ENTRY M0920 20160322 M082M092000000001 SUBENT M0920001 20160322 M082M092000100001 BIB 9 33 M092000100002 TITLE Reliability of the data on the cross sections of the M092000100003 partial photoneutron reaction for 63,65Cu and 80Se M092000100004 Nuclei. M092000100005 AUTHOR (V.V.Varlamov,A.I.Davydov,M.A.Makarov,V.N.Orlin, M092000100006 N.N.Peskov) M092000100007 REFERENCE (J,IZV,80,(3),351,2016) M092000100008 #doi:10.7868/S0367676516030339 M092000100009 (J,BAS,80,(3),317,2016) M092000100010 #doi:10.3103/S1062873816030333 M092000100011 English translation of IZV,80,(3),351,2016. M092000100012 INSTITUTE (4RUSMOS) M092000100013 INC-SOURCE (QMPH,ARAD) M092000100014 ANALYSIS The joint analysis of data for total (g,xn) and M092000100015 partial (g,n), (g,2n) and (g,3n) reactions obtained M092000100016 in various experiments was carried out. The new M092000100017 approach to analysis of systematic disagreements M092000100018 between data was proposed on the base of new M092000100019 criteria of systematic uncertainties presence - M092000100020 specially proposed transitional multiplicity M092000100021 functions M092000100022 Fi-theor = SIG(g,in)/SIG(g,xn). M092000100023 Using these functions calculated in the frame of M092000100024 combined photonuclear reaction model new reliable M092000100025 and free from problems of neutron multiplicity M092000100026 sorting data for photoneutron partial reactions M092000100027 cross sections M092000100028 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M092000100029 were evaluated using experimental neutron yield M092000100030 reaction cross sections SIG-exp(g,xn). M092000100031 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M092000100032 STATUS (TABLE,APRVD) Approved by V.Varlamov. M092000100033 HISTORY (20160322C) Data were compiled at the Russia MSU SINP M092000100034 CDFE by V.Varlamov. M092000100035 ENDBIB 33 0 M092000100036 NOCOMMON 0 0 M092000100037 ENDSUBENT 36 0 M092000199999 SUBENT M0920002 20160322 M082M092000200001 BIB 3 8 M092000200002 REACTION (29-CU-63(G,X)0-NN-1,UNW,SIG,,,EVAL) M092000200003 ANALYSIS The total neutron reaction cross section obtained as M092000200004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M092000200005 STATUS Data plotted in Fig. 3. M092000200006 (DEP,M0920003) M092000200007 Evaluated (g,n) reaction cross section. M092000200008 (DEP,M0920004) M092000200009 Evaluated (g,2n) reaction cross section. M092000200010 ENDBIB 8 0 M092000200011 NOCOMMON 0 0 M092000200012 DATA 3 61 M092000200013 EN DATA DATA-ERR M092000200014 MEV MB MB M092000200015 10.26 4.0 1.3 M092000200016 10.56 1.0 1.3 M092000200017 10.87 5.5 1.2 M092000200018 11.18 5.4 1.1 M092000200019 11.49 7.2 1.3 M092000200020 11.64 3.0 2.0 M092000200021 11.79 15.2 2.6 M092000200022 11.95 12.2 2.4 M092000200023 12.10 17.8 3.1 M092000200024 12.25 14.0 2.7 M092000200025 12.41 17.0 2.6 M092000200026 12.71 19.2 3.0 M092000200027 13.02 22.5 3.3 M092000200028 13.33 22.8 3.4 M092000200029 13.64 28.5 4.2 M092000200030 13.94 32.4 4.7 M092000200031 14.25 36.8 5.3 M092000200032 14.56 43.5 6.2 M092000200033 14.87 46.5 6.6 M092000200034 15.17 52.0 7.4 M092000200035 15.48 58.5 8.3 M092000200036 15.79 65.1 9.2 M092000200037 16.1 69.5 10.0 M092000200038 16.40 69.6 9.9 M092000200039 16.71 68.8 9.8 M092000200040 17.02 66.5 9.4 M092000200041 17.32 60.6 8.6 M092000200042 17.63 57.4 8.2 M092000200043 17.94 60.6 8.6 M092000200044 18.25 51.5 7.4 M092000200045 18.55 56.7 8.1 M092000200046 18.86 52.5 7.6 M092000200047 19.17 54.5 7.8 M092000200048 19.48 44.0 6.8 M092000200049 19.78 48.4 7.0 M092000200050 20.09 46.6 7.5 M092000200051 20.40 43.5 6.5 M092000200052 20.70 43.1 6.5 M092000200053 21.01 45.6 6.2 M092000200054 21.32 39.3 6.1 M092000200055 21.63 43.3 5.9 M092000200056 21.93 39.0 6.0 M092000200057 22.24 44.4 5.8 M092000200058 22.55 42.8 6.4 M092000200059 22.86 45.5 5.8 M092000200060 23.16 38.8 5.2 M092000200061 23.47 39.8 5.1 M092000200062 23.78 33.6 4.7 M092000200063 24.08 35.1 4.6 M092000200064 24.39 29.5 4.3 M092000200065 24.70 29.1 3.8 M092000200066 25.01 29.8 4.6 M092000200067 25.31 27.5 4.6 M092000200068 25.62 26.1 4.9 M092000200069 25.93 26.2 4.1 M092000200070 26.24 20.1 4.6 M092000200071 26.54 20.0 4.7 M092000200072 