ENTRY M0974 20190306 M100M0974 0 1 SUBENT M0974001 20190306 M100M0974 1 1 BIB 9 31 M0974 1 2 TITLE New photoneutron reaction cross section data for 153Eu M0974 1 3 and 165Ho. M0974 1 4 AUTHOR (V.V.Varlamov,A.I.Davydov) M0974 1 5 REFERENCE (C,2018VORNZH,,97,2018) M0974 1 6 INSTITUTE (4RUSMOS) M0974 1 7 INC-SOURCE (QMPH,ARAD) M0974 1 8 ANALYSIS The joint analysis of data for total (gamma,xn) and M0974 1 9 partial (gamma,n),(gamma,2n) and (gamma,3n) reactions M0974 1 10 obtained in various experiments was carried out. The M0974 1 11 new approach to analysis of systematic disagreements M0974 1 12 between data was proposed on the base of new M0974 1 13 criteria of systematic uncertainties presence - M0974 1 14 specially proposed transitional multiplicity M0974 1 15 functions M0974 1 16 Fi-theor = SIG(gamma,in)/SIG(gamma,xn). M0974 1 17 Using these functions calculated in the frame of M0974 1 18 combined photonuclear reaction model new reliable M0974 1 19 and free from problems of neutron multiplicity M0974 1 20 sorting data for photoneutron partial reactions M0974 1 21 cross sections M0974 1 22 SIG-eval(gamma,in) = Fi-theor x SIG-exp(gamma,xn) M0974 1 23 were evaluated using experimental neutron yield M0974 1 24 reaction cross sections SIG-exp(gamma,xn). M0974 1 25 ERR-ANALYS (DATA-ERR) Mean-root-squared errors. M0974 1 26 STATUS (TABLE) M0974 1 27 (APRVD) Approved by V.Varlamov. M0974 1 28 HISTORY (20180823C) Data were compiled at the Russia MSU SINP M0974 1 29 CDFE by V.Varlamov. M0974 1 30 (20190306A) Corrected by V.Varlamov: SUBENTS 010 - 017 M0974 1 31 deleted becaus of duplication with SUBENTS M0977005 - M0974 1 32 M0977008 and M0977012 - M0977015, correspondingly. M0974 1 33 ENDBIB 31 0 M0974 1 34 NOCOMMON 0 0 M0974 1 35 ENDSUBENT 34 0 M0974 199999 SUBENT M0974002 20180823 M098M0974 2 1 BIB 3 9 M0974 2 2 REACTION (63-EU-153(G,X)0-NN-1,UNW,SIG,,,EVAL) M0974 2 3 ANALYSIS The total neutron reaction cross section obtained as M0974 2 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0974 2 5 STATUS (DEP,M0974003) M0974 2 6 Evaluated (g,1n) reaction cross section. M0974 2 7 (DEP,M0974004) M0974 2 8 Evaluated (g,2n) reaction cross section. M0974 2 9 (DEP,M0974005) M0974 2 10 Evaluated (g,3n) reaction cross section. M0974 2 11 ENDBIB 9 0 M0974 2 12 NOCOMMON 0 0 M0974 2 13 DATA 3 66 M0974 2 14 EN DATA DATA-ERR M0974 2 15 MEV MB MB M0974 2 16 8.8 2.66 1.99 M0974 2 17 9.1 25.07 8.35 M0974 2 18 9.4 38.71 11.51 M0974 2 19 9.7 52.33 12.34 M0974 2 20 10.0 47.60 10.60 M0974 2 21 10.3 68.69 13.58 M0974 2 22 10.7 88.07 16.87 M0974 2 23 11.0 115.50 21.50 M0974 2 24 11.3 145.30 26.42 M0974 2 25 11.6 176.70 29.97 M0974 2 26 11.9 197.50 33.29 M0974 2 27 12.2 228.00 38.18 M0974 2 28 12.5 238.80 39.78 M0974 2 29 12.8 239.20 39.83 M0974 2 30 13.1 223.50 37.31 M0974 2 31 13.4 222.10 37.02 M0974 2 32 13.7 224.90 37.42 