ENTRY M0975 20190121 M099M097500000001 SUBENT M0975001 20190121 M099M097500100001 BIB 9 26 M097500100002 TITLE New reliable data on the photodisintegration of 160Gd M097500100003 AUTHOR (V.V.Varlamov,V.D.Kaidarova,V.N.Orlin) M097500100004 REFERENCE (J,MPM,1,1910202,2019) M097500100005 INSTITUTE (4RUSMOS) M097500100006 INC-SOURCE (QMPH,ARAD) M097500100007 ANALYSIS The joint analysis of data for total (g,xn) and M097500100008 partial (g,n), (g,2n) and (g,3n) reactions obtained M097500100009 in various experiments was carried out. The new M097500100010 approach to analysis of systematic disagreements M097500100011 between data was proposed on the base of new M097500100012 criteria of systematic uncertainties presence - M097500100013 specially proposed transitional multiplicity M097500100014 functions M097500100015 Fi-theor = SIG(g,in)/SIG(g,xn). M097500100016 Using these functions calculated in the frame of M097500100017 combined photonuclear reaction model new reliable M097500100018 and free from problems of neutron multiplicity M097500100019 sorting data for photoneutron partial reactions M097500100020 cross sections M097500100021 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M097500100022 were evaluated using experimental neutron yield M097500100023 reaction cross sections SIG-exp(g,xn). M097500100024 ERR-ANALYS (DATA-ERR) Root-mean-squared errors. M097500100025 STATUS (APRVD) By V.Varlamov. M097500100026 HISTORY (20190121C) Data were compiled at the Russia MSU SINP M097500100027 CDFE by V.Varlamov. M097500100028 ENDBIB 26 0 M097500100029 NOCOMMON 0 0 M097500100030 ENDSUBENT 29 0 M097500199999 SUBENT M0975002 20190121 M099M097500200001 BIB 3 10 M097500200002 REACTION (64-GD-160(G,X)0-NN-1,UNW,SIG,,,EVAL) M097500200003 ANALYSIS The total neutron reaction cross section obtained as M097500200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M097500200005 STATUS (TABLE) Data plotted in Fig. 3. M097500200006 (DEP,M0975003) M097500200007 Evaluated (g,n) reaction cross section. M097500200008 (DEP,M0975004) M097500200009 Evaluated (g,2n) reaction cross section. M097500200010 (DEP,M0975005) M097500200011 Evaluated (g,3n) reaction cross section. M097500200012 ENDBIB 10 0 M097500200013 NOCOMMON 0 0 M097500200014 DATA 3 50 M097500200015 EN DATA DATA-ERR M097500200016 MEV MB MB M097500200017 7.91 20.53 6.74 M097500200018 8.31 32.02 6.15 M097500200019 8.71 36.68 6.65 M097500200020 9.11 43.00 6.84 M097500200021 9.51 52.04 6.73 M097500200022 9.91 65.07 7.77 M097500200023 10.31 92.73 10.59 M097500200024 10.71 120.17 12.77 M097500200025 11.11 142.11 16.36 M097500200026 11.51 214.29 23.54 M097500200027 11.91 264.36 28.53 M097500200028 12.31 278.09 30.00 M097500200029 12.71 269.85 29.42 M097500200030 13.11 256.39 28.21 M097500200031 13.51 250.88 27.81 M097500200032 13.91 222.18 23.01 M097500200033 14.31 245.18 20.48 M097500200034 14.71 236.39 17.55 M097500200035 15.11 260.72 19.46 M097500200036 15.51 249.41 18.85 M097500200037 15.91 270.64 19.88 M097500200038 16.31 264.47 19.96 M097500200039 16.71 248.83 19.90 M097500200040 17.11 223.65 17.65 M097500200041 17.51 207.80 16.74 M097500200042 17.91 177.00 14.48 M097500200043 18.31 156.13 13.21 M097500200044 18.71 135.79 11.70 M097500200045 19.11 125.32 11.14 M097500200046 19.51 106.24 9.82 M097500200047 20.11 99.11 9.40 M097500200048 20.31 86.78 8.00 M097500200049 20.71 70.19 6.93 M097500200050 21.11 