26.85 16.7 4.6 M092000200073 27.16 15.6 3.7 M092000200074 27.47 11.2 4.3 M092000200075 27.77 9.2 3.7 M092000200076 ENDDATA 63 0 M092000200077 ENDSUBENT 76 0 M092000299999 SUBENT M0920003 20160322 M082M092000300001 BIB 4 22 M092000300002 REACTION ((29-CU-63(G,N)29-CU-62,,SIG,,,EVAL)+ M092000300003 (29-CU-63(G,N+P)28-NI-61,,SIG,,,EVAL)) M092000300004 ANALYSIS The contribution of partial reaction (g,n) cross M092000300005 section into the experimental total neutron yield M092000300006 reaction (g,xn) cross section obtained using M092000300007 quasimonoenergetic annihilation photons at Livermore M092000300008 (USA) was evaluated using specially theoretically M092000300009 calculated transitional multiplicity function - M092000300010 ratio M092000300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092000300012 by the way M092000300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M092000300014 REL-REF (R,L0006005,S.C.Fultz+,J,PR,133,B1149,1964) M092000300015 Experimental data for the total neutron yield M092000300016 reaction (g,xn)= (g,n) + 2(g,2n) cross section. M092000300017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092000300018 Theoretical preequilibrium model of photonuclear M092000300019 reactions based on the Fermi gas densities. M092000300020 STATUS Data plotted in Fig. 3. M092000300021 (DEP,L0006005) M092000300022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092000300023 cross section. M092000300024 ENDBIB 22 0 M092000300025 NOCOMMON 0 0 M092000300026 DATA 3 61 M092000300027 EN DATA DATA-ERR M092000300028 MEV MB MB M092000300029 10.261 4.0 1.3 M092000300030 10.568 1.0 1.3 M092000300031 10.876 5.5 1.2 M092000300032 11.183 5.4 1.1 M092000300033 11.49 7.2 1.3 M092000300034 11.644 3.0 2.0 M092000300035 11.797 15.2 2.6 M092000300036 11.951 12.2 2.4 M092000300037 12.105 17.8 3.1 M092000300038 12.258 14.0 2.7 M092000300039 12.412 17.0 2.6 M092000300040 12.719 19.2 3.0 M092000300041 13.027 22.5 3.3 M092000300042 13.334 22.8 3.4 M092000300043 13.641 28.5 4.2 M092000300044 13.949 32.4 4.7 M092000300045 14.256 36.8 5.3 M092000300046 14.563 43.5 6.2 M092000300047 14.87 46.5 6.6 M092000300048 15.178 52.0 7.4 M092000300049 15.485 58.5 8.3 M092000300050 15.792 65.1 9.2 M092000300051 16.1 69.5 10.0 M092000300052 16.407 69.6 9.9 M092000300053 16.714 68.8 9.8 M092000300054 17.022 66.5 9.4 M092000300055 17.329 60.6 8.6 M092000300056 17.636 57.4 8.2 M092000300057 17.943 60.6 8.6 M092000300058 18.251 51.5 7.4 M092000300059 18.558 56.7 8.1 M092000300060 18.865 52.5 7.6 M092000300061 19.173 54.5 7.8 M092000300062 19.48 44.0 6.8 M092000300063 19.787 48.4 7.0 M092000300064 20.095 46.4 7.5 M092000300065 20.402 42.6 6.5 M092000300066 20.709 41.3 6.5 M092000300067 21.016 42.4 6.2 M092000300068 21.324 35.5 6.1 M092000300069 21.631 38.0 5.9 M092000300070 21.938 33.3 5.9 M092000300071 22.246 37.1 5.7 M092000300072 22.553 35.1 6.3 M092000300073 22.86 36.8 5.6 M092000300074 23.168 31.0 5.1 M092000300075 23.475 31.6 5.0 M092000300076 23.782 26.5 4.5 M092000300077 24.089 27.6 4.5 M092000300078 24.397 23.2 4.1 M092000300079 24.704 22.9 3.7 M092000300080 25.011 23.5 4.5 M092000300081 25.319 21.8 4.4 M092000300082 25.626 20.8 4.8 M092000300083 25.933 21.1 4.0 M092000300084 26.241 16.3 4.5 M092000300085 26.548 16.3 4.6 M092000300086 26.855 13.7 4.5 M092000300087 27.162 12.8 3.6 M092000300088 27.47 9.2 4.2 M092000300089 27.777 7.6 3.6 M092000300090 ENDDATA 63 0 M092000300091 ENDSUBENT 90 0 M092000399999 SUBENT M0920004 20160322 M082M092000400001 BIB 4 22 M092000400002 REACTION ((29-CU-63(G,2N)29-CU-61,,SIG,,,EVAL)+ M092000400003 (29-CU-63(G,2N+P)28-NI-60,,SIG,,,EVAL)) M092000400004 ANALYSIS The contribution of partial reaction (g,n) cross M092000400005 section into the experimental total neutron yield M092000400006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M092000400007 obtained using quasimonoenergetic annihilation M092000400008 photons at Livermore (USA) was evaluated using M092000400009 specially theoretically calculated transitional M092000400010 multiplicity function - ratio M092000400011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092000400012 by the way M092000400013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092000400014 