ENTRY M1036 20221019 M121M103600000001 SUBENT M1036001 20221019 M121M103600100001 BIB 9 28 M103600100002 TITLE Reliability of results of photonuclear experiments for M103600100003 58Ni. M103600100004 AUTHOR (V.V.Varlamov,A.I.Davydov,V.N.Orlin) M103600100005 REFERENCE (J,PAN,85,316,2022) M103600100006 #doi:10.1134/S1063778822040123 M103600100007 English translation of YF,85,237,2022. M103600100008 (J,YF,85,237,2022) M103600100009 #doi:10.31857/S0044002721030156 M103600100010 INSTITUTE (4RUSMOS) M103600100011 INC-SOURCE (QMPH,ARAD) M103600100012 ANALYSIS The joint analysis of the cross sections of total and M103600100013 partial (g,xn), (g,n) and (g,2n) reactions obtained M103600100014 in different experiments was carried out using an M103600100015 approach which consists in analyzing the systematic M103600100016 disagreement among data, attributed to the systematic M103600100017 uncertainties. Transitional multiplicity functions M103600100018 Fi-theor = SIG-theor(g,in)/SIG-theor(g,xn) M103600100019 were proposed in the framework of the combined M103600100020 photonucleon reaction model in order to evaluate M103600100021 partial photoneutron reaction cross sections using M103600100022 experimental neutron yields SIG-exp(g,xn), without M103600100023 the problems related to the neutron multiplicity M103600100024 sorting procedure M103600100025 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn). M103600100026 ERR-ANALYS (DATA-ERR) Mean-root-squared errors. M103600100027 STATUS (APRVD) Approved by V.Varlamov. M103600100028 HISTORY (20221019C) Data were compiled at the Russia MSU SINP M103600100029 CDFE by V.Varlamov. M103600100030 ENDBIB 28 0 M103600100031 NOCOMMON 0 0 M103600100032 ENDSUBENT 31 0 M103600199999 SUBENT M1036002 20221019 M121M103600200001 BIB 4 24 M103600200002 REACTION ((28-NI-58(G,N)28-NI-57,,SIG,,,EVAL)+ M103600200003 (28-NI-58(G,N+P)27-CO-56,,SIG,,,EVAL)) M103600200004 ANALYSIS The contribution of partial reaction (g,1n) cross M103600200005 section into the experimental total neutron yield M103600200006 reaction (g,xn) cross section obtained using M103600200007 quasimonoenergetic annihilation photons at Livermore M103600200008 (USA) was evaluated using specially theoretically M103600200009 calculated transitional multiplicity function - M103600200010 ratio M103600200011 F1-theor = SIG-theor(g,1n)/SIG-theor(g,xn) M103600200012 by the way M103600200013 SIG-eval(g,1n) = (F1-theor)x(SIG-exp(g,xn)). M103600200014 REL-REF (R,L0034002,S.C.Fultz+,J,PR/C,10,608,1974) M103600200015 The neutron yield cross section of 58Ni(g,xn) reaction M103600200016 obtained at Livermore. M103600200017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M103600200018 Theoretical combined model of photonuclear M103600200019 reactions - preequilibrium model based on the Fermi M103600200020 gas densities. M103600200021 STATUS (TABLE) Data presented in Fig. 4c M103600200022 of Phys.Atom.Nucl.85(2022)316. M103600200023 (DEP,L0034002) M103600200024 The neutron yield cross section of 58Ni(g,xn) reaction M103600200025 obtained at Livermore. M103600200026 ENDBIB 24 0 M103600200027 NOCOMMON 0 0 M103600200028 DATA 3 112 M103600200029 EN DATA