60.28 6.36 M097500200051 21.51 58.17 7.59 M097500200052 21.91 48.76 7.21 M097500200053 22.31 49.84 7.29 M097500200054 22.71 51.72 5.80 M097500200055 23.11 51.77 6.11 M097500200056 23.51 49.70 6.23 M097500200057 23.91 47.56 5.87 M097500200058 24.31 47.11 5.57 M097500200059 24.71 46.99 5.46 M097500200060 25.31 31.32 4.77 M097500200061 25.91 32.91 5.21 M097500200062 26.51 39.51 5.53 M097500200063 27.11 22.00 4.06 M097500200064 27.71 20.56 4.56 M097500200065 28.31 31.25 5.13 M097500200066 29.51 26.72 8.95 M097500200067 ENDDATA 52 0 M097500200068 ENDSUBENT 67 0 M097500299999 SUBENT M0975003 20190121 M099M097500300001 BIB 4 21 M097500300002 REACTION ((64-GD-160(G,N)64-GD-159,,SIG,,,EVAL)+ M097500300003 (64-GD-160(G,N+P)63-EU-158,,SIG,,,EVAL)) M097500300004 ANALYSIS The contribution of partial reaction (g,n) cross M097500300005 section into the experimental total neutron yield M097500300006 reaction (g,xn) cross section obtained using M097500300007 quasimonoenergetic annihilation photons at Livermore M097500300008 (USA) was evaluated using specially theoretically M097500300009 calculated transitional multiplicity function - M097500300010 ratio M097500300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097500300012 by the way M097500300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097500300014 REL-REF (R,L0016006,B.L.Berman+,J,PR,185,1576,1969) M097500300015 Experimental data for the total neutron yield M097500300016 reaction (g,xn) cross section. M097500300017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097500300018 Theoretical preequilibrium model of photonuclear M097500300019 reactions based on the Fermi gas densities. M097500300020 STATUS (TABLE) Data plotted in Fig. 3. M097500300021 (DEP,L0016006) M097500300022 The neutron yield reaction (g,xn) cross section. M097500300023 ENDBIB 21 0 M097500300024 NOCOMMON 0 0 M097500300025 DATA 3 50 M097500300026 EN DATA DATA-ERR M097500300027 MEV MB MB M097500300028 7.91 20.53 6.74 M097500300029 8.31 32.02 6.15 M097500300030 8.71 36.68 6.65 M097500300031 9.11 43.00 6.84 M097500300032 9.51 52.04 6.73 M097500300033 9.91 65.07 7.77 M097500300034 10.31 92.73 10.59 M097500300035 10.71 120.17 12.77 M097500300036 11.11 142.11 16.36 M097500300037 11.51 214.29 23.54 M097500300038 11.91 264.36 28.53 M097500300039 12.31 278.09 30.00 M097500300040 12.71 269.85 29.42 M097500300041 13.11 256.39 28.21 M097500300042 13.51 250.88 27.81 M097500300043 13.91 214.10 22.99 M097500300044 14.31 189.26 19.64 M097500300045 14.71 139.51 14.42 M097500300046 15.11 126.32 13.33 M097500300047 15.51 107.55 11.39 M097500300048 15.91 107.25 10.91 M097500300049 16.31 97.09 10.01 M097500300050 16.71 83.95 9.03 M097500300051 17.11 69.86 7.30 M097500300052 17.51 60.26 6.33 M097500300053 17.91 50.87 5.41 M097500300054 18.31 40.03 4.30 M097500300055 18.71 33.38 3.62 M097500300056 19.11 29.60 3.29 M097500300057 19.51 24.28 2.79 M097500300058 20.11 22.03 2.58 M097500300059 20.31 19.22 2.18 M097500300060 20.71 15.44 1.88 M097500300061 21.11 13.19 1.71 M097500300062 21.51 12.69 2.04 M097500300063 21.91 10.52 1.91 M097500300064 22.31 10.62 1.92 M097500300065 22.71 10.90 1.57 M097500300066 23.11 10.77 1.76 M097500300067 23.51 10.12 1.91 M097500300068 23.91 9.49 1.88 M097500300069 24.31 9.13 1.78 M097500300070 24.71 8.82 1.69 M097500300071 25.31 5.70 1.40 M097500300072 25.91 5.87 1.46 M097500300073 26.51 7.04 1.52 M097500300074 