0972 2 3 ANALYSIS The total neutron reaction cross section obtained as M0972 2 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0972 2 5 STATUS (TABLE) M0972 2 6 (DEP,M0972003) M0972 2 7 Evaluated (g,1n) reaction cross section. M0972 2 8 (DEP,M0972004) M0972 2 9 Evaluated (g,2n) reaction cross section. M0972 2 10 ENDBIB 8 0 M0972 2 11 NOCOMMON 0 0 M0972 2 12 DATA 3 43 M0972 2 13 EN DATA DATA-ERR M0972 2 14 MEV MB MB M0972 2 15 9.40 49.79 4.98 M0972 2 16 9.80 52.47 5.25 M0972 2 17 10.20 55.42 5.54 M0972 2 18 10.60 64.55 6.46 M0972 2 19 11.00 73.40 7.34 M0972 2 20 11.40 96.16 9.62 M0972 2 21 12.00 113.86 11.39 M0972 2 22 12.20 136.19 13.62 M0972 2 23 12.60 154.94 15.49 M0972 2 24 13.00 196.52 19.65 M0972 2 25 13.40 237.26 23.73 M0972 2 26 13.80 279.82 27.98 M0972 2 27 14.20 329.48 32.95 M0972 2 28 14.60 358.91 35.89 M0972 2 29 15.00 389.39 38.94 M0972 2 30 15.40 380.40 38.04 M0972 2 31 15.80 345.28 34.53 M0972 2 32 16.20 300.12 30.01 M0972 2 33 16.60 272.24 27.22 M0972 2 34 17.00 228.77 22.88 M0972 2 35 17.40 187.62 18.76 M0972 2 36 17.80 161.98 16.20 M0972 2 37 18.20 130.75 13.07 M0972 2 38 18.60 120.51 12.05 M0972 2 39 19.00 109.87 10.99 M0972 2 40 19.40 97.10 9.71 M0972 2 41 20.00 90.10 9.01 M0972 2 42 20.20 92.88 9.29 M0972 2 43 20.60 89.01 8.90 M0972 2 44 21.00 82.03 8.20 M0972 2 45 21.40 77.93 7.79 M0972 2 46 21.80 73.31 7.33 M0972 2 47 22.20 68.46 6.85 M0972 2 48 22.60 70.00 7.00 M0972 2 49 23.00 60.24 6.02 M0972 2 50 23.40 53.13 5.31 M0972 2 51 23.80 51.64 5.16 M0972 2 52 24.20 53.66 5.37 M0972 2 53 24.60 44.48 4.45 M0972 2 54 25.00 52.23 5.22 M0972 2 55 25.40 46.37 4.36 M0972 2 56 25.80 44.70 4.42 M0972 2 57 26.20 48.14 4.81 M0972 2 58 ENDDATA 45 0 M0972 2 59 ENDSUBENT 58 0 M0972 299999 SUBENT M0972003 20180823 M098M0972 3 1 BIB 4 23 M0972 3 2 REACTION ((58-CE-140(G,N)58-CE-139,,SIG,,,EVAL)+ M0972 3 3 (58-CE-140(G,N+P)57-LA-138,,SIG,,,EVAL)) M0972 3 4 ANALYSIS The contribution of partial reaction (g,n) cross M0972 3 5 section into the experimental total neutron yield M0972 3 6 reaction (g,xn) cross section obtained using M0972 3 7 quasimonoenergetic annihilation photons at Saclay M0972 3 8 was evaluated using specially theoretically M0972 3 9 calculated transitional multiplicity function - M0972 3 10 ratio M0972 3 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0972 3 12 by the way M0972 3 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0972 3 14 The neutron yield cross section was obtained at M0972 3 15 Saclay by Beil. M0972 3 16 REL-REF (R,L0042016,A.Lepretre+,J,NP/A,258,350,1976) M0972 3 17 Experimental data for the total neutron yield M0972 3 18 reaction (g,xn) cross section. M0972 3 19 