DATA-ERR M103600200030 MEV MB MB M103600200031 12.21 2.14 1.09 M103600200032 12.34 5.50 1.03 M103600200033 12.46 3.71 1.07 M103600200034 12.58 3.17 1.22 M103600200035 12.70 5.18 1.16 M103600200036 12.82 8.15 1.47 M103600200037 12.94 5.24 1.10 M103600200038 13.06 8.02 1.18 M103600200039 13.18 5.67 0.84 M103600200040 13.30 3.00 0.44 M103600200041 13.55 7.14 1.39 M103600200042 13.79 4.24 8.47 M103600200043 14.03 7.69 5.22 M103600200044 14.27 8.07 2.87 M103600200045 14.51 8.94 2.77 M103600200046 14.76 9.27 1.96 M103600200047 15.00 11.21 2.11 M103600200048 15.24 11.28 1.95 M103600200049 15.48 13.62 1.95 M103600200050 15.72 16.29 2.26 M103600200051 15.97 15.56 2.08 M103600200052 16.09 16.84 2.10 M103600200053 16.21 21.51 2.76 M103600200054 16.45 20.27 2.37 M103600200055 16.69 18.50 2.36 M103600200056 16.93 21.53 2.60 M103600200057 17.06 22.83 2.75 M103600200058 17.18 25.45 2.85 M103600200059 17.30 26.70 2.88 M103600200060 17.42 22.59 2.55 M103600200061 17.54 25.04 2.86 M103600200062 17.66 24.07 2.58 M103600200063 17.78 25.34 2.99 M103600200064 17.90 20.65 2.35 M103600200065 18.02 22.14 2.67 M103600200066 18.14 24.91 2.78 M103600200067 18.27 22.40 2.48 M103600200068 18.39 20.82 2.53 M103600200069 18.51 23.33 2.76 M103600200070 18.63 24.78 2.98 M103600200071 18.75 23.53 2.81 M103600200072 18.87 23.85 2.85 M103600200073 19.11 24.17 3.01 M103600200074 19.36 24.98 3.02 M103600200075 19.60 20.75 2.67 M103600200076 19.84 21.04 2.69 M103600200077 20.08 19.04 2.49 M103600200078 20.32 19.98 2.69 M103600200079 20.57 19.75 2.68 M103600200080 20.81 19.14 2.67 M103600200081 21.05 16.87 2.54 M103600200082 21.29 18.08 2.67 M103600200083 21.53 16.92 2.52 M103600200084 21.78 16.18 2.64 M103600200085 22.02 18.65 2.61 M103600200086 22.26 17.01 2.11 M103600200087 22.38 17.27 2.25 M103600200088 22.50 21.95 3.47 M103600200089 22.62 23.15 3.21 M103600200090 22.75 19.77 3.73 M103600200091 22.87 14.19 2.05 M103600200092 22.99 16.41 3.22 M103600200093 23.11 16.72 2.88 M103600200094 23.23 13.25 3.46 M103600200095 23.35 15.49 2.79 M103600200096 23.47 15.29 2.87 M103600200097 23.59 16.36 3.19 M103600200098 23.71 16.42 3.83 M103600200099 23.83 19.24 4.27 M103600200100 23.95 14.12 3.97 M103600200101 24.08 13.51 3.14 M103600200102 24.20 8.16 4.79 M103600200103 24.32 9.28 3.55 M103600200104 24.44 12.65 3.22 M103600200105 24.56 13.39 5.13 M103600200106 24.68 10.58 4.45 M103600200107 24.80 15.84 4.12 M103600200108 24.92 16.16 4.82 M103600200109 25.04 13.55 4.34 M103600200110 25.16 13.19 3.70 M103600200111 25.41 12.93 3.87 M103600200112 25.65 13.65 3.99 M103600200113 25.89 13.56 3.55 M103600200114 26.13 8.64 2.84 M103600200115 26.38 10.47 3.18 M103600200116 26.62 10.61 3.24 M103600200117 26.86 9.80 3.01 M103600200118 27.10 10.60 3.18 M103600200119 27.34 12.48 3.57 M103600200120 27.59 11.01 3.32 M103600200121 27.83 9.84 3.12 M103600200122 28.07 11.41 3.48 M103600200123 28.31 7.99 2.87 M103600200124 28.55 9.67 3.23 M103600200125 28.80 8.88 3.13 M103600200126 29.04 9.94 3.49 M103600200127 29.28 9.47 3.42 M103600200128 29.52 8.42 3.22 M103600200129 29.77 9.76 3.50 M103600200130 30.01 12.52 4.09 M103600200131 30.25 5.54 2.74 M103600200132 30.49 7.66 2.51 M103600200133 