27.11 3.85 1.07 M097500300075 27.71 3.43 1.12 M097500300076 28.31 4.89 1.15 M097500300077 29.51 3.75 1.72 M097500300078 ENDDATA 52 0 M097500300079 ENDSUBENT 78 0 M097500399999 SUBENT M0975004 20190121 M099M097500400001 BIB 4 20 M097500400002 REACTION (64-GD-160(G,2N)64-GD-158,,SIG,,,EVAL) M097500400003 ANALYSIS The contribution of partial reaction (g,2n) cross M097500400004 section into the experimental total neutron yield M097500400005 reaction (g,xn) cross section obtained using M097500400006 quasimonoenergetic annihilation photons at Livermore M097500400007 (USA) was evaluated using specially theoretically M097500400008 calculated transitional multiplicity function - M097500400009 ratio M097500400010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097500400011 by the way M097500400012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097500400013 REL-REF (R,L0016006,B.L.Berman+,J,PR,185,1576,1969) M097500400014 Experimental data for the total neutron yield M097500400015 reaction (g,xn) cross section. M097500400016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097500400017 Theoretical preequilibrium model of photonuclear M097500400018 reactions based on the Fermi gas densities. M097500400019 STATUS (TABLE) Data plotted in Fig. 3. M097500400020 (DEP,L0016006) M097500400021 The neutron yield reaction (g,xn) cross section. M097500400022 ENDBIB 20 0 M097500400023 NOCOMMON 0 0 M097500400024 DATA 3 35 M097500400025 EN DATA DATA-ERR M097500400026 MEV MB MB M097500400027 13.91 8.07 0.86 M097500400028 14.31 55.91 5.80 M097500400029 14.71 96.88 10.01 M097500400030 15.11 134.40 14.18 M097500400031 15.51 141.86 15.02 M097500400032 15.91 163.39 16.62 M097500400033 16.31 167.38 17.26 M097500400034 16.71 164.87 17.73 M097500400035 17.11 153.79 16.07 M097500400036 17.51 147.53 15.50 M097500400037 17.91 126.12 13.44 M097500400038 18.31 116.10 12.48 M097500400039 18.71 102.40 11.12 M097500400040 19.11 95.71 10.64 M097500400041 19.51 81.95 9.42 M097500400042 20.11 77.08 9.03 M097500400043 20.31 67.55 7.69 M097500400044 20.71 54.74 6.67 M097500400045 21.11 47.09 6.12 M097500400046 21.51 45.47 7.31 M097500400047 21.91 38.23 6.95 M097500400048 22.31 38.80 7.03 M097500400049 22.71 38.46 5.57 M097500400050 23.11 35.11 5.76 M097500400051 23.51 29.76 5.63 M097500400052 23.91 24.70 4.89 M097500400053 24.31 21.23 4.14 M097500400054 24.71 18.40 3.54 M097500400055 25.31 10.12 2.49 M097500400056 25.91 9.19 2.29 M097500400057 26.51 9.94 2.14 M097500400058 27.11 5.07 1.41 M097500400059 27.71 4.31 1.41 M097500400060 28.31 5.95 1.40 M097500400061 29.51 4.32 1.98 M097500400062 ENDDATA 37 0 M097500400063 ENDSUBENT 62 0 M097500499999 SUBENT M0975005 20190121 M099M097500500001 BIB 4 20 M097500500002 REACTION (64-GD-160(G,3N)64-GD-157,,SIG,,,EVAL) M097500500003 ANALYSIS The contribution of partial reaction (g,3n) cross M097500500004 section into the experimental total neutron yield M097500500005 reaction (g,xn) cross section obtained using M097500500006 quasimonoenergetic annihilation photons at Livermore M097500500007 (USA) was evaluated using specially theoretically M097500500008 calculated transitional multiplicity function - M097500500009 ratio M097500500010 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M097500500011 by the way M097500500012 SIG-eval(g,3n) = (F2-theor)x(SIG-exp(g,xn)). M097500500013 REL-REF (R,L0016006,B.L.Berman+,J,PR,185,1576,1969) M097500500014 