REL-REF (R,L0006005,S.C.Fultz+,J,PR,133,B1149,1964) M092000400015 Experimental data for the total neutron yield M092000400016 reaction (g,xn) cross section. M092000400017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092000400018 Theoretical preequilibrium model of photonuclear M092000400019 reactions based on the Fermi gas densities. M092000400020 STATUS Data plotted in Fig. 3. M092000400021 (DEP,L0006005) M092000400022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092000400023 cross section. M092000400024 ENDBIB 22 0 M092000400025 NOCOMMON 0 0 M092000400026 DATA 3 26 M092000400027 EN DATA DATA-ERR M092000400028 MEV MB MB M092000400029 20.09 0.23 0.03 M092000400030 20.40 0.87 0.13 M092000400031 20.70 1.84 0.29 M092000400032 21.01 3.17 0.46 M092000400033 21.32 3.82 0.65 M092000400034 21.63 5.30 0.82 M092000400035 21.93 5.65 1.01 M092000400036 22.24 7.26 1.12 M092000400037 22.55 7.65 1.37 M092000400038 22.86 8.70 1.33 M092000400039 23.16 7.77 1.28 M092000400040 23.47 8.23 1.30 M092000400041 23.78 7.10 1.21 M092000400042 24.08 7.50 1.22 M092000400043 24.39 6.31 1.13 M092000400044 24.70 6.17 1.00 M092000400045 25.01 6.26 1.19 M092000400046 25.31 5.69 1.17 M092000400047 25.62 5.29 1.22 M092000400048 25.93 5.14 0.98 M092000400049 26.24 3.80 1.04 M092000400050 26.54 3.69 1.05 M092000400051 26.85 3.03 1.01 M092000400052 27.16 2.77 0.79 M092000400053 27.47 1.96 0.90 M092000400054 27.77 1.58 0.76 M092000400055 ENDDATA 28 0 M092000400056 ENDSUBENT 55 0 M092000499999 SUBENT M0920005 20160322 M082M092000500001 BIB 3 8 M092000500002 REACTION (29-CU-65(G,X)0-NN-1,UNW,SIG,,,EVAL) M092000500003 ANALYSIS The total neutron reaction cross section obtained as M092000500004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M092000500005 STATUS Data plotted in Fig. 4. M092000500006 (DEP,M0920006) M092000500007 Evaluated (g,n) reaction cross section. M092000500008 (DEP,M0920007) M092000500009 Evaluated (g,2n) reaction cross section. M092000500010 ENDBIB 8 0 M092000500011 NOCOMMON 0 0 M092000500012 DATA 3 79 M092000500013 EN DATA DATA-ERR M092000500014 MEV MB MB M092000500015 9.33 -0.6 1.8 M092000500016 9.64 0.3 2.1 M092000500017 9.95 4.8 2.1 M092000500018 10.26 6.8 2.0 M092000500019 10.56 10.7 2.5 M092000500020 10.87 7.0 2.9 M092000500021 11.18 11.6 4.3 M092000500022 11.49 15.1 4.7 M092000500023 11.79 22.0 4.4 M092000500024 12.10 20.7 4.4 M092000500025 12.41 19.4 3.9 M092000500026 12.71 23.6 4.5 M092000500027 13.02 29.1 5.2 M092000500028 13.33 31.6 5.5 M092000500029 13.64 35.4 5.8 M092000500030 13.94 39.3 6.4 M092000500031 14.25 45.4 7.2 M092000500032 14.56 49.9 7.6 M092000500033 14.87 57.7 8.8 M092000500034 15.17 63.8 9.8 M092000500035 15.48 67.5 10.3 M092000500036 15.79 69.8 10.1 M092000500037 16.1 72.1 10.6 M092000500038 16.25 73.5 10.8 M092000500039 16.40 75.2 11.0 M092000500040 16.56 74.5 10.8 M092000500041 16.71 77.4 11.2 M092000500042 16.86 75.4 11.0 M092000500043 17.02 77.0 11.2 M092000500044 17.17 74.6 11.0 M092000500045 17.32 75.3 11.1 M092000500046 17.48 70.3 10.3 M092000500047 17.63 66.6 9.9 M092000500048 17.79 68.5 10.3 M092000500049 17.94 70.9 10.5 M092000500050 18.09 66.0 9.9 M092000500051 18.25 63.6 9.6 M092000500052 18.40 61.4 9.3 M092000500053 18.55 68.6 10.0 M092000500054 18.71 66.1 9.4 M092000500055 18.86 63.6 8.9 M092000500056 19.01 58.4 8.0 M092000500057 19.17 57.5 7.6 M092000500058 19.32 60.0 7.5 M092000500059 19.48 60.2 7.3 M092000500060 19.63 58.2 7.1 M092000500061 19.78 58.9 6.9 M092000500062 19.94 57.0 6.4 M092000500063 20.09 52.7 6.2 M092000500064 20.24 50.7 5.7 M092000500065 20.40 49.6 5.5 M092000500066 20.55 48.4 5.3 M092000500067 20.70 47.8 5.3 M092000500068 20.86 45.3 5.0 M092000500069 21.01 45.7 5.6 M092000500070 21.17 43.7 4.9 M092000500071 21.32 44.2 6.0 M092000500072 21.47 45.2 5.0 M092000500073 21.63 43.0 5.5 M092000500074 21.78 43.3 5.0 M092000500075 21.93 39.2 5.2 M092000500076 22.09 37.9 4.4 M092000500077 22.24 36.4 5.0 M092000500078 22.39 37.8 4.4 M092000500079 22.55 36.6 5.1 M092000500080 22.70 36.6 4.3 M092000500081 22.86 34.2 4.8 M092000500082 23.01 34.4 4.2 M092000500083 23.16 34.0 4.8 M092000500084 23.47 30.2 4.2 M092000500085 23.78 24.1 4.0 M092000500086 24.08 23.3 4.1 M092000500087 