30.73 10.80 3.52 M103600200134 30.98 8.16 3.00 M103600200135 31.10 5.73 2.68 M103600200136 31.22 8.90 3.16 M103600200137 31.46 10.21 3.42 M103600200138 31.70 9.72 3.34 M103600200139 32.06 8.23 2.63 M103600200140 32.55 8.03 2.50 M103600200141 33.03 8.33 2.69 M103600200142 33.52 6.18 2.38 M103600200143 ENDDATA 114 0 M103600200144 ENDSUBENT 143 0 M103600299999 SUBENT M1036003 20221019 M121M103600300001 BIB 4 23 M103600300002 REACTION (28-NI-58(G,2N)28-NI-56,,SIG,,,EVAL) M103600300003 ANALYSIS The contribution of partial reaction (g,2n) cross M103600300004 section into the experimental total neutron yield M103600300005 reaction (g,xn) cross section obtained using M103600300006 quasimonoenergetic annihilation photons at Livermore M103600300007 (USA) was evaluated using specially theoretically M103600300008 calculated transitional multiplicity function - M103600300009 ratio M103600300010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M103600300011 by the way M103600300012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M103600300013 REL-REF (R,L0034002,S.C.Fultz+,J,PR/C,10,608,1974) M103600300014 The neutron yield cross section of 58Ni(g,xn) reaction M103600300015 obtained at Livermore. M103600300016 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M103600300017 Theoretical combined model of photonuclear M103600300018 reactions - preequilibrium model based on the Fermi M103600300019 gas densities. M103600300020 STATUS (TABLE) Data presented in Fig. 4d M103600300021 of Phys.Atom.Nucl.85(2022)316. M103600300022 (DEP,L0034002) M103600300023 The neutron yield cross section of 58NI(g,xn) reaction M103600300024 obtained at Livermore. M103600300025 ENDBIB 23 0 M103600300026 NOCOMMON 0 0 M103600300027 DATA 3 54 M103600300028 EN DATA DATA-ERR M103600300029 MEV MB MB M103600300030 22.62 0.01 0.00 M103600300031 22.75 -0.00 0.00 M103600300032 22.87 -0.01 0.00 M103600300033 22.99 -0.01 0.00 M103600300034 23.11 0.01 0.00 M103600300035 23.23 0.01 0.00 M103600300036 23.35 0.04 0.00 M103600300037 23.47 0.05 0.01 M103600300038 23.59 0.08 0.02 M103600300039 23.71 0.10 0.03 M103600300040 23.83 0.15 0.04 M103600300041 23.95 0.14 0.04 M103600300042 24.08 0.15 0.04 M103600300043 24.20 0.11 0.06 M103600300044 24.32 0.14 0.05 M103600300045 24.44 0.20 0.05 M103600300046 24.56 0.23 0.09 M103600300047 24.68 0.20 0.08 M103600300048 24.80 0.31 0.08 M103600300049 24.92 0.33 0.10 M103600300050 25.04 0.29 0.09 M103600300051 25.16 0.29 0.08 M103600300052 25.41 0.29 0.09 M103600300053 25.65 0.32 0.10 M103600300054 25.89 0.32 0.09 M103600300055 26.13 0.21 0.07 M103600300056 26.38 0.25 0.08 M103600300057 26.62 0.25 0.08 M103600300058 26.86 0.24 0.07 M103600300059 27.10 0.26 0.08 M103600300060 27.34 0.30 0.09 M103600300061 27.59 0.27 0.08 M103600300062 27.83 0.24 0.08 M103600300063 28.07 0.29 0.09 M103600300064 28.31 0.20 0.07 M103600300065 28.55 0.25 0.08 M103600300066 28.80 0.23 0.08 M103600300067 29.04 0.26 0.09 M103600300068 29.28 0.25 0.09 M103600300069 29.52 0.23 0.09 M103600300070 29.77 0.27 0.10 M103600300071 30.01 0.36 0.12 M103600300072 30.25 0.16 0.08 M103600300073 30.49 0.23 0.08 M103600300074 30.73 0.33 0.11 M103600300075 30.98 0.25 0.09 