Experimental data for the total neutron yield M097500500015 reaction (g,xn) cross section. M097500500016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097500500017 Theoretical preequilibrium model of photonuclear M097500500018 reactions based on the Fermi gas densities. M097500500019 STATUS (TABLE) Data plotted in Fig. 3. M097500500020 (DEP,L0016006) M097500500021 The neutron yield reaction (g,xn) cross section. M097500500022 ENDBIB 20 0 M097500500023 NOCOMMON 0 0 M097500500024 DATA 3 14 M097500500025 EN DATA DATA-ERR M097500500026 MEV MB MB M097500500027 22.31 0.41 0.07 M097500500028 22.71 2.35 0.34 M097500500029 23.11 5.89 0.96 M097500500030 23.51 9.81 1.85 M097500500031 23.91 13.35 2.64 M097500500032 24.31 16.74 3.26 M097500500033 24.71 19.75 3.80 M097500500034 25.31 15.48 3.82 M097500500035 25.91 17.85 4.45 M097500500036 26.51 22.52 4.86 M097500500037 27.11 13.06 3.65 M097500500038 27.71 12.81 4.19 M097500500039 28.31 20.40 4.80 M097500500040 29.51 18.64 8.55 M097500500041 ENDDATA 16 0 M097500500042 ENDSUBENT 41 0 M097500599999 SUBENT M0975006 20190121 M099M097500600001 BIB 3 4 M097500600002 REACTION (64-GD-160(G,X)0-NN-1,UNW,INT,,,EVAL) M097500600003 ANALYSIS Integration of evaluated cross section. M097500600004 STATUS (DEP,M0975002) Evaluated cross section. M097500600005 (TABLE) Data from Table 2. M097500600006 ENDBIB 4 0 M097500600007 NOCOMMON 0 0 M097500600008 DATA 3 39 M097500600009 EN-MAX DATA DATA-ERR M097500600010 MEV MB*MEV MB*MEV M097500600011 13.4 754.93 27.58 M097500600012 21.3 2235.71 40.62 M097500600013 30.0 2569.06 43.48 M097500600014 ENDDATA 5 0 M097500600015 ENDSUBENT 14 0 M097500699999 SUBENT M0975007 20190121 M099M097500700001 BIB 3 5 M097500700002 REACTION ((64-GD-160(G,N)64-GD-159,,INT,,,EVAL)+ M097500700003 (64-GD-160(G,N+P)63-EU-158,,INT,,,EVAL)) M097500700004 ANALYSIS Integration of evaluated cross section. M097500700005 STATUS (DEP,M0975003) Evaluated cross section. M097500700006 (TABLE) Data from Table 2. M097500700007 ENDBIB 5 0 M097500700008 NOCOMMON 0 0 M097500700009 DATA 3 39 M097500700010 EN-MAX DATA DATA-ERR M097500700011 MEV MB*MEV MB*MEV M097500700012 13.4 754.93 27.58 M097500700013 21.3 1433.11 34.53 M097500700014 30.0 1495.69 34.72 M097500700015 ENDDATA 5 0 M097500700016 ENDSUBENT 15 0 M097500799999 SUBENT M0975008 20190121 M099M097500800001 BIB 3 4 M097500800002 REACTION (64-GD-160(G,2N)64-GD-158,,INT,,,EVAL) M097500800003 ANALYSIS Integration of evaluated cross section. M097500800004 STATUS (DEP,M0975004) Evaluated cross section. M097500800005 (TABLE) Data from Table 2. M097500800006 ENDBIB 4 0 M097500800007 NOCOMMON 0 0 M097500800008 DATA 3 29 M097500800009 EN-MAX DATA DATA-ERR M097500800010 MEV MB*MEV MB*MEV M097500800011 21.3 802.60 34.53 M097500800012 30.0 954.28 22.83 M097500800013 ENDDATA 4 0 M097500800014 ENDSUBENT 13 0 M097500899999 SUBENT M0975009 20190121 M099M097500900001 BIB 3 4 M097500900002 REACTION (64-GD-160(G,3N)64-GD-157,,INT,,,EVAL) M097500900003 ANALYSIS Integration of evaluated cross section. M097500900004 STATUS (DEP,M0975005) Evaluated cross section. M097500900005 (TABLE) Data from Table 2. M097500900006 ENDBIB 4 0 M097500900007 NOCOMMON 0 0 M097500900008 DATA 3 19 M097500900009 EN-MAX DATA DATA-ERR M097500900010 MEV MB*MEV MB*MEV M097500900011 30.0 119.10 12.78 M097500900012 ENDDATA 3 0 M097500900013 ENDSUBENT 12 0 M097500999999 ENDENTRY 9 0 M097599999999