M0974 2 33 14.1 214.60 36.12 M0974 2 34 14.4 232.00 40.27 M0974 2 35 14.7 245.50 44.90 M0974 2 36 15.0 241.40 40.83 M0974 2 37 15.3 245.10 41.51 M0974 2 38 15.6 249.40 42.65 M0974 2 39 15.9 224.40 39.83 M0974 2 40 16.2 221.90 42.38 M0974 2 41 16.5 204.00 40.50 M0974 2 42 16.8 204.80 41.79 M0974 2 43 17.1 181.50 37.76 M0974 2 44 17.5 173.90 36.75 M0974 2 45 17.8 168.00 35.97 M0974 2 46 18.1 145.50 31.67 M0974 2 47 18.4 129.40 28.53 M0974 2 48 18.7 122.90 27.57 M0974 2 49 19.0 112.60 25.74 M0974 2 50 19.3 106.50 24.70 M0974 2 51 19.6 91.52 21.59 M0974 2 52 19.9 86.84 20.77 M0974 2 53 20.2 83.20 20.14 M0974 2 54 20.6 80.73 19.74 M0974 2 55 20.9 78.27 19.38 M0974 2 56 21.2 75.17 18.77 M0974 2 57 21.5 63.30 16.59 M0974 2 58 21.8 57.31 15.08 M0974 2 59 22.1 50.83 13.90 M0974 2 60 22.4 58.81 15.62 M0974 2 61 22.7 56.21 13.97 M0974 2 62 23.0 55.05 16.11 M0974 2 63 23.3 51.82 16.48 M0974 2 64 23.6 40.01 13.48 M0974 2 65 24.0 48.52 15.20 M0974 2 66 24.3 51.00 16.32 M0974 2 67 24.6 38.41 14.65 M0974 2 68 24.9 27.67 11.85 M0974 2 69 25.2 40.36 16.21 M0974 2 70 25.5 45.13 18.93 M0974 2 71 25.8 33.86 13.99 M0974 2 72 26.1 24.33 14.26 M0974 2 73 26.4 29.05 13.42 M0974 2 74 26.8 23.14 14.03 M0974 2 75 27.1 22.50 11.93 M0974 2 76 27.4 28.78 16.66 M0974 2 77 27.7 26.09 13.62 M0974 2 78 28.0 23.46 14.97 M0974 2 79 28.3 33.14 16.17 M0974 2 80 28.6 36.15 19.02 M0974 2 81 28.9 40.94 20.77 M0974 2 82 ENDDATA 68 0 M0974 2 83 ENDSUBENT 82 0 M0974 299999 SUBENT M0974003 20180823 M098M0974 3 1 BIB 4 22 M0974 3 2 REACTION ((63-EU-153(G,N)63-EU-152,,SIG,,,EVAL)+ M0974 3 3 (63-EU-153(G,N+P)62-SM-151,,SIG,,,EVAL)) M0974 3 4 ANALYSIS The contribution of partial reaction (g,n) cross M0974 3 5 section into the experimental total neutron yield M0974 3 6 reaction (g,xn) cross section obtained using M0974 3 7 quasimonoenergetic annihilation photons at Saclay M0974 3 8 was evaluated using specially theoretically M0974 3 9 calculated transitional multiplicity function - M0974 3 10 ratio M0974 3 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0974 3 12 by the way M0974 3 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0974 3 14 The neutron yield cross section was obtained at M0974 3 15 Livermore. M0974 3 16 REL-REF (R,L0016002,B.L.Berman+,J,PR,185,1576,1969) M0974 3 17 Experimental data for the total neutron yield M0974 3 18 reaction (g,xn) cross section. M0974 3 19 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0974 3 20 Theoretical preequilibrium model of photonuclear M0974 3 21 reactions based on the Fermi gas densities. M0974 3 22 STATUS (DEP,L0016002) M0974 3 23 The neutron yield reaction (g,xn) cross section. M0974 3 24 ENDBIB 22 0 M0974 3 25 NOCOMMON 0 0 M0974 3 26 DATA 3 66 M0974 3 27 EN DATA DATA-ERR M0974 3 28 MEV MB MB M0974 3 29 8.8 2.66 1.82 M0974 3 30 9.1 25.07 7.79 M0974 3 31 9.4 38.71 10.77 M0974 3 32 