ENTRY M0971 20180803 M097M097100000001 SUBENT M0971001 20180803 M097M097100100001 BIB 9 33 M097100100002 TITLE Reliability of the partial photoneutron reaction cross M097100100003 sections for 139La and 145,148Nd. M097100100004 AUTHOR (V.V.Varlamov,V.D.Kaidarova) M097100100005 REFERENCE (J,MPM,4,1840201,2018) M097100100006 (J,IZV,82,693,2018) M097100100007 #DOI:10.7868/S0367676518060030 M097100100008 (J,BAS,82,614,2018) M097100100009 #DOI:10.3103/S1062873818060321 M097100100010 English translation of IZV,82,693,2018. M097100100011 Evaluated data for 139La. M097100100012 INSTITUTE (4RUSMOS) M097100100013 INC-SOURCE (QMPH,ARAD) M097100100014 ANALYSIS The joint analysis of data for total (g,xn) and M097100100015 partial (g,n), (g,2n) and (g,3n) reactions obtained M097100100016 in various experiments was carried out. The new M097100100017 approach to analysis of systematic disagreements M097100100018 between data was proposed on the base of new M097100100019 criteria of systematic uncertainties presence - M097100100020 specially proposed transitional multiplicity M097100100021 functions M097100100022 Fi-theor = SIG(g,in)/SIG(g,xn). M097100100023 Using these functions calculated in the frame of M097100100024 combined photonuclear reaction model new reliable M097100100025 and free from problems of neutron multiplicity M097100100026 sorting data for photoneutron partial reactions M097100100027 cross sections M097100100028 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M097100100029 were evaluated using experimental neutron yield M097100100030 reaction cross sections SIG-exp(g,xn). M097100100031 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M097100100032 STATUS (APRVD) Approved by V.Varlamov. M097100100033 HISTORY (20180803C) Data were compiled at the Russia MSU SINP M097100100034 CDFE by V.Varlamov. M097100100035 ENDBIB 33 0 M097100100036 NOCOMMON 0 0 M097100100037 ENDSUBENT 36 0 M097100199999 SUBENT M0971002 20180803 M097M097100200001 BIB 3 8 M097100200002 REACTION (60-ND-145(G,X)0-NN-1,UNW,SIG,,,EVAL) M097100200003 ANALYSIS The total neutron reaction cross section obtained as M097100200004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097100200005 STATUS (TABLE) Data plotted in Fig. 8a. M097100200006 (DEP,M0971003) M097100200007 Evaluated (g,1n) reaction cross section. M097100200008 (DEP,M0971004) M097100200009 Evaluated (g,2n) reaction cross section. M097100200010 ENDBIB 8 0 M097100200011 NOCOMMON 0 0 M097100200012 DATA 3 24 M097100200013 EN DATA DATA-ERR M097100200014 MEV MB MB M097100200015 10.36 66.47 12.04 M097100200016 10.76 76.78 12.73 M097100200017 11.16 92.83 13.85 M097100200018 11.56 123.77 16.17 M097100200019 11.96 144.4 17.87 M097100200020 12.36 177.63 20.71 M097100200021 12.76 197.11 22.46 M097100200022 13.16 206.28 23.32 M097100200023 13.56 225.76 27.01 M097100200024 13.96 275.04 31.31 M097100200025 14.36 308.15 31.01 M097100200026 14.76 312.92 27.10 M097100200027 15.16 325.94 25.34 M097100200028 15.56 328.55 24.52 M097100200029 15.96 305.36 22.76 M097100200030 16.36 262.19 19.93 M097100200031 16.76 248.57 19.13 M097100200032 17.16 233.57 18.23 M097100200033 17.56 205.45 16.46 M097100200034 17.96 184.56 15.15 M097100200035 18.36 140.10 12.45 M097100200036 18.76 107.26 10.61 M097100200037 19.16 98.672 10.20 M097100200038 20.16 111.00 10.94 M097100200039 ENDDATA 26 0 M097100200040 ENDSUBENT 39 0 M097100299999 SUBENT M0971003 20180803 