M103600300076 31.10 0.18 0.08 M103600300077 31.22 0.28 0.10 M103600300078 31.46 0.33 0.11 M103600300079 31.70 0.32 0.11 M103600300080 32.06 0.28 0.09 M103600300081 32.55 0.28 0.09 M103600300082 33.03 0.30 0.10 M103600300083 33.52 0.23 0.09 M103600300084 ENDDATA 56 0 M103600300085 ENDSUBENT 84 0 M103600399999 SUBENT M1036004 20221019 M121M103600400001 BIB 3 11 M103600400002 REACTION (28-NI-58(G,X)0-NN-1,UNW,SIG,,,EVAL) M103600400003 ANALYSIS The cross section of the total neutron reaction M103600400004 SIGMA(g,tot) = SIGMA(g,1n)+SIGMA(G,1n1p)+SIGMA(g,2n) M103600400005 was obtained as the sum of SIGMA of the correspondent M103600400006 partial reactions. M103600400007 STATUS (TABLE) Data presented in Fig. 4b M103600400008 of Phys.Atom.Nucl.85(2022)316. M103600400009 (DEP,M1036002) M103600400010 The cross section of the reaction (g,1n)+(g,1n1p). M103600400011 (DEP,M1036003) M103600400012 The cross section of the reaction (g,2n). M103600400013 ENDBIB 11 0 M103600400014 NOCOMMON 0 0 M103600400015 DATA 3 112 M103600400016 EN DATA DATA-ERR M103600400017 MEV MB MB M103600400018 12.21 2.14 1.09 M103600400019 12.34 5.50 1.03 M103600400020 12.46 3.71 1.07 M103600400021 12.58 3.17 1.22 M103600400022 12.70 5.18 1.16 M103600400023 12.82 8.15 1.47 M103600400024 12.94 5.24 1.10 M103600400025 13.06 8.02 1.18 M103600400026 13.18 5.67 0.84 M103600400027 13.30 3.00 0.44 M103600400028 13.55 7.14 1.39 M103600400029 13.79 4.24 8.47 M103600400030 14.03 7.69 5.22 M103600400031 14.27 8.07 2.87 M103600400032 14.51 8.94 2.77 M103600400033 14.76 9.27 1.96 M103600400034 15.00 11.21 2.11 M103600400035 15.24 11.28 1.95 M103600400036 15.48 13.62 1.95 M103600400037 15.72 16.29 2.26 M103600400038 15.97 15.56 2.08 M103600400039 16.09 16.84 2.10 M103600400040 16.21 21.51 2.76 M103600400041 16.45 20.27 2.37 M103600400042 16.69 18.50 2.36 M103600400043 16.93 21.53 2.60 M103600400044 17.06 22.83 2.75 M103600400045 17.18 25.45 2.85 M103600400046 17.30 26.70 2.88 M103600400047 17.42 22.59 2.55 M103600400048 17.54 25.04 2.86 M103600400049 17.66 24.07 2.58 M103600400050 17.78 25.34 2.99 M103600400051 17.90 20.65 2.35 M103600400052 18.02 22.14 2.67 M103600400053 18.14 24.91 2.78 M103600400054 18.27 22.40 2.48 M103600400055 18.39 20.82 2.53 M103600400056 18.51 23.33 2.76 M103600400057 18.63 24.78 2.98 M103600400058 18.75 23.53 2.81 M103600400059 18.87 23.85 2.85 M103600400060 19.11 24.17 3.01 M103600400061 19.36 24.98 3.02 M103600400062 19.60 20.75 2.67 M103600400063 19.84 21.04 2.69 M103600400064 20.08 19.04 2.49 M103600400065 20.32 19.98 2.69 M103600400066 20.57 19.75 2.68 M103600400067 20.81 19.14 2.67 M103600400068 21.05 16.87 2.54 M103600400069 21.29 18.08 2.67 M103600400070 21.53 16.92 2.52 M103600400071 21.78 16.18 2.64 M103600400072 22.02 18.65 2.61 M103600400073 22.26 17.01 2.11 M103600400074 22.38 17.27 2.25 M103600400075 22.50 21.96 3.47 M103600400076 22.62 23.16 3.21 M103600400077 22.75 19.76 3.73 M103600400078 22.87 14.19 2.05 M103600400079 22.99 16.39 3.22 M103600400080 23.11 16.73 2.88 M103600400081 23.23 13.27 3.46 M103600400082 23.35 15.53 2.79 M103600400083 23.47 15.34 2.87 M103600400084 23.59 16.43 3.19 M103600400085 23.71 16.53 3.83 M103600400086 