9.7 52.33 11.34 M0974 3 33 10.0 47.60 9.68 M0974 3 34 10.3 68.69 12.27 M0974 3 35 10.7 88.07 15.19 M0974 3 36 11.0 115.50 19.29 M0974 3 37 11.3 145.30 23.65 M0974 3 38 11.6 176.70 26.60 M0974 3 39 11.9 197.50 29.53 M0974 3 40 12.2 228.00 33.83 M0974 3 41 12.5 238.80 35.22 M0974 3 42 12.8 239.20 35.26 M0974 3 43 13.1 223.50 33.04 M0974 3 44 13.4 222.10 32.77 M0974 3 45 13.7 224.90 33.11 M0974 3 46 14.1 214.60 32.00 M0974 3 47 14.4 232.00 35.80 M0974 3 48 14.7 245.40 39.85 M0974 3 49 15.0 239.30 36.19 M0974 3 50 15.3 234.50 35.72 M0974 3 51 15.6 215.50 33.81 M0974 3 52 15.9 166.50 28.68 M0974 3 53 16.2 139.00 27.89 M0974 3 54 16.5 108.30 24.71 M0974 3 55 16.8 93.56 24.01 M0974 3 56 17.1 72.80 20.72 M0974 3 57 17.5 62.59 19.47 M0974 3 58 17.8 55.37 18.55 M0974 3 59 18.1 44.67 15.95 M0974 3 60 18.4 37.61 14.11 M0974 3 61 18.7 34.24 13.40 M0974 3 62 19.0 30.36 12.31 M0974 3 63 19.3 28.02 11.67 M0974 3 64 19.6 23.58 10.07 M0974 3 65 19.9 21.94 9.58 M0974 3 66 20.2 20.68 9.20 M0974 3 67 20.6 19.76 8.94 M0974 3 68 20.9 18.88 8.69 M0974 3 69 21.2 17.87 8.36 M0974 3 70 21.5 14.85 7.20 M0974 3 71 21.8 13.31 6.52 M0974 3 72 22.1 11.71 5.89 M0974 3 73 22.4 13.47 6.70 M0974 3 74 22.7 12.79 6.18 M0974 3 75 23.0 12.49 6.60 M0974 3 76 23.3 11.76 6.52 M0974 3 77 23.6 9.07 5.22 M0974 3 78 24.0 10.98 6.11 M0974 3 79 24.3 11.51 6.57 M0974 3 80 24.6 8.63 5.78 M0974 3 81 24.9 6.20 4.44 M0974 3 82 25.2 9.05 6.70 M0974 3 83 25.5 10.13 8.03 M0974 3 84 25.8 7.66 5.59 M0974 3 85 26.1 5.56 5.69 M0974 3 86 26.4 6.73 5.26 M0974 3 87 26.8 5.42 5.63 M0974 3 88 27.1 5.26 4.52 M0974 3 89 27.4 6.70 6.87 M0974 3 90 27.7 5.97 5.25 M0974 3 91 28.0 5.31 5.89 M0974 3 92 28.3 7.32 6.49 M0974 3 93 28.6 7.89 8.12 M0974 3 94 28.9 8.72 8.30 M0974 3 95 ENDDATA 68 0 M0974 3 96 ENDSUBENT 95 0 M0974 399999 SUBENT M0974004 20180823 M098M0974 4 1 BIB 4 21 M0974 4 2 REACTION (63-EU-153(G,2N)63-EU-151,,SIG,,,EVAL) M0974 4 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0974 4 4 section into the experimental total neutron yield M0974 4 5 reaction (g,xn) cross section obtained using M0974 4 6 quasimonoenergetic annihilation photons at Saclay M0974 4 7 was evaluated using specially theoretically M0974 4 8 calculated transitional multiplicity function - M0974 4 9 ratio M0974 4 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0974 4 11 by the way M0974 4 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0974 4 13 The neutron yield cross section was obtained at M0974 4 14 Livermore. M0974 4 15 REL-REF (R,L0016002,B.L.Berman+,J,PR,185,1576,1969) M0974 4 16 Experimental data for the total neutron yield M0974 4 17 reaction (g,xn) cross section. M0974 4 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0974 4 19 Theoretical preequilibrium model of photonuclear M0974 4 20 reactions based on the Fermi gas densities. M0974 4 21 STATUS (DEP,L0016002) M0974 