24.39 22.8 4.7 M092000500088 24.70 19.1 4.5 M092000500089 25.31 18.6 4.9 M092000500090 25.93 15.9 4.1 M092000500091 26.54 21.2 4.8 M092000500092 27.16 18.3 4.2 M092000500093 27.77 16.2 5.8 M092000500094 ENDDATA 81 0 M092000500095 ENDSUBENT 94 0 M092000599999 SUBENT M0920006 20160322 M082M092000600001 BIB 4 22 M092000600002 REACTION ((29-CU-65(G,N)29-CU-64,,SIG,,,EVAL)+ M092000600003 (29-CU-65(G,N+P)28-NI-63,,SIG,,,EVAL)) M092000600004 ANALYSIS The contribution of partial reaction (g,n) cross M092000600005 section into the experimental total neutron yield M092000600006 reaction (g,xn) cross section obtained using M092000600007 quasimonoenergetic annihilation photons at Livermore M092000600008 (USA) was evaluated using specially theoretically M092000600009 calculated transitional multiplicity function - M092000600010 ratio M092000600011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092000600012 by the way M092000600013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M092000600014 REL-REF (R,L0006008,S.C.Fultz+,J,PR,133,B1149,1964) M092000600015 Experimental data for the total neutron yield M092000600016 reaction (g,xn)= (g,n) + 2(g,2n) cross section. M092000600017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092000600018 Theoretical preequilibrium model of photonuclear M092000600019 reactions based on the Fermi gas densities. M092000600020 STATUS Data plotted in Fig. 4. M092000600021 (DEP,L0006008) M092000600022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092000600023 cross section. M092000600024 ENDBIB 22 0 M092000600025 NOCOMMON 0 0 M092000600026 DATA 3 79 M092000600027 EN DATA DATA-ERR M092000600028 MEV MB MB M092000600029 9.33 -0.6 1.8 M092000600030 9.64 0.3 2.1 M092000600031 9.95 4.8 2.1 M092000600032 10.26 6.8 2.0 M092000600033 10.56 10.7 2.5 M092000600034 10.87 7.0 2.9 M092000600035 11.18 11.6 4.3 M092000600036 11.49 15.1 4.7 M092000600037 11.79 22.0 4.4 M092000600038 12.10 20.7 4.4 M092000600039 12.41 19.4 3.9 M092000600040 12.71 23.6 4.5 M092000600041 13.02 29.1 5.2 M092000600042 13.33 31.6 5.5 M092000600043 13.64 35.4 5.8 M092000600044 13.94 39.3 6.4 M092000600045 14.25 45.4 7.2 M092000600046 14.56 49.9 7.6 M092000600047 14.87 57.7 8.8 M092000600048 15.17 63.8 9.8 M092000600049 15.48 67.5 10.3 M092000600050 15.79 69.8 10.1 M092000600051 16.1 72.1 10.6 M092000600052 16.25 73.5 10.8 M092000600053 16.40 75.2 11.0 M092000600054 16.56 74.5 10.8 M092000600055 16.71 77.4 11.2 M092000600056 16.86 75.4 11.0 M092000600057 17.02 77.0 11.2 M092000600058 17.17 74.6 11.0 M092000600059 17.32 75.3 11.1 M092000600060 17.48 70.3 10.3 M092000600061 17.63 66.6 9.99 M092000600062 17.79 68.5 10.3 M092000600063 17.94 70.9 10.5 M092000600064 18.09 66.0 9.9 M092000600065 18.25 62.8 9.6 M092000600066 18.40 59.7 9.3 M092000600067 18.55 65.1 10.0 M092000600068 18.71 61.1 9.4 M092000600069 18.86 56.9 8.9 M092000600070 19.01 50.4 7.9 M092000600071 19.17 47.8 7.4 M092000600072 19.32 47.9 7.3 M092000600073 19.48 46.1 7.0 M092000600074 19.63 42.7 6.7 M092000600075 19.78 41.5 6.4 M092000600076 19.94 38.5 5.7 M092000600077 20.09 34.3 5.4 M092000600078 20.24 31.7 4.8 M092000600079 20.40 29.9 4.6 M092000600080 20.55 28.1 4.3 M092000600081 20.70 26.9 4.2 M092000600082 20.86 24.7 3.8 M092000600083 21.01 24.2 4.2 M092000600084 21.17 22.6 3.5 M092000600085 21.32 22.4 4.3 M092000600086 21.47 22.5 3.5 M092000600087 21.63 21.1 3.8 M092000600088 21.78 21.0 3.4 M092000600089 21.93 18.9 3.5 M092000600090 22.09 18.2 3.0 M092000600091 22.24 17.5 3.4 M092000600092 22.39 18.3 3.0 M092000600093 22.55 17.8 3.5 M092000600094 22.70 18.0 3.0 M092000600095 22.86 17.0 3.4 M092000600096 23.01 17.4 3.0 M092000600097 23.16 17.4 3.4 M092000600098 23.47 16.0 3.1 M092000600099 23.78 13.2 3.1 M092000600100 24.08 13.1 3.2 M092000600101 24.39 13.2 3.8 M092000600102 24.70 11.2 3.7 M092000600103 25.31 11.3 4.1 M092000600104 25.93 9.8 3.5 M092000600105 26.54 13.0 4.0 M092000600106 27.16 11.1 3.5 M092000600107 27.77 9.6 4.8 M092000600108 ENDDATA 81 0 M092000600109 ENDSUBENT 108 0 M092000699999 SUBENT M0920007 20160322 M082M092000700001 BIB 4 22 M092000700002 REACTION ((29-CU-65(G,2N)29-CU-63,,SIG,,,EVAL)+ M092000700003 (29-CU-65(G,2N+P)28-NI-62,,SIG,,,EVAL)) M092000700004 