M097M097100300001 BIB 4 23 M097100300002 REACTION ((60-ND-145(G,N)60-ND-144,,SIG,,,EVAL)+ M097100300003 (60-ND-145(G,N+P)59-PR-143,,SIG,,,EVAL)) M097100300004 ANALYSIS The contribution of partial reaction (g,n) cross M097100300005 section into the experimental total neutron yield M097100300006 reaction (g,xn) cross section obtained using M097100300007 quasimonoenergetic annihilation photons at Saclay M097100300008 was evaluated using specially theoretically M097100300009 calculated transitional multiplicity function - M097100300010 ratio M097100300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097100300012 by the way M097100300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097100300014 The neutron yield cross section was obtained at M097100300015 Saclay by Beil. M097100300016 REL-REF (R,L0025011,P.Carlos+,J,NP/A,172,437,1971) M097100300017 Experimental data for the total neutron yield M097100300018 reaction (g,xn) cross section. M097100300019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097100300020 Theoretical preequilibrium model of photonuclear M097100300021 reactions based on the Fermi gas densities. M097100300022 STATUS (TABLE) Data plotted in Fig. 8b. M097100300023 (DEP,L0025011) M097100300024 The neutron yield reaction (g,xn) cross section. M097100300025 ENDBIB 23 0 M097100300026 NOCOMMON 0 0 M097100300027 DATA 3 24 M097100300028 EN DATA DATA-ERR M097100300029 MEV MB MB M097100300030 10.36 66.47 12.04 M097100300031 10.76 76.78 12.73 M097100300032 11.16 92.83 13.85 M097100300033 11.56 123.77 16.17 M097100300034 11.96 144.4 17.87 M097100300035 12.36 177.63 20.71 M097100300036 12.76 197.11 22.46 M097100300037 13.16 206.28 23.32 M097100300038 13.56 225.76 27.01 M097100300039 13.96 275.04 31.31 M097100300040 14.36 281.67 30.87 M097100300041 14.76 241.93 26.00 M097100300042 15.16 209.53 22.15 M097100300043 15.56 180.38 18.94 M097100300044 15.96 148.88 15.69 M097100300045 16.36 117.56 12.57 M097100300046 16.76 105.20 11.32 M097100300047 17.16 94.70 10.27 M097100300048 17.56 80.86 8.96 M097100300049 17.96 71.16 8.05 M097100300050 18.36 53.29 6.51 M097100300051 18.76 40.34 5.48 M097100300052 19.16 36.90 5.23 M097100300053 20.16 40.94 5.52 M097100300054 ENDDATA 26 0 M097100300055 ENDSUBENT 54 0 M097100399999 SUBENT M0971004 20180803 M097M097100400001 BIB 4 22 M097100400002 REACTION (60-ND-145(G,2N)60-ND-143,,SIG,,,EVAL) M097100400003 ANALYSIS The contribution of partial reaction (g,2n) cross M097100400004 section into the experimental total neutron yield M097100400005 reaction (g,xn) cross section obtained using M097100400006 quasimonoenergetic annihilation photons at Saclay M097100400007 was evaluated using specially theoretically M097100400008 calculated transitional multiplicity function - M097100400009 ratio M097100400010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097100400011 by the way M097100400012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097100400013 The neutron yield cross section was obtained at M097100400014 Saclay by Beil. M097100400015 REL-REF (R,L0025011,P.Carlos+,J,NP/A,172,437,1971) M097100400016 Experimental data for the total neutron yield M097100400017 reaction (g,xn) cross section. M097100400018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097100400019 Theoretical preequilibrium model of photonuclear M097100400020 reactions based on the Fermi gas densities. M097100400021 STATUS (TABLE) Data plotted in