4 22 The neutron yield reaction (g,xn) cross section. M0974 4 23 ENDBIB 21 0 M0974 4 24 NOCOMMON 0 0 M0974 4 25 DATA 3 48 M0974 4 26 EN DATA DATA-ERR M0974 4 27 MEV MB MB M0974 4 28 14.4 0.00 4.32 M0974 4 29 14.7 0.05 4.87 M0974 4 30 15.0 2.07 4.48 M0974 4 31 15.3 10.59 5.62 M0974 4 32 15.6 33.87 8.66 M0974 4 33 15.9 57.99 10.97 M0974 4 34 16.2 82.94 14.29 M0974 4 35 16.5 95.68 15.59 M0974 4 36 16.8 111.30 17.57 M0974 4 37 17.1 108.70 16.86 M0974 4 38 17.5 111.30 17.10 M0974 4 39 17.8 112.60 17.24 M0974 4 40 18.1 100.80 15.56 M0974 4 41 18.4 91.81 14.27 M0974 4 42 18.7 88.70 14.03 M0974 4 43 19.0 82.20 13.30 M0974 4 44 19.3 78.47 12.91 M0974 4 45 19.6 67.94 11.42 M0974 4 46 19.9 64.89 11.09 M0974 4 47 20.2 62.52 10.85 M0974 4 48 20.6 60.96 10.70 M0974 4 49 20.9 59.39 10.59 M0974 4 50 21.2 57.30 10.32 M0974 4 51 21.5 48.45 9.31 M0974 4 52 21.8 44.00 8.49 M0974 4 53 22.1 39.12 7.94 M0974 4 54 22.4 45.34 8.84 M0974 4 55 22.7 43.42 7.72 M0974 4 56 23.0 42.54 9.43 M0974 4 57 23.3 39.87 9.85 M0974 4 58 23.6 30.35 8.07 M0974 4 59 24.0 35.67 8.66 M0974 4 60 24.3 35.59 8.89 M0974 4 61 24.6 25.22 7.67 M0974 4 62 24.9 16.36 5.85 M0974 4 63 25.2 21.31 7.05 M0974 4 64 25.5 21.68 7.53 M0974 4 65 25.8 14.44 5.27 M0974 4 66 26.1 9.14 4.91 M0974 4 67 26.4 9.83 4.31 M0974 4 68 26.8 7.07 4.20 M0974 4 69 27.1 6.20 3.33 M0974 4 70 27.4 7.32 4.46 M0974 4 71 27.7 6.01 3.39 M0974 4 72 28.0 5.08 3.63 M0974 4 73 28.3 6.55 3.74 M0974 4 74 28.6 6.83 4.42 M0974 4 75 28.9 7.12 4.52 M0974 4 76 ENDDATA 50 0 M0974 4 77 ENDSUBENT 76 0 M0974 499999 SUBENT M0974005 20180823 M098M0974 5 1 BIB 4 21 M0974 5 2 REACTION (63-EU-153(G,3N)63-EU-150,,SIG,,,EVAL) M0974 5 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0974 5 4 section into the experimental total neutron yield M0974 5 5 reaction (g,xn) cross section obtained using M0974 5 6 quasimonoenergetic annihilation photons at Saclay M0974 5 7 was evaluated using specially theoretically M0974 5 8 calculated transitional multiplicity function - M0974 5 9 ratio M0974 5 10 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M0974 5 11 by the way M0974 5 12 SIG-eval(g,3n) = (F3-theor)x(SIG-exp(g,xn)). M0974 5 13 The neutron yield cross section was obtained at M0974 5 14 Livermore. M0974 5 15 REL-REF (R,L0016002,B.L.Berman+,J,PR,185,1576,1969) M0974 5 16 Experimental data for the total neutron yield M0974 5 17 reaction (g,xn) cross section. M0974 5 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0974 5 19 Theoretical preequilibrium model of photonuclear M0974 5 20 reactions based on the Fermi gas densities. M0974 5 21 STATUS (DEP,L0016002) M0974 5 22 The neutron yield reaction (g,xn) cross section. M0974 5 23 ENDBIB 21 0 M0974 5 24 NOCOMMON 0 0 M0974 5 25 DATA 3 21 M0974 5 26 EN DATA DATA-ERR M0974 5 27 MEV MB MB M0974 5 28 22.7 0.00 0.06 M0974 5 29 23.0 0.02 0.06 M0974 