ANALYSIS The contribution of partial reaction (g,n) cross M092000700005 section into the experimental total neutron yield M092000700006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M092000700007 obtained using quasimonoenergetic annihilation M092000700008 photons at Livermore (USA) was evaluated using M092000700009 specially theoretically calculated transitional M092000700010 multiplicity function - ratio M092000700011 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092000700012 by the way M092000700013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092000700014 REL-REF (R,L0006008,S.C.Fultz+,J,PR,133,B1149,1964) M092000700015 Experimental data for the total neutron yield M092000700016 reaction (g,xn)= (g,n) + 2(g,2n)cross section. M092000700017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092000700018 Theoretical preequilibrium model of photonuclear M092000700019 reactions based on the Fermi gas densities. M092000700020 STATUS Data plotted in Fig. 4. M092000700021 (DEP,L0006008) M092000700022 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092000700023 cross section. M092000700024 ENDBIB 22 0 M092000700025 NOCOMMON 0 0 M092000700026 DATA 3 43 M092000700027 EN DATA DATA-ERR M092000700028 MEV MB MB M092000700029 18.25 0.82 0.12 M092000700030 18.40 1.67 0.26 M092000700031 18.55 3.46 0.53 M092000700032 18.71 4.99 0.77 M092000700033 18.86 6.70 1.04 M092000700034 19.01 7.98 1.25 M092000700035 19.17 9.73 1.51 M092000700036 19.32 12.13 1.86 M092000700037 19.48 14.08 2.14 M092000700038 19.63 15.48 2.43 M092000700039 19.78 17.36 2.69 M092000700040 19.94 18.45 2.76 M092000700041 20.09 18.43 2.93 M092000700042 20.24 19.02 2.93 M092000700043 20.40 19.72 3.05 M092000700044 20.55 20.27 3.12 M092000700045 20.70 20.92 3.30 M092000700046 20.86 20.62 3.23 M092000700047 21.01 21.50 3.76 M092000700048 21.17 21.09 3.35 M092000700049 21.32 21.79 4.23 M092000700050 21.47 22.68 3.60 M092000700051 21.63 21.92 3.99 M092000700052 21.78 22.30 3.69 M092000700053 21.93 20.32 3.82 M092000700054 22.09 19.67 3.25 M092000700055 22.24 18.91 3.73 M092000700056 22.39 19.52 3.23 M092000700057 22.55 18.75 3.72 M092000700058 22.70 18.56 3.09 M092000700059 22.86 17.20 3.45 M092000700060 23.01 17.04 2.94 M092000700061 23.16 16.60 3.31 M092000700062 23.47 14.23 2.83 M092000700063 23.78 10.93 2.58 M092000700064 24.08 10.20 2.51 M092000700065 24.39 9.64 2.78 M092000700066 24.70 7.86 2.60 M092000700067 25.31 7.33 2.71 M092000700068 25.93 6.09 2.19 M092000700069 26.54 8.18 2.55 M092000700070 27.16 7.23 2.29 M092000700071 27.77 6.56 3.27 M092000700072 ENDDATA 45 0 M092000700073 ENDSUBENT 72 0 M092000799999 SUBENT M0920008 20160322 M082M092000800001 BIB 3 8 M092000800002 REACTION (34-SE-80(G,X)0-NN-1,UNW,SIG,,,EVAL) M092000800003 ANALYSIS The total neutron reaction cross section obtained as M092000800004 sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n). M092000800005 STATUS Data plotted in Fig. 5. M092000800006 (DEP,M0920009) M092000800007 Evaluated (g,n) reaction cross section. M092000800008 (DEP,M0920010) M092000800009 Evaluated (g,2n) reaction cross section. M092000800010 ENDBIB 8 0 M092000800011 NOCOMMON 0 0 M092000800012 DATA 3 68 M092000800013 EN DATA DATA-ERR M092000800014 MEV MB MB M092000800015 9.92 0.3 4.0 M092000800016 10.2 18.1 4.0 M092000800017 10.47 23.8 4.1 M092000800018 10.74 12.5 4.1 M092000800019 11.01 18.0 4.2 M092000800020 11.28 33.1 4.3 M092000800021 11.55 26.4 4.3 M092000800022 11.82 29.3 4.4 M092000800023 12.09 33.2 4.4 M092000800024 12.36 30.4 4.5 M092000800025 12.63 38.4 4.6 M092000800026 12.91 43.6 4.6 M092000800027 13.18 51.1 4.7 M092000800028 13.45 63.2 4.7 M092000800029 13.72 74.5 4.8 M092000800030 13.99 77.9 4.9 M092000800031 14.26 91.8 4.9 M092000800032 14.53 102.3 5.0 M092000800033 14.8 108.7 5.0 M092000800034 15.07 114.4 5.1 M092000800035 15.34 123.0 5.1 M092000800036 15.62 129.8 5.2 M092000800037 15.89 137.0 5.3 M092000800038 16.16 135.2 5.3 M092000800039 16.43 140.8 6.4 M092000800040 16.7 135.0 6.5 M092000800041 16.97 125.9 6.6 M092000800042 17.24 127.6 6.7 M092000800043 17.51 132.5 6.7 M092000800044 17.78 125.5 6.8 M092000800045 18.05 117.3 6.9 M092000800046 18.33 107.5 7.0 M092000800047 18.6 114.5 7.1 