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0972 3 20 Theoretical preequilibrium model of photonuclear M0972 3 21 reactions based on the Fermi gas densities. M0972 3 22 STATUS (TABLE) M0972 3 23 (DEP,L0042016) M0972 3 24 The neutron yield reaction (g,xn) cross section. M0972 3 25 ENDBIB 23 0 M0972 3 26 NOCOMMON 0 0 M0972 3 27 DATA 3 43 M0972 3 28 EN DATA DATA-ERR M0972 3 29 MEV MB MB M0972 3 30 9.4 49.79 8.85 M0972 3 31 9.8 52.47 9.33 M0972 3 32 10.2 55.42 9.85 M0972 3 33 10.6 64.55 11.48 M0972 3 34 11.0 73.40 13.05 M0972 3 35 11.4 96.16 17.10 M0972 3 36 11.8 113.86 20.24 M0972 3 37 12.2 136.19 24.21 M0972 3 38 12.6 154.94 27.55 M0972 3 39 13.0 196.52 34.94 M0972 3 40 13.4 237.26 42.18 M0972 3 41 13.8 279.82 49.75 M0972 3 42 14.2 329.48 58.57 M0972 3 43 14.6 358.90 63.81 M0972 3 44 15.0 389.39 69.23 M0972 3 45 15.4 380.40 67.63 M0972 3 46 15.8 345.28 61.38 M0972 3 47 16.2 300.12 53.36 M0972 3 48 16.6 272.24 48.40 M0972 3 49 17.0 222.82 39.55 M0972 3 50 17.4 157.13 27.69 M0972 3 51 17.8 110.13 19.29 M0972 3 52 18.2 70.99 12.38 M0972 3 53 18.6 53.63 9.32 M0972 3 54 19.0 41.92 7.28 M0972 3 55 19.4 33.55 5.82 M0972 3 56 19.8 29.43 5.10 M0972 3 57 20.2 30.51 5.29 M0972 3 58 20.6 30.22 5.24 M0972 3 59 21.0 29.06 5.04 M0972 3 60 21.4 27.99 4.85 M0972 3 61 21.8 25.65 4.43 M0972 3 62 22.2 22.71 3.90 M0972 3 63 22.6 21.95 3.75 M0972 3 64 23.0 17.98 3.06 M0972 3 65 23.4 15.12 2.57 M0972 3 66 23.8 14.27 2.42 M0972 3 67 24.2 14.54 2.46 M0972 3 68 24.6 11.92 2.01 M0972 3 69 25.0 13.82 2.33 M0972 3 70 25.4 11.42 1.93 M0972 3 71 25.8 12.90 2.07 M0972 3 72 26.2 13.67 2.10 M0972 3 73 ENDDATA 45 0 M0972 3 74 ENDSUBENT 73 0 M0972 399999 SUBENT M0972004 20180823 M098M0972 4 1 BIB 4 22 M0972 4 2 REACTION (58-CE-140(G,2N)58-CE-138,,SIG,,,EVAL) M0972 4 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0972 4 4 section into the experimental total neutron yield M0972 4 5 reaction (g,xn) cross section obtained using M0972 4 6 quasimonoenergetic annihilation photons at Saclay M0972 4 7 was evaluated using specially theoretically M0972 4 8 calculated transitional multiplicity function - M0972 4 9 ratio M0972 4 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0972 4 11 by the way M0972 4 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0972 4 13 The neutron yield cross section was obtained at M0972 4 14 Saclay by Beil. M0972 4 15 REL-REF (R,L0042016,A.Lepretre+,J,NP/A,258,350,1976) M0972 4 16 Experimental data for the total neutron yield M0972 4 17 reaction (g,xn) cross section. M0972 4 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0972 4 19 Theoretical preequilibrium model of photonuclear M0972 4 20 reactions based on the Fermi gas densities. M0972 4 21 