Fig. 8c. M097100400022 (DEP,L0025011) M097100400023 The neutron yield reaction (g,xn) cross section. M097100400024 ENDBIB 22 0 M097100400025 NOCOMMON 0 0 M097100400026 DATA 3 14 M097100400027 EN DATA DATA-ERR M097100400028 MEV MB MB M097100400029 14.36 26.47 2.90 M097100400030 14.76 70.98 7.63 M097100400031 15.16 116.41 12.31 M097100400032 15.56 148.17 15.56 M097100400033 15.96 156.47 16.49 M097100400034 16.36 144.62 15.47 M097100400035 16.76 143.36 15.42 M097100400036 17.16 138.87 15.06 M097100400037 17.56 124.59 13.80 M097100400038 17.96 113.39 12.84 M097100400039 18.36 86.80 10.61 M097100400040 18.76 66.92 9.09 M097100400041 19.16 61.76 8.76 M097100400042 20.16 70.06 9.45 M097100400043 ENDDATA 16 0 M097100400044 ENDSUBENT 43 0 M097100499999 SUBENT M0971005 20180803 M097M097100500001 BIB 3 8 M097100500002 REACTION (60-ND-148(G,X)0-NN-1,UNW,SIG,,,EVAL) M097100500003 ANALYSIS The total neutron reaction cross section obtained as M097100500004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097100500005 STATUS (TABLE) Data plotted in Fig. 10a. M097100500006 (DEP,M0971006) M097100500007 Evaluated (g,1n) reaction cross section. M097100500008 (DEP,M0971007) M097100500009 Evaluated (g,2n) reaction cross section. M097100500010 ENDBIB 8 0 M097100500011 NOCOMMON 0 0 M097100500012 DATA 3 28 M097100500013 EN DATA DATA-ERR M097100500014 MEV MB MB M097100500015 8.13 27.00 6.67 M097100500016 8.53 14.00 6.35 M097100500017 8.93 22.00 6.76 M097100500018 9.33 44.00 7.84 M097100500019 9.73 49.00 8.26 M097100500020 10.13 58.00 8.93 M097100500021 10.53 83.00 10.82 M097100500022 10.93 98.00 12.10 M097100500023 11.33 115.00 13.59 M097100500024 11.73 151.00 16.81 M097100500025 12.13 176.00 19.15 M097100500026 12.53 197.40 21.77 M097100500027 12.93 228.34 23.57 M097100500028 13.33 221.41 18.86 M097100500029 13.73 226.28 16.83 M097100500030 14.13 241.44 17.88 M097100500031 14.53 246.05 19.13 M097100500032 14.93 262.81 21.28 M097100500033 15.33 259.61 21.66 M097100500034 15.73 258.90 21.98 M097100500035 16.13 230.73 19.90 M097100500036 16.53 219.10 19.06 M097100500037 16.93 188.83 16.65 M097100500038 17.33 176.75 15.70 M097100500039 17.73 153.67 13.88 M097100500040 18.13 146.66 13.35 M097100500041 18.53 111.97 10.70 M097100500042 18.93 109.36 10.52 M097100500043 ENDDATA 30 0 M097100500044 ENDSUBENT 43 0 M097100599999 SUBENT M0971006 20180803 M097M097100600001 BIB 4 23 M097100600002 REACTION ((60-ND-148(G,N)60-ND-147,,SIG,,,EVAL)+ M097100600003 (60-ND-148(G,N+P)59-PR-146,,SIG,,,EVAL)) M097100600004 ANALYSIS The contribution of partial reaction (g,n) cross M097100600005 section into the experimental total neutron yield M097100600006 reaction (g,xn) cross section obtained using M097100600007 quasimonoenergetic annihilation photons at Saclay M097100600008 was evaluated using specially theoretically M097100600009 calculated transitional multiplicity function - M097100600010 ratio M097100600011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097100600012 by the way M097100600013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097100600014 The neutron yield cross section was obtained at M097100600015 Saclay by Beil. M097100600016 REL-REF (R,L0025017,P.Carlos+,J,NP/A,172,437,1971) M097100600017 Experimental data for the total neutron yield M097100600018 reaction (g,xn) cross section. M097100600019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097100600020 Theoretical preequilibrium