M092000800048 18.87 99.1 7.1 M092000800049 19.14 98.0 7.2 M092000800050 19.41 95.7 7.3 M092000800051 19.68 83.1 7.4 M092000800052 19.95 83.5 7.5 M092000800053 20.22 79.9 7.6 M092000800054 20.49 71.9 7.6 M092000800055 20.76 73.5 7.7 M092000800056 21.04 72.0 7.8 M092000800057 21.31 66.2 7.9 M092000800058 21.58 69.7 8.0 M092000800059 21.85 61.2 8.1 M092000800060 22.12 55.1 8.1 M092000800061 22.39 60.0 8.2 M092000800062 22.66 52.3 8.3 M092000800063 22.93 50.8 8.4 M092000800064 23.2 45.2 8.5 M092000800065 23.47 44.9 8.5 M092000800066 23.75 44.1 8.6 M092000800067 24.02 40.5 8.7 M092000800068 24.29 36.1 8.8 M092000800069 24.56 41.1 8.9 M092000800070 24.83 29.4 9.0 M092000800071 25.1 34.4 9.0 M092000800072 25.37 29.2 9.1 M092000800073 25.64 32.2 9.2 M092000800074 25.91 24.4 9.3 M092000800075 26.18 31.8 9.4 M092000800076 26.46 23.4 9.5 M092000800077 26.73 24.5 9.5 M092000800078 27. 19.8 9.6 M092000800079 27.27 23.3 9.7 M092000800080 27.54 15.5 9.8 M092000800081 27.81 27.5 9.9 M092000800082 28.08 23.7 10.0 M092000800083 ENDDATA 70 0 M092000800084 ENDSUBENT 83 0 M092000899999 SUBENT M0920009 20160322 M082M092000900001 BIB 4 24 M092000900002 REACTION ((34-SE-80(G,N)34-SE-79,,SIG,,,EVAL)+ M092000900003 (34-SE-80(G,N+P)33-AS-78,,SIG,,,EVAL)) M092000900004 ANALYSIS The contribution of partial reaction (g,n) cross M092000900005 section into the experimental total neutron yield M092000900006 reaction (g,xn) = (g,n) + 2(g,2n) cross section M092000900007 obtained using M092000900008 quasimonoenergetic annihilation photons at Saclay M092000900009 (France) was evaluated using specially theoretically M092000900010 calculated transitional multiplicity function - M092000900011 ratio M092000900012 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092000900013 by the way M092000900014 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M092000900015 REL-REF (R,L0043031,P.Carlos+,J,NP/A,258,365,1976) M092000900016 Experimental data for the total neutron yield M092000900017 reaction (g,xn) = (g,n) + 2(g,2n) M092000900018 cross section. M092000900019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092000900020 Theoretical preequilibrium model of photonuclear M092000900021 reactions based on the Fermi gas densities. M092000900022 STATUS Data plotted in Fig. 5. M092000900023 (DEP,L0043031) M092000900024 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092000900025 cross section. M092000900026 ENDBIB 24 0 M092000900027 NOCOMMON 0 0 M092000900028 DATA 3 68 M092000900029 EN DATA DATA-ERR M092000900030 MEV MB MB M092000900031 9.92 0.3 4.0 M092000900032 10.2 18.1 4.0 M092000900033 10.47 23.8 4.1 M092000900034 10.74 12.5 4.1 M092000900035 11.01 18.0 4.2 M092000900036 11.28 33.1 4.3 M092000900037 11.55 26.4 4.3 M092000900038 11.82 29.3 4.4 M092000900039 12.09 33.2 4.4 M092000900040 12.36 30.4 4.5 M092000900041 12.63 38.4 4.6 M092000900042 12.91 43.6 4.6 M092000900043 13.18 51.1 4.7 M092000900044 13.45 63.2 4.7 M092000900045 13.72 74.5 4.8 M092000900046 13.99 77.9 4.9 M092000900047 14.26 91.8 4.9 M092000900048 14.53 102.3 5.0 M092000900049 14.8 108.7 5.0 M092000900050 15.07 114.4 5.1 M092000900051 15.34 123.0 5.1 M092000900052 15.62 129.8 5.2 M092000900053 15.89 137.0 5.3 M092000900054 16.16 135.2 5.3 M092000900055 16.43 140.8 5.4 M092000900056 16.7 135.0 5.4 M092000900057 16.97 125.9 5.5 M092000900058 17.24 126.0 5.6 M092000900059 17.51 128.6 5.6 M092000900060 17.78 110.5 5.7 M092000900061 18.05 92.0 5.7 M092000900062 18.33 75.8 5.8 M092000900063 18.6 73.9 5.9 M092000900064 18.87 57.1 5.9 M092000900065 19.14 52.0 6.0 M092000900066 19.41 47.2 6.0 M092000900067 19.68 38.6 6.1 M092000900068 19.95 35.2 6.2 M092000900069 20.22 32.5 6.2 M092000900070 20.49 28.5 6.3 M092000900071 20.76 28.3 6.3 M092000900072 21.04 27.2 6.4 M092000900073 21.31 24.5 6.5 M092000900074 21.58 25.8 6.5 M092000900075 21.85 22.3 6.6 M092000900076 22.12 20.0 6.6 M092000900077 22.39 21.3 6.7 M092000900078 22.66 18.1 6.8 M092000900079 22.93 16.8 6.8 M092000900080 23.2 14.4 6.9 M092000900081 23.47 13.6 6.9 M092000900082 23.75 13.0 7.0 M092000900083 24.02 11.7 7.1 M092000900084 24.29 10.4 7.1 M092000900085 24.56 11.7 7.2 M092000900086 24.83 8.28 7.2 M092000900087 25.1 9.56 7.3 M092000900088 25.37 8.05 7.4 M092000900089 25.64 8.82 7.4 M092000900090 25.91 6.59 7.5 M092000900091 26.18 8.51 7.5 M092000900092 26.46 6.17 7.6 M092000900093 26.73 6.38 7.7 M092000900094 27. 