STATUS (TABLE) M0972 4 22 (DEP,L0025016) M0972 4 23 The neutron yield reaction (g,xn) cross section. M0972 4 24 ENDBIB 22 0 M0972 4 25 NOCOMMON 0 0 M0972 4 26 DATA 3 24 M0972 4 27 EN DATA DATA-ERR M0972 4 28 MEV MB MB M0972 4 29 17.0 5.99 1.04 M0972 4 30 17.4 30.65 5.33 M0972 4 31 17.8 52.04 9.04 M0972 4 32 18.2 59.92 10.40 M0972 4 33 18.6 67.02 11.62 M0972 4 34 19.0 68.06 11.80 M0972 4 35 19.4 63.65 11.03 M0972 4 36 19.8 60.76 10.53 M0972 4 37 20.2 62.46 10.83 M0972 4 38 20.6 58.89 10.21 M0972 4 39 21.0 53.07 9.21 M0972 4 40 21.4 50.09 8.70 M0972 4 41 21.8 47.89 8.32 M0972 4 42 22.2 46.06 8.02 M0972 4 43 22.6 48.48 8.45 M0972 4 44 23.0 42.70 7.45 M0972 4 45 23.4 38.45 6.71 M0972 4 46 23.8 37.82 6.60 M0972 4 47 24.2 39.61 6.92 M0972 4 48 24.6 32.99 5.76 M0972 4 49 25.0 38.92 6.80 M0972 4 50 25.4 32.64 5.71 M0972 4 51 25.8 36.18 6.38 M0972 4 52 26.2 38.15 6.7 M0972 4 53 ENDDATA 26 0 M0972 4 54 ENDSUBENT 53 0 M0972 499999 SUBENT M0972005 20180823 M098M0972 5 1 BIB 3 8 M0972 5 2 REACTION (58-CE-142(G,X)0-NN-1,UNW,SIG,,,EVAL) M0972 5 3 ANALYSIS The total neutron reaction cross section obtained as M0972 5 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0972 5 5 STATUS (TABLE) M0972 5 6 (DEP,M0972006) M0972 5 7 Evaluated (g,1n) reaction cross section. M0972 5 8 (DEP,M0972007) M0972 5 9 Evaluated (g,2n) reaction cross section. M0972 5 10 ENDBIB 8 0 M0972 5 11 NOCOMMON 0 0 M0972 5 12 DATA 3 59 M0972 5 13 EN DATA DATA-ERR M0972 5 14 MEV MB MB M0972 5 15 7.76 27.80 6.61 M0972 5 16 8.03 39.40 7.22 M0972 5 17 8.30 37.80 7.18 M0972 5 18 8.57 29.90 6.85 M0972 5 19 8.84 43.00 7.55 M0972 5 20 9.11 39.70 7.41 M0972 5 21 9.38 51.60 8.15 M0972 5 22 9.65 44.10 7.74 M0972 5 23 9.92 64.80 9.11 M0972 5 24 10.20 64.60 9.14 M0972 5 25 10.47 80.90 10.39 M0972 5 26 10.74 75.50 10.01 M0972 5 27 11.01 97.10 11.75 M0972 5 28 11.28 93.70 11.50 M0972 5 29 11.55 110.40 12.92 M0972 5 30 11.82 128.50 14.53 M0972 5 31 12.09 135.20 16.69 M0972 5 32 12.36 165.80 19.33 M0972 5 33 12.63 185.50 21.12 M0972 5 34 12.91 222.32 23.61 M0972 5 35 13.18 238.32 22.94 M0972 5 36 13.45 253.05 21.69 M0972 5 37 13.72 292.07 22.66 M0972 5 38 13.99 299.18 22.05 M0972 5 39 14.26 313.90 22.79 M0972 5 40 14.53 339.01 24.69 M0972 5 41 14.80 344.23 25.39 M0972 5 42 15.07 331.38 24.99 M0972 5 43 15.34 326.51 25.05 M0972 5 44 15.62 321.79 25.29 M0972 5 45 15.89 292.44 23.60 M0972 5 46 16.16 274.12 22.66 M0972 5 47 16.43 240.35 20.59 M0972 5 48 16.70 216.98 19.08 M0972 5 49 16.97 209.83 8.53 M0972 5 50 17.24 184.36 16.74 M0972 5 51 17.51 163.08 15.35 M0972 5 52 17.78 148.28 14.22 M0972 5 53 18.05 138.24 13.47 M0972 5 54 18.33 118.35 12.14 M0972 5 55 18.60 112.57 11.75 M0972 5 56 18.87 109.87 