model of photonuclear M097100600021 reactions based on the Fermi gas densities. M097100600022 STATUS (TABLE) Data plotted in Fig. 10b. M097100600023 (DEP,L0025017) M097100600024 The neutron yield reaction (g,xn) cross section. M097100600025 ENDBIB 23 0 M097100600026 NOCOMMON 0 0 M097100600027 DATA 3 28 M097100600028 EN DATA DATA-ERR M097100600029 MEV MB MB M097100600030 8.13 27.00 6.67 M097100600031 8.53 14.00 6.35 M097100600032 8.93 22.00 6.76 M097100600033 9.33 44.00 7.84 M097100600034 9.73 49.00 8.26 M097100600035 10.13 58.00 8.93 M097100600036 10.53 83.00 10.82 M097100600037 10.93 98.00 12.10 M097100600038 11.33 115.00 13.59 M097100600039 11.73 151.00 16.81 M097100600040 12.13 176.00 19.15 M097100600041 12.53 197.40 21.77 M097100600042 12.93 219.27 23.55 M097100600043 13.33 171.01 18.09 M097100600044 13.73 128.76 13.42 M097100600045 14.13 98.88 10.19 M097100600046 14.53 75.91 7.79 M097100600047 14.93 65.21 6.67 M097100600048 15.33 55.22 5.65 M097100600049 15.73 50.01 5.11 M097100600050 16.13 42.06 4.33 M097100600051 16.53 38.81 4.01 M097100600052 16.93 33.06 3.45 M097100600053 17.33 30.90 3.25 M097100600054 17.73 26.96 2.88 M097100600055 18.13 25.73 2.77 M097100600056 18.53 20.14 2.29 M097100600057 18.93 19.72 2.26 M097100600058 ENDDATA 30 0 M097100600059 ENDSUBENT 58 0 M097100699999 SUBENT M0971007 20180803 M097M097100700001 BIB 4 22 M097100700002 REACTION (60-ND-148(G,2N)60-ND-146,,SIG,,,EVAL) M097100700003 ANALYSIS The contribution of partial reaction (g,2n) cross M097100700004 section into the experimental total neutron yield M097100700005 reaction (g,xn) cross section obtained using M097100700006 quasimonoenergetic annihilation photons at Saclay M097100700007 was evaluated using specially theoretically M097100700008 calculated transitional multiplicity function - M097100700009 ratio M097100700010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097100700011 by the way M097100700012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097100700013 The neutron yield cross section was obtained at M097100700014 Saclay by Beil. M097100700015 REL-REF (R,L0025017,P.Carlos+,J,NP/A,172,437,1971) M097100700016 Experimental data for the total neutron yield M097100700017 reaction (g,xn) cross section. M097100700018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097100700019 Theoretical preequilibrium model of photonuclear M097100700020 reactions based on the Fermi gas densities. M097100700021 STATUS (TABLE) Data Data plotted in Fig. 10c. M097100700022 (DEP,L0026017) M097100700023 The neutron yield reaction (g,xn) cross section. M097100700024 ENDBIB 22 0 M097100700025 NOCOMMON 0 0 M097100700026 DATA 3 16 M097100700027 EN DATA DATA-ERR M097100700028 MEV MB MB M097100700029 12.93 9.06 0.97 M097100700030 13.33 50.39 5.33 M097100700031 13.73 97.51 10.16 M097100700032 14.13 142.55 14.69 M097100700033 14.53 170.14 17.47 M097100700034 14.93 197.59 20.21 M097100700035 15.33 204.38 20.91 M097100700036 15.73 208.89 21.37 M097100700037 16.13 188.66 19.42 M097100700038 16.53 180.28 18.63 M097100700039 16.93 155.76 16.29 M097100700040 17.33 145.85 15.35 M097100700041 17.73 126.71 13.58 M097100700042 18.13 120.93 13.05 M097100700043 18.53 91.82 10.45 M097100700044 18.93 89.63 10.28 M097100700045 ENDDATA 18 0 M097100700046 ENDSUBENT 45 0 M097100799999 SUBENT M0971008 20180803 M097M097100800001 BIB 3 4 M097100800002 REACTION (60-ND-145(G,X)0-NN-1,UNW,INT,,,EVAL) M097100800003 