5.15 7.7 M092000900095 27.27 6.03 7.8 M092000900096 27.54 3.93 7.8 M092000900097 27.81 6.87 7.9 M092000900098 28.08 5.76 8.0 M092000900099 ENDDATA 70 0 M092000900100 ENDSUBENT 99 0 M092000999999 SUBENT M0920010 20160322 M082M092001000001 BIB 4 23 M092001000002 REACTION ((34-SE-80(G,2N)34-SE-78,,SIG,,,EVAL)+ M092001000003 (34-SE-80(G,2N+P)33-AS-77,,SIG,,,EVAL)) M092001000004 ANALYSIS The contribution of partial reaction (g,n) cross M092001000005 section into the experimental total neutron yield M092001000006 reaction (g,xn) = (g,n) + 2(g,2n) M092001000007 cross section obtained using M092001000008 quasimonoenergetic annihilation photons at Sacle M092001000009 (France)was evaluated using specially theoretically M092001000010 calculated transitional multiplicity function - M092001000011 ratio M092001000012 F2-theor = SIG-theor(g,n)/SIG-theor(g,xn) M092001000013 by the way M092001000014 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M092001000015 REL-REF (R,L0043031,B.L.Berman+,J,PR,162,1098,1967) M092001000016 Experimental data for the total neutron yield M092001000017 reaction (g,xn) cross section. M092001000018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M092001000019 Theoretical preequilibrium model of photonuclear M092001000020 reactions based on the Fermi gas densities. M092001000021 STATUS Data plotted in Fig. 5. M092001000022 (DEP,L0046004) M092001000023 The neutron yield reaction (g,xn) = (g,n) + 2(g,2n) M092001000024 cross section. M092001000025 ENDBIB 23 0 M092001000026 NOCOMMON 0 0 M092001000027 DATA 3 41 M092001000028 EN DATA DATA-ERR M092001000029 MEV MB MB M092001000030 17.24 1.62 3.67 M092001000031 17.51 3.85 3.73 M092001000032 17.78 14.96 3.79 M092001000033 18.05 25.35 3.85 M092001000034 18.33 31.76 3.91 M092001000035 18.6 40.57 3.97 M092001000036 18.87 42.02 4.02 M092001000037 19.14 45.98 4.08 M092001000038 19.41 48.48 4.14 M092001000039 19.68 44.47 4.20 M092001000040 19.95 48.24 4.26 M092001000041 20.22 47.39 4.31 M092001000042 20.49 43.35 4.37 M092001000043 20.76 45.18 4.43 M092001000044 21.04 44.77 4.49 M092001000045 21.31 41.69 4.55 M092001000046 21.58 43.93 4.61 M092001000047 21.85 38.90 4.66 M092001000048 22.12 35.04 4.72 M092001000049 22.39 38.66 4.78 M092001000050 22.66 34.11 4.84 M092001000051 22.93 34.04 4.90 M092001000052 23.2 30.78 4.95 M092001000053 23.47 31.26 5.01 M092001000054 23.75 31.10 5.07 M092001000055 24.02 28.72 5.13 M092001000056 24.29 25.71 5.19 M092001000057 24.56 29.36 5.25 M092001000058 24.83 21.16 5.30 M092001000059 25.1 24.90 5.36 M092001000060 25.37 21.22 5.42 M092001000061 25.64 23.38 5.48 M092001000062 25.91 17.86 5.53 M092001000063 26.18 23.33 5.59 M092001000064 26.46 17.30 5.65 M092001000065 26.73 18.11 5.71 M092001000066 27. 14.66 5.77 M092001000067 27.27 17.31 5.83 M092001000068 27.54 11.56 5.88 M092001000069 27.81 20.65 5.94 M092001000070 28.08 18.01 6.00 M092001000071 ENDDATA 43 0 M092001000072 ENDSUBENT 71 0 M092001099999 SUBENT M0920011 20160322 M082M092001100001 BIB 3 4 M092001100002 REACTION (29-CU-63(G,X)0-NN-1,UNW,INT,,,EVAL) M092001100003 ANALYSIS Integration of evaluated cross section. M092001100004 STATUS (DEP,M0920002) Evaluated cross section. M092001100005 Data from the Table 2. M092001100006 ENDBIB 4 0 M092001100007 NOCOMMON 0 0 M092001100008 DATA 3 2 M092001100009 EN-MAX DATA DATA-ERR M092001100010 MEV MB*MEV MB*MEV M092001100011 19.7 380.3 11.1 M092001100012 28.0 664.2 14.2 M092001100013 ENDDATA 4 0 M092001100014 ENDSUBENT 13 0 M092001199999 SUBENT M0920012 20160322 M082M092001200001 BIB 3 5 M092001200002 REACTION ((29-CU-63(G,N)29-CU-62,,INT,,,EVAL)+ M092001200003 (29-CU-63(G,N+P)28-NI-61,,INT,,,EVAL)) M092001200004 ANALYSIS Integration of evaluated cross section. M092001200005 STATUS (DEP,M0920003) Evaluated cross section. M092001200006 Data from the Table 2. M092001200007 ENDBIB 5 0 M092001200008 NOCOMMON 0 0 M092001200009 DATA 3 2 M092001200010 EN-MAX DATA DATA-ERR M092001200011 MEV MB*MEV MB*MEV M092001200012 19.7 370.3 11.1 M092001200013 28.0 605.2 14.0 M092001200014 ENDDATA 4 0 M092001200015 ENDSUBENT 14 0 M092001299999 SUBENT M0920013 20160322 M082M092001300001 BIB 3 5 M092001300002 REACTION ((29-CU-63(G,2N)29-CU-61,,INT,,,EVAL)+ M092001300003 (29-CU-63(G,2N+P)28-NI-60,,INT,,,EVAL)) M092001300004 ANALYSIS Integration of evaluated cross section. M092001300005 STATUS (DEP,M0920004) Evaluated cross section. M092001300006 Data from the Table 2. M092001300007 ENDBIB 5 0 M092001300008 NOCOMMON 0 0 M092001300009 DATA 3 1 M092001300010 EN-MAX DATA DATA-ERR M092001300011 MEV MB*MEV MB*MEV M092001300012 28. 