11.59 M0972 5 57 19.14 104.81 11.17 M0972 5 58 19.41 93.37 10.43 M0972 5 59 19.68 86.78 10.05 M0972 5 60 19.95 84.89 9.98 M0972 5 61 20.22 74.14 9.37 M0972 5 62 20.49 78.68 9.53 M0972 5 63 20.76 76.79 9.47 M0972 5 64 21.04 68.92 9.06 M0972 5 65 21.31 70.35 9.20 M0972 5 66 21.58 52.80 8.26 M0972 5 67 21.85 65.35 9.04 M0972 5 68 22.12 55.38 8.64 M0972 5 69 22.39 71.34 9.49 M0972 5 70 22.66 32.89 7.93 M0972 5 71 22.93 66.06 9.34 M0972 5 72 23.20 69.47 9.57 M0972 5 73 23.47 45.82 8.58 M0972 5 74 ENDDATA 61 0 M0972 5 75 ENDSUBENT 74 0 M0972 599999 SUBENT M0972006 20180823 M098M0972 6 1 BIB 4 21 M0972 6 2 REACTION ((58-CE-142(G,N)58-CE-141,,SIG,,,EVAL)+ M0972 6 3 (58-CE-142(G,N+P)57-LA-140,,SIG,,,EVAL)) M0972 6 4 ANALYSIS The contribution of partial reaction (g,n) cross M0972 6 5 section into the experimental total neutron yield M0972 6 6 reaction (g,xn) cross section obtained using M0972 6 7 quasimonoenergetic annihilation photons at Saclay M0972 6 8 was evaluated using specially theoretically M0972 6 9 calculated transitional multiplicity function - M0972 6 10 ratio M0972 6 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0972 6 12 by the way M0972 6 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0972 6 14 The neutron yield cross section was obtained at M0972 6 15 Saclay by Beil. M0972 6 16 REL-REF (R,L0042019,A.Lepretre+,J,NP/A,258,350,1976) M0972 6 17 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0972 6 18 Theoretical preequilibrium model of photonuclear M0972 6 19 reactions based on the Fermi gas densities. M0972 6 20 STATUS (TABLE) M0972 6 21 (DEP,L0025019) M0972 6 22 The neutron yield reaction (g,xn) cross section. M0972 6 23 ENDBIB 21 0 M0972 6 24 NOCOMMON 0 0 M0972 6 25 DATA 3 59 M0972 6 26 EN DATA DATA-ERR M0972 6 27 MEV MB MB M0972 6 28 7.76 27.80 6.61 M0972 6 29 8.03 39.40 7.22 M0972 6 30 8.30 37.80 7.18 M0972 6 31 8.57 29.90 6.85 M0972 6 32 8.84 43.00 7.55 M0972 6 33 9.11 39.70 7.41 M0972 6 34 9.38 51.60 8.15 M0972 6 35 9.65 44.10 7.74 M0972 6 36 9.92 64.80 9.11 M0972 6 37 10.20 64.60 9.14 M0972 6 38 10.47 80.90 10.39 M0972 6 39 10.74 75.50 10.01 M0972 6 40 11.01 97.10 11.75 M0972 6 41 11.28 93.70 11.50 M0972 6 42 11.55 110.40 12.92 M0972 6 43 11.82 128.50 14.53 M0972 6 44 12.09 135.20 16.69 M0972 6 45 12.36 165.80 19.33 M0972 6 46 12.63 185.50 21.12 M0972 6 47 12.91 215.45 23.60 M0972 6 48 13.18 211.84 22.76 M0972 6 49 13.45 197.50 20.88 M0972 6 50 13.72 195.99 20.35 M0972 6 51 13.99 170.96 17.64 M0972 6 52 14.26 156.95 16.11 M0972 6 53 14.53 148.32 15.16 M0972 6 54 14.80 136.60 13.95 M0972 6 55 15.07 115.98 11.85 M0972 6 56 15.34 105.15 10.75 M0972 6 57 15.62 92.72 9.49 M0972 6 58 15.89 75.63 7.77 M0972 6 59 