ENTRY M0971 20180803 M097M0971 0 1 SUBENT M0971001 20180803 M097M0971 1 1 BIB 9 33 M0971 1 2 TITLE Reliability of the partial photoneutron reaction cross M0971 1 3 sections for 139La and 145,148Nd. M0971 1 4 AUTHOR (V.V.Varlamov,V.D.Kaidarova) M0971 1 5 REFERENCE (J,MPM,4,1840201,2018) M0971 1 6 (J,IZV,82,693,2018) M0971 1 7 #DOI:10.7868/S0367676518060030 M0971 1 8 (J,BAS,82,614,2018) M0971 1 9 #DOI:10.3103/S1062873818060321 M0971 1 10 English translation of IZV,82,693,2018. M0971 1 11 Evaluated data for 139La. M0971 1 12 INSTITUTE (4RUSMOS) M0971 1 13 INC-SOURCE (QMPH,ARAD) M0971 1 14 ANALYSIS The joint analysis of data for total (g,xn) and M0971 1 15 partial (g,n), (g,2n) and (g,3n) reactions obtained M0971 1 16 in various experiments was carried out. The new M0971 1 17 approach to analysis of systematic disagreements M0971 1 18 between data was proposed on the base of new M0971 1 19 criteria of systematic uncertainties presence - M0971 1 20 specially proposed transitional multiplicity M0971 1 21 functions M0971 1 22 Fi-theor = SIG(g,in)/SIG(g,xn). M0971 1 23 Using these functions calculated in the frame of M0971 1 24 combined photonuclear reaction model new reliable M0971 1 25 and free from problems of neutron multiplicity M0971 1 26 sorting data for photoneutron partial reactions M0971 1 27 cross sections M0971 1 28 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M0971 1 29 were evaluated using experimental neutron yield M0971 1 30 reaction cross sections SIG-exp(g,xn). M0971 1 31 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M0971 1 32 STATUS (APRVD) Approved by V.Varlamov. M0971 1 33 HISTORY (20180803C) Data were compiled at the Russia MSU SINP M0971 1 34 CDFE by V.Varlamov. M0971 1 35 ENDBIB 33 0 M0971 1 36 NOCOMMON 0 0 M0971 1 37 ENDSUBENT 36 0 M0971 199999 SUBENT M0971002 20180803 M097M0971 2 1 BIB 3 8 M0971 2 2 REACTION (60-ND-145(G,X)0-NN-1,UNW,SIG,,,EVAL) M0971 2 3 ANALYSIS The total neutron reaction cross section obtained as M0971 2 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0971 2 5 STATUS (TABLE) Data plotted in Fig. 8a. M0971 2 6 (DEP,M0971003) M0971 2 7 Evaluated (g,1n) reaction cross section. M0971 2 8 (DEP,M0971004) M0971 2 9 Evaluated (g,2n) reaction cross section. M0971 2 10 ENDBIB 8 0 M0971 2 11 NOCOMMON 0 0 M0971 2 12 DATA 3 24 M0971 2 13 EN DATA DATA-ERR M0971 2 14 MEV MB MB M0971 2 15 10.36 66.47 12.04 M0971 2 16 10.76 76.78 12.73 M0971 2 17 11.16 92.83 13.85 M0971 2 18 11.56 123.77 16.17 M0971 2 19 11.96 144.4 17.87 M0971 2 20 12.36 177.63 20.71 M0971 2 21 12.76 197.11 22.46 M0971 2 22 13.16 206.28 23.32 M0971 2 23 13.56 225.76 27.01 M0971 2 24 13.96 275.04 31.31 M0971 2 25 14.36 308.15 31.01 M0971 2 26 14.76 312.92 27.10 M0971 2 27 15.16 325.94 25.34 M0971 2 28 15.56 328.55 24.52 M0971 2 29 15.96 305.36 22.76 M0971 2 30 16.36 262.19 19.93 M0971 2 31 16.76 