5 30 23.3 0.18 0.09 M0974 5 31 23.6 0.59 0.17 M0974 5 32 24.0 1.87 0.42 M0974 5 33 24.3 3.90 0.85 M0974 5 34 24.6 4.54 1.19 M0974 5 35 24.9 5.09 1.55 M0974 5 36 25.2 10.00 2.44 M0974 5 37 25.5 13.32 3.35 M0974 5 38 25.8 11.75 3.12 M0974 5 39 26.1 9.62 3.65 M0974 5 40 26.4 12.48 3.84 M0974 5 41 26.8 10.65 4.18 M0974 5 42 27.1 11.04 4.07 M0974 5 43 27.4 14.75 5.32 M0974 5 44 27.7 14.10 4.97 M0974 5 45 28.0 13.06 5.43 M0974 5 46 28.3 19.26 5.93 M0974 5 47 28.6 21.43 6.46 M0974 5 48 28.9 25.10 7.94 M0974 5 49 ENDDATA 23 0 M0974 5 50 ENDSUBENT 49 0 M0974 599999 SUBENT M0974006 20180823 M098M0974 6 1 BIB 3 3 M0974 6 2 REACTION (63-EU-153(G,X)0-NN-1,UNW,INT,,,EVAL) M0974 6 3 ANALYSIS Integration of evaluated cross section. M0974 6 4 STATUS (DEP,M0974002) Evaluated cross section. M0974 6 5 ENDBIB 3 0 M0974 6 6 NOCOMMON 0 0 M0974 6 7 DATA 3 39 M0974 6 8 EN-MAX DATA DATA-ERR M0974 6 9 MEV MB*MEV MB*MEV M0974 6 10 14.9 955.1 48.2 M0974 6 11 22.3 1990.3 72.2 M0974 6 12 29.0 2245.6 76.7 M0974 6 13 ENDDATA 5 0 M0974 6 14 ENDSUBENT 13 0 M0974 699999 SUBENT M0974007 20180823 M098M0974 7 1 BIB 3 4 M0974 7 2 REACTION ((63-EU-153(G,N)63-EU-152,,INT,,,EVAL)+ M0974 7 3 (63-EU-153(G,N+P)62-SM-151,,INT,,,EVAL)) M0974 7 4 ANALYSIS Integration of evaluated cross section. M0974 7 5 STATUS (DEP,M0974003) Evaluated cross section. M0974 7 6 ENDBIB 4 0 M0974 7 7 NOCOMMON 0 0 M0974 7 8 DATA 3 39 M0974 7 9 EN-MAX DATA DATA-ERR M0974 7 10 MEV MB*MEV MB*MEV M0974 7 11 14.9 954.7 42.8 M0974 7 12 22.3 1471.7 54.5 M0974 7 13 29.0 1529.3 55.5 M0974 7 14 ENDDATA 5 0 M0974 7 15 ENDSUBENT 14 0 M0974 799999 SUBENT M0974008 20180823 M098M0974 8 1 BIB 3 3 M0974 8 2 REACTION (63-EU-153(G,2N)63-EU-151,,INT,,,EVAL) M0974 8 3 ANALYSIS Integration of evaluated cross section. M0974 8 4 STATUS (DEP,M0974004) Evaluated cross section. M0974 8 5 ENDBIB 3 0 M0974 8 6 NOCOMMON 0 0 M0974 8 7 DATA 3 29 M0974 8 8 EN-MAX DATA DATA-ERR M0974 8 9 MEV MB*MEV MB*MEV M0974 8 10 22.3 518.6 22.6 M0974 8 11 29.0 655.1 25.1 M0974 8 12 ENDDATA 4 0 M0974 8 13 ENDSUBENT 12 0 M0974 899999 SUBENT M0974009 20180823 M098M0974 9 1 BIB 3 3 M0974 9 2 REACTION (63-EU-153(G,3N)63-EU-150,,INT,,,EVAL) M0974 9 3 ANALYSIS Integration of evaluated cross section. M0974 9 4 STATUS (DEP,M0974004) Evaluated cross section. M0974 9 5 ENDBIB 3 0 M0974 9 6 NOCOMMON 0 0 M0974 9 7 DATA 3 19 M0974 9 8 EN-MAX DATA DATA-ERR M0974 9 9 MEV MB*MEV MB*MEV M0974 9 10 29.0 68.1 3.6 M0974 9 11 ENDDATA 3 0 M0974 9 12 ENDSUBENT 11 0 M0974 999999 NOSUBENT M0974010 20181010 M100M0974 10 1 NOSUBENT M0974011 20181010 M100M0974 11 1 NOSUBENT M0974012 20181010 M100M0974 12 1 NOSUBENT M0974013 20181010 M100M0974 13 1 NOSUBENT M0974014 20181010 M100M0974 14 1 NOSUBENT M0974015 20181010 M100M0974 15 1 NOSUBENT M0974016 20181010 M100M0974 16 1 NOSUBENT M0974017 20181010 M100M0974 17 1 ENDENTRY 17 0 M097499999999