16.16 63.63 6.56 M0972 6 60 16.43 48.07 4.99 M0972 6 61 16.70 39.45 4.14 M0972 6 62 16.97 38.15 4.02 M0972 6 63 17.24 30.73 3.28 M0972 6 64 17.51 24.16 2.63 M0972 6 65 17.78 21.97 2.44 M0972 6 66 18.05 20.48 2.31 M0972 6 67 18.33 15.63 1.82 M0972 6 68 18.60 14.87 1.77 M0972 6 69 18.87 14.51 1.74 M0972 6 70 19.14 15.53 1.91 M0972 6 71 19.41 13.83 1.79 M0972 6 72 19.68 12.86 1.72 M0972 6 73 19.95 12.58 1.71 M0972 6 74 20.22 10.98 1.61 M0972 6 75 20.49 13.11 1.87 M0972 6 76 20.76 12.80 1.86 M0972 6 77 21.04 12.53 1.97 M0972 6 78 21.31 12.79 1.99 M0972 6 79 21.58 10.56 2.00 M0972 6 80 21.85 12.84 2.15 M0972 6 81 22.12 10.88 2.05 M0972 6 82 22.39 12.97 2.06 M0972 6 83 22.66 5.98 1.72 M0972 6 84 22.93 12.01 2.02 M0972 6 85 23.20 12.63 2.07 M0972 6 86 23.47 8.33 1.86 M0972 6 87 ENDDATA 61 0 M0972 6 88 ENDSUBENT 87 0 M0972 699999 SUBENT M0972007 20180823 M098M0972 7 1 BIB 4 22 M0972 7 2 REACTION (58-CE-142(G,2N)58-CE-140,,SIG,,,EVAL) M0972 7 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0972 7 4 section into the experimental total neutron yield M0972 7 5 reaction (g,xn) cross section obtained using M0972 7 6 quasimonoenergetic annihilation photons at Saclay M0972 7 7 was evaluated using specially theoretically M0972 7 8 calculated transitional multiplicity function - M0972 7 9 ratio M0972 7 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0972 7 11 by the way M0972 7 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0972 7 13 The neutron yield cross section was obtained at M0972 7 14 Saclay by Beil. M0972 7 15 REL-REF (R,L0042019,A.Lepretre+,J,NP/A,258,350,1976) M0972 7 16 Experimental data for the total neutron yield M0972 7 17 reaction (g,xn) cross section. M0972 7 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) ????? M0972 7 19 Theoretical preequilibrium model of photonuclear M0972 7 20 reactions based on the Fermi gas densities. M0972 7 21 STATUS (TABLE) M0972 7 22 (DEP,L0026019) M0972 7 23 The neutron yield reaction (g,xn) cross section. M0972 7 24 ENDBIB 22 0 M0972 7 25 NOCOMMON 0 0 M0972 7 26 DATA 3 40 M0972 7 27 EN DATA DATA-ERR M0972 7 28 MEV MB MB M0972 7 29 12.91 6.87 0.75 M0972 7 30 13.18 26.48 2.84 M0972 7 31 13.45 55.55 5.87 M0972 7 32 13.72 96.07 9.97 M0972 7 33 13.99 128.22 13.23 M0972 7 34 14.26 156.95 16.11 M0972 7 35 14.53 190.69 19.49 M0972 7 36 14.80 207.63 21.21 M0972 7 37 15.07 215.40 22.00 M0972 7 38 15.34 221.36 22.62 M0972 7 39 15.62 229.07 23.44 M0972 7 40 15.89 216.81 22.29 M0972 7 41 16.16 210.48 21.69 M0972 7 42 16.43 192.28 19.98 M0972 7 43 16.70 177.52 18.62 M0972 7 44 16.97 171.67 18.09 M0972 7 45 17.24 153.63 16.41 M0972 7 46 17.51 138.92 15.12 M0972 7 47 17.78 126.32 14.00 M0972 7 48 