39.2 1.6 M092001300013 ENDDATA 3 0 M092001300014 ENDSUBENT 13 0 M092001399999 SUBENT M0920014 20160322 M082M092001400001 BIB 4 7 M092001400002 REACTION (29-CU-65(G,X)0-NN-1,UNW,INT,,,EVAL) M092001400003 ANALYSIS Integration of evaluated cross section. M092001400004 CRITIQUE Integrated cross section calculated up to EN-MAX = M092001400005 17.8 MeV is 364.7 mb*MeV, not 334.7 mb*MeV as in M092001400006 article. M092001400007 STATUS (DEP,M0920005) Evaluated cross section. M092001400008 Data from the Table 2. M092001400009 ENDBIB 7 0 M092001400010 NOCOMMON 0 0 M092001400011 DATA 3 2 M092001400012 EN-MAX DATA DATA-ERR M092001400013 MEV MB*MEV MB*MEV M092001400014 17.8 364.7 11.1 M092001400015 28.0 702.9 14.3 M092001400016 ENDDATA 4 0 M092001400017 ENDSUBENT 16 0 M092001499999 SUBENT M0920015 20160322 M082M092001500001 BIB 3 5 M092001500002 REACTION ((29-CU-65(G,N)29-CU-64,,INT,,,EVAL)+ M092001500003 (29-CU-65(G,N+P)28-NI-63,,INT,,,EVAL)) M092001500004 ANALYSIS Integration of evaluated cross section. M092001500005 STATUS (DEP,M0920006) Evaluated cross section. M092001500006 Data from the Table 2. M092001500007 ENDBIB 5 0 M092001500008 NOCOMMON 0 0 M092001500009 DATA 3 2 M092001500010 EN-MAX DATA DATA-ERR M092001500011 MEV MB*MEV MB*MEV M092001500012 17.8 370.3 11.1 M092001500013 28.0 581.2 13.4 M092001500014 ENDDATA 4 0 M092001500015 ENDSUBENT 14 0 M092001599999 SUBENT M0920016 20160322 M082M092001600001 BIB 3 5 M092001600002 REACTION ((29-CU-65(G,2N)29-CU-63,,INT,,,EVAL)+ M092001600003 (29-CU-65(G,2N+P)28-NI-62,,INT,,,EVAL)) M092001600004 ANALYSIS Integration of evaluated cross section. M092001600005 STATUS (DEP,M0920007) Evaluated cross section. M092001600006 Data from the Table 2. M092001600007 ENDBIB 5 0 M092001600008 NOCOMMON 0 0 M092001600009 DATA 3 1 M092001600010 EN-MAX DATA DATA-ERR M092001600011 MEV MB*MEV MB*MEV M092001600012 28. 121.9 4.9 M092001600013 ENDDATA 3 0 M092001600014 ENDSUBENT 13 0 M092001699999 SUBENT M0920017 20160322 M082M092001700001 BIB 3 4 M092001700002 REACTION (34-SE-80(G,X)0-NN-1,UNW,INT,,,EVAL) M092001700003 ANALYSIS Integration of evaluated cross section. M092001700004 STATUS (DEP,M0920008) Evaluated cross section. M092001700005 Data from the Table 2. M092001700006 ENDBIB 4 0 M092001700007 NOCOMMON 0 0 M092001700008 DATA 3 2 M092001700009 EN-MAX DATA DATA-ERR M092001700010 MEV MB*MEV MB*MEV M092001700011 16.8 502.5 6.8 M092001700012 28.0 1191.1 16.0 M092001700013 ENDDATA 4 0 M092001700014 ENDSUBENT 13 0 M092001799999 SUBENT M0920018 20160322 M082M092001800001 BIB 3 5 M092001800002 REACTION ((34-SE-80(G,N)34-SE-79,,INT,,,EVAL)+ M092001800003 (34-SE-80(G,N+P)33-AS-78,,INT,,,EVAL)) M092001800004 ANALYSIS Integration of evaluated cross section. M092001800005 STATUS (DEP,M0920009) Evaluated cross section. M092001800006 Data from the Table 2. M092001800007 ENDBIB 5 0 M092001800008 NOCOMMON 0 0 M092001800009 DATA 3 2 M092001800010 EN-MAX DATA DATA-ERR M092001800011 MEV MB*MEV MB*MEV M092001800012 16.8 502.5 11.1 M092001800013 28.0 862.6 13.6 M092001800014 ENDDATA 4 0 M092001800015 ENDSUBENT 14 0 M092001899999 SUBENT M0920019 20160322 M082M092001900001 BIB 3 5 M092001900002 REACTION ((34-SE-80(G,2N)34-SE-78,,INT,,,EVAL)+ M092001900003 (34-SE-80(G,2N+P)33-AS-77,,INT,,,EVAL)) M092001900004 ANALYSIS Integration of evaluated cross section. M092001900005 STATUS (DEP,M0920010) Evaluated cross section. M092001900006 Data from the Table 2. M092001900007 ENDBIB 5 0 M092001900008 NOCOMMON 0 0 M092001900009 DATA 3 1 M092001900010 EN-MAX DATA DATA-ERR M092001900011 MEV MB*MEV MB*MEV M092001900012 28. 328.5 8.4 M092001900013 ENDDATA 3 0 M092001900014 ENDSUBENT 13 0 M092001999999 ENDENTRY 19 0 M092099999999