ANALYSIS Integration of evaluated cross section. M097100800004 STATUS (DEP,M0971002) Evaluated cross section. M097100800005 (TABLE) Data presented in Table 5. M097100800006 ENDBIB 4 0 M097100800007 NOCOMMON 0 0 M097100800008 DATA 3 39 M097100800009 EN-MAX DATA DATA-ERR M097100800010 MEV MB*MEV MB*MEV M097100800011 13.6 465.97 22.93 M097100800012 19.7 1888.57 39.82 M097100800013 20.3 1999.58 41.29 M097100800014 ENDDATA 5 0 M097100800015 ENDSUBENT 14 0 M097100899999 SUBENT M0971009 20180803 M097M097100900001 BIB 3 5 M097100900002 REACTION ((60-ND-145(G,N)60-ND-144,,INT,,,EVAL)+ M097100900003 (60-ND-145(G,N+P)59-PR-143,,INT,,,EVAL)) M097100900004 ANALYSIS Integration of evaluated cross section. M097100900005 STATUS (DEP,M0971003) Evaluated cross section. M097100900006 (TABLE) Data presented in Table 5. M097100900007 ENDBIB 5 0 M097100900008 NOCOMMON 0 0 M097100900009 DATA 3 39 M097100900010 EN-MAX DATA DATA-ERR M097100900011 MEV MB*MEV MB*MEV M097100900012 13.6 465.97 22.93 M097100900013 19.7 1310.49 35.07 M097100900014 20.3 1351.43 35.50 M097100900015 ENDDATA 5 0 M097100900016 ENDSUBENT 15 0 M097100999999 SUBENT M0971010 20180803 M097M097101000001 BIB 3 4 M097101000002 REACTION (60-ND-145(G,2N)60-ND-143,,INT,,,EVAL) M097101000003 ANALYSIS Integration of evaluated cross section. M097101000004 STATUS (DEP,M0971004) Evaluated cross section. M097101000005 (TABLE) Data presented in Table 5. M097101000006 ENDBIB 4 0 M097101000007 NOCOMMON 0 0 M097101000008 DATA 3 29 M097101000009 EN-MAX DATA DATA-ERR M097101000010 MEV MB*MEV MB*MEV M097101000011 19.7 578.08 18.86 M097101000012 20.3 648.15 21.09 M097101000013 ENDDATA 4 0 M097101000014 ENDSUBENT 13 0 M097101099999 SUBENT M0971011 20180803 M097M097101100001 BIB 3 4 M097101100002 REACTION (60-ND-148(G,X)0-NN-1,UNW,INT,,,EVAL) M097101100003 ANALYSIS Integration of evaluated cross section. M097101100004 STATUS (DEP,M0971005) Evaluated cross section. M097101100005 (TABLE) Data presented in Table 6. M097101100006 ENDBIB 4 0 M097101100007 NOCOMMON 0 0 M097101100008 DATA 3 29 M097101100009 EN-MAX DATA DATA-ERR M097101100010 MEV MB*MEV MB*MEV M097101100011 12.6 385.78 17.49 M097101100012 19.0 1726.55 33.65 M097101100013 ENDDATA 4 0 M097101100014 ENDSUBENT 13 0 M097101199999 SUBENT M0971012 20180803 M097M097101200001 BIB 3 5 M097101200002 REACTION ((60-ND-148(G,N)60-ND-147,,INT,,,EVAL)+ M097101200003 (60-ND-148(G,N+P)59-PR-146,,INT,,,EVAL)) M097101200004 ANALYSIS Integration of evaluated cross section. M097101200005 STATUS (DEP,M0971006) Evaluated cross section. M097101200006 (TABLE) Data presented in Table 6. M097101200007 ENDBIB 5 0 M097101200008 NOCOMMON 0 0 M097101200009 DATA 3 29 M097101200010 EN-MAX DATA DATA-ERR M097101200011 MEV MB*MEV MB*MEV M097101200012 12.6 385.78 17.49 M097101200013 19.0 1185.62 23.07 M097101200014 ENDDATA 4 0 M097101200015 ENDSUBENT 14 0 M097101299999 SUBENT M0971013 20180803 M097M097101300001 BIB 3 4 M097101300002 REACTION (60-ND-148(G,2N)60-ND-146,,INT,,,EVAL) M097101300003 ANALYSIS Integration of evaluated cross section. M097101300004 STATUS (DEP,M0971007) Evaluated cross section. M097101300005 (TABLE) Data presented in Table 6. M097101300006 ENDBIB 4 0 M097101300007 NOCOMMON 0 0 M097101300008 DATA 3 19 M097101300009 EN-MAX DATA DATA-ERR M097101300010 MEV MB*MEV MB*MEV M097101300011 19.0 656.62 24.50 M097101300012 ENDDATA 3 0 M097101300013 ENDSUBENT 12 0 M097101399999 ENDENTRY 13 0 M097199999999