18.05 117.76 13.27 M0972 7 49 18.33 102.72 11.99 M0972 7 50 18.60 97.70 11.61 M0972 7 51 18.87 95.36 11.46 M0972 7 52 19.14 89.29 11.00 M0972 7 53 19.41 79.53 10.27 M0972 7 54 19.68 73.92 9.90 M0972 7 55 19.95 72.31 9.83 M0972 7 56 20.22 63.16 9.23 M0972 7 57 20.49 65.56 9.35 M0972 7 58 20.76 63.99 9.29 M0972 7 59 21.04 56.38 8.85 M0972 7 60 21.31 57.55 8.98 M0972 7 61 21.58 42.24 8.01 M0972 7 62 21.85 52.51 8.78 M0972 7 63 22.12 44.50 8.39 M0972 7 64 22.39 58.36 9.26 M0972 7 65 22.66 26.91 7.74 M0972 7 66 22.93 54.04 9.11 M0972 7 67 23.20 56.83 9.34 M0972 7 68 23.47 37.48 8.37 M0972 7 69 ENDDATA 42 0 M0972 7 70 ENDSUBENT 69 0 M0972 799999 SUBENT M0972008 20180823 M098M0972 8 1 BIB 3 5 M0972 8 2 REACTION ((58-CE-140(G,N)58-CE-139,,INT,,,EVAL)+ M0972 8 3 (58-CE-140(G,N+P)57-LA-138,,INT,,,EVAL)) M0972 8 4 ANALYSIS Integration of evaluated cross section. M0972 8 5 STATUS (DEP,M0972003) Evaluated cross section. M0972 8 6 (TABLE) M0972 8 7 ENDBIB 5 0 M0972 8 8 NOCOMMON 0 0 M0972 8 9 DATA 3 29 M0972 8 10 EN-MAX DATA DATA-ERR M0972 8 11 MEV MB*MEV MB*MEV M0972 8 12 16.7 1554.48 71.76 M0972 8 13 26.4 1961.40 75.17 M0972 8 14 ENDDATA 4 0 M0972 8 15 ENDSUBENT 14 0 M0972 899999 SUBENT M0972009 20180823 M098M0972 9 1 BIB 3 4 M0972 9 2 REACTION (58-CE-140(G,2N)58-CE-138,,INT,,,EVAL) M0972 9 3 ANALYSIS Integration of evaluated cross section. M0972 9 4 STATUS (DEP,M0972004) Evaluated cross section. M0972 9 5 (TABLE) M0972 9 6 ENDBIB 4 0 M0972 9 7 NOCOMMON 0 0 M0972 9 8 DATA 3 19 M0972 9 9 EN-MAX DATA DATA-ERR M0972 9 10 MEV MB*MEV MB*MEV M0972 9 11 26.4 448.22 16.54 M0972 9 12 ENDDATA 3 0 M0972 9 13 ENDSUBENT 12 0 M0972 999999 SUBENT M0972010 20180823 M098M0972 10 1 BIB 3 5 M0972 10 2 REACTION ((58-CE-142(G,N)58-CE-141,,INT,,,EVAL)+ M0972 10 3 (58-CE-142(G,N+P)57-LA-140,,INT,,,EVAL)) M0972 10 4 ANALYSIS Integration of evaluated cross section. M0972 10 5 STATUS (DEP,M0972006) Evaluated cross section. M0972 10 6 (TABLE) M0972 10 7 ENDBIB 5 0 M0972 10 8 NOCOMMON 0 0 M0972 10 9 DATA 3 29 M0972 10 10 EN-MAX DATA DATA-ERR M0972 10 11 MEV MB*MEV MB*MEV M0972 10 12 12.6 410.7 13.7 M0972 10 13 21.6 1029.3 21.1 M0972 10 14 ENDDATA 4 0 M0972 10 15 ENDSUBENT 14 0 M0972 1099999 SUBENT M0972011 20180823 M098M0972 11 1 BIB 3 4 M0972 11 2 REACTION (58-CE-142(G,2N)58-CE-140,,INT,,,EVAL) M0972 11 3 ANALYSIS Integration of evaluated cross section. M0972 11 4 STATUS (DEP,M0972007) Evaluated cross section. M0972 11 5 (TABLE) M0972 11 6 ENDBIB 4 0 M0972 11 7 NOCOMMON 0 0 M0972 11 8 DATA 3 19 M0972 11 9 EN-MAX DATA DATA-ERR M0972 11 10 MEV MB*MEV MB*MEV M0972 11 11 21.6 1083.8 23.0 M0972 11 12 ENDDATA 3 0 M0972 11 13 ENDSUBENT 12 0 M0972 1199999 ENDENTRY 11 0 M097299999999