23.83 19.39 4.27 M103600400087 23.95 14.25 3.97 M103600400088 24.08 13.67 3.14 M103600400089 24.20 8.26 4.79 M103600400090 24.32 9.41 3.55 M103600400091 24.44 12.86 3.22 M103600400092 24.56 13.62 5.14 M103600400093 24.68 10.77 4.45 M103600400094 24.80 16.15 4.13 M103600400095 24.92 16.49 4.82 M103600400096 25.04 13.84 4.34 M103600400097 25.16 13.48 3.70 M103600400098 25.41 13.22 3.88 M103600400099 25.65 13.97 3.99 M103600400100 25.89 13.88 3.55 M103600400101 26.13 8.84 2.84 M103600400102 26.38 10.73 3.19 M103600400103 26.62 10.86 3.24 M103600400104 26.86 10.03 3.01 M103600400105 27.10 10.86 3.18 M103600400106 27.34 12.79 3.57 M103600400107 27.59 11.28 3.32 M103600400108 27.83 10.09 3.13 M103600400109 28.07 11.69 3.48 M103600400110 28.31 8.20 2.88 M103600400111 28.55 9.92 3.24 M103600400112 28.80 9.11 3.13 M103600400113 29.04 10.20 3.49 M103600400114 29.28 9.73 3.42 M103600400115 29.52 8.65 3.22 M103600400116 29.77 10.03 3.50 M103600400117 30.01 12.87 4.09 M103600400118 30.25 5.70 2.74 M103600400119 30.49 7.89 2.51 M103600400120 30.73 11.13 3.52 M103600400121 30.98 8.42 3.00 M103600400122 31.10 5.91 2.68 M103600400123 31.22 9.18 3.17 M103600400124 31.46 10.54 3.43 M103600400125 31.70 10.04 3.34 M103600400126 32.06 8.51 2.63 M103600400127 32.55 8.31 2.50 M103600400128 33.03 8.64 2.70 M103600400129 33.52 6.41 2.38 M103600400130 ENDDATA 114 0 M103600400131 ENDSUBENT 130 0 M103600499999 SUBENT M1036005 20221019 M121M103600500001 BIB 3 5 M103600500002 REACTION (28-NI-58(G,X)0-NN-1,UNW,INT,,,DERIV) M103600500003 ANALYSIS Integration of evaluated cross section. M103600500004 STATUS (DEP,M1036004) M103600500005 Evaluated reaction cross section. M103600500006 (TABLE) Data from Table 2. M103600500007 ENDBIB 5 0 M103600500008 NOCOMMON 0 0 M103600500009 DATA 3 29 M103600500010 EN-MAX DATA DATA-ERR M103600500011 MEV MB*MEV MB*MEV M103600500012 22.5 167.41 14.33 M103600500013 33.5 290.82 14.81 M103600500014 ENDDATA 4 0 M103600500015 ENDSUBENT 14 0 M103600599999 SUBENT M1036006 20221019 M121M103600600001 BIB 3 6 M103600600002 REACTION ((28-NI-58(G,N)28-NI-57,,INT,,,DERIV)+ M103600600003 (28-NI-58(G,N+P)27-CO-56,,INT,,,DERIV)) M103600600004 ANALYSIS Integration of evaluated cross section. M103600600005 STATUS (DEP,M1036002) M103600600006 Evaluated reaction cross section. M103600600007 (TABLE) Data from Table 2. M103600600008 ENDBIB 6 0 M103600600009 NOCOMMON 0 0 M103600600010 DATA 3 29 M103600600011 EN-MAX DATA DATA-ERR M103600600012 MEV MB*MEV MB*MEV M103600600013 22.5 167.41 14.33 M103600600014 33.5 288.25 14.81 M103600600015 ENDDATA 4 0 M103600600016 ENDSUBENT 15 0 M103600699999 SUBENT M1036007 20221019 M121M103600700001 BIB 3 5 M103600700002 REACTION (28-NI-58(G,2N)28-NI-56,,INT,,,DERIV) M103600700003 ANALYSIS Integration of evaluated cross section. M103600700004 STATUS (DEP,M1036003) M103600700005 Evaluated reaction cross section. M103600700006 (TABLE) Data from Table 2. M103600700007 ENDBIB 5 0 M103600700008 NOCOMMON 0 0 M103600700009 DATA 3 19 M103600700010 EN-MAX DATA DATA-ERR M103600700011 MEV MB*MEV MB*MEV M103600700012 33.5 2.57 0.10 M103600700013 ENDDATA 3 0 M103600700014 ENDSUBENT 13 0 M103600799999 ENDENTRY 7 0 M103699999999