248.57 19.13 M0971 2 32 17.16 233.57 18.23 M0971 2 33 17.56 205.45 16.46 M0971 2 34 17.96 184.56 15.15 M0971 2 35 18.36 140.10 12.45 M0971 2 36 18.76 107.26 10.61 M0971 2 37 19.16 98.672 10.20 M0971 2 38 20.16 111.00 10.94 M0971 2 39 ENDDATA 26 0 M0971 2 40 ENDSUBENT 39 0 M0971 299999 SUBENT M0971003 20180803 M097M0971 3 1 BIB 4 23 M0971 3 2 REACTION ((60-ND-145(G,N)60-ND-144,,SIG,,,EVAL)+ M0971 3 3 (60-ND-145(G,N+P)59-PR-143,,SIG,,,EVAL)) M0971 3 4 ANALYSIS The contribution of partial reaction (g,n) cross M0971 3 5 section into the experimental total neutron yield M0971 3 6 reaction (g,xn) cross section obtained using M0971 3 7 quasimonoenergetic annihilation photons at Saclay M0971 3 8 was evaluated using specially theoretically M0971 3 9 calculated transitional multiplicity function - M0971 3 10 ratio M0971 3 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0971 3 12 by the way M0971 3 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0971 3 14 The neutron yield cross section was obtained at M0971 3 15 Saclay by Beil. M0971 3 16 REL-REF (R,L0025011,P.Carlos+,J,NP/A,172,437,1971) M0971 3 17 Experimental data for the total neutron yield M0971 3 18 reaction (g,xn) cross section. M0971 3 19 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0971 3 20 Theoretical preequilibrium model of photonuclear M0971 3 21 reactions based on the Fermi gas densities. M0971 3 22 STATUS (TABLE) Data plotted in Fig. 8b. M0971 3 23 (DEP,L0025011) M0971 3 24 The neutron yield reaction (g,xn) cross section. M0971 3 25 ENDBIB 23 0 M0971 3 26 NOCOMMON 0 0 M0971 3 27 DATA 3 24 M0971 3 28 EN DATA DATA-ERR M0971 3 29 MEV MB MB M0971 3 30 10.36 66.47 12.04 M0971 3 31 10.76 76.78 12.73 M0971 3 32 11.16 92.83 13.85 M0971 3 33 11.56 123.77 16.17 M0971 3 34 11.96 144.4 17.87 M0971 3 35 12.36 177.63 20.71 M0971 3 36 12.76 197.11 22.46 M0971 3 37 13.16 206.28 23.32 M0971 3 38 13.56 225.76 27.01 M0971 3 39 13.96 275.04 31.31 M0971 3 40 14.36 281.67 30.87 M0971 3 41 14.76 241.93 26.00 M0971 3 42 15.16 209.53 22.15 M0971 3 43 15.56 180.38 18.94 M0971 3 44 15.96 148.88 15.69 M0971 3 45 16.36 117.56 12.57 M0971 3 46 16.76 105.20 11.32 M0971 3 47 17.16 94.70 10.27 M0971 3 48 17.56 80.86 8.96 M0971 3 49 17.96 71.16 8.05 M0971 3 50 18.36 53.29 6.51 M0971 3 51 18.76 40.34 5.48 M0971 3 52 19.16 36.90 5.23 M0971 3 53 20.16 40.94 5.52 M0971 3 54 ENDDATA 26 0 M0971 3 55 ENDSUBENT 54 0 M0971 399999 SUBENT M0971004 20180803 M097M0971 4 1 BIB 4 22 M0971 4 2 REACTION (60-ND-145(G,2N)60-ND-143,,SIG,,,EVAL) M0971 4 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0971 4 4 section into the experimental total neutron yield M0971 4 5 reaction (g,xn) cross section obtained using M0971 4 6 quasimonoenergetic annihilation photons at Saclay M0971 4 7 was evaluated using specially theoretically M0971 4 8 calculated transitional multiplicity function - M0971 4 9 ratio M0971 4 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0971 4 11 by the way M0971 4 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0971 4 13 The neutron yield cross section was obtained at M0971 4 14 Saclay by Beil. M0971 4 15 REL-REF (R,L0025011,P.Carlos+,J,NP/A,172,437,1971) M0971 4 16 Experimental data for the total neutron yield M0971 4 17 reaction (g,xn) cross section. M0971 4 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0971 4 19 Theoretical preequilibrium model of photonuclear M0971 4 20 reactions based on the Fermi gas densities. M0971 4 21 STATUS (TABLE) Data plotted in Fig. 8c. M0971 4 22 (DEP,L0025011) M0971 4 23 The neutron yield reaction (g,xn) cross section. M0971 4 24 ENDBIB 22 0 M0971 4 25 NOCOMMON 0 0 M0971 4 26 DATA 3 14 M0971 4 27 EN DATA DATA-ERR M0971 4 28 MEV MB MB M0971 4 29 14.36 26.47 2.90 M0971 4 30 14.76 70.98 7.63 M0971 4 31 15.16 116.41 12.31 M0971 4 32 15.56 148.17 15.56 M0971 4 33 15.96 156.47 16.49 M0971 4 34 16.36 144.62 15.47 M0971 4 35 16.76 143.36 15.42 M0971 4 36 17.16 138.87 15.06 M0971 4 37 17.56 124.59 13.80 M0971 4 38 17.96 113.39 12.84 M0971 4 39 18.36 86.80 10.61 M0971 4 40 18.76 66.92 9.09 M0971 4 41 19.16 61.76 8.76 M0971 4 42 20.16 70.06 9.45 M0971 4 43 ENDDATA 16 0 M0971 4 44 ENDSUBENT 43 0 M0971 499999 SUBENT M0971005 20180803 M097M0971 5 1 BIB 3 8 M0971 5 2 REACTION (60-ND-148(G,X)0-NN-1,UNW,SIG,,,EVAL) M0971 5 3 ANALYSIS The total neutron reaction cross section obtained as M0971 5 4 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M0971 5 5 STATUS (TABLE) Data plotted in Fig. 10a. M0971 5 6 (DEP,M0971006) M0971 5 7 Evaluated (g,1n) reaction cross section. M0971 5 8 (DEP,M0971007) M0971 5 9 Evaluated (g,2n) reaction cross section. M0971 5 10 ENDBIB 8 0 M0971 5 11 NOCOMMON 0 0 M0971 5 12 DATA 3 28 M0971 5 13 EN DATA DATA-ERR M0971 5 14 MEV MB MB M0971 5 15 8.13 27.00 6.67 M0971 5 16 8.53 14.00 6.35 M0971 5 17 8.93 22.00 6.76 M0971 5 18 9.33 44.00 7.84 M0971 5 19 9.73 49.00 8.26 M0971 5 20 10.13 58.00 8.93 M0971 5 21 10.53 83.00 10.82 M0971 5 22 10.93 98.00 12.10 M0971 5 23 11.33 115.00 13.59 M0971 5 24 11.73 151.00 16.81 M0971 5 25 12.13 176.00 19.15 M0971 5 26 12.53 197.40 21.77 M0971 5 27 12.93 228.34 23.57 M0971 5 28 13.33 221.41 18.86 M0971 5 29 13.73 226.28 16.83 M0971 5 30 14.13 241.44 17.88 M0971 5 31 14.53 246.05 19.13 M0971 5 32 14.93 262.81 21.28 M0971 5 33 15.33 259.61 21.66 M0971 5 34 15.73 258.90 21.98 M0971 5 35 16.13 230.73 19.90 M0971 5 36 16.53 219.10 19.06 M0971 5 37 16.93 188.83 16.65 M0971 5 38 17.33 176.75 15.70 M0971 5 39 17.73 153.67 13.88 M0971 5 40 18.13 146.66 13.35 M0971 5 41 18.53 111.97 10.70 M0971 5 42 18.93 109.36 10.52 M0971 5 43 ENDDATA 30 0 M0971 5 44 ENDSUBENT 43 0 M0971 599999 SUBENT M0971006 20180803 M097M0971 6 1 BIB 4 23 M0971 6 2 REACTION ((60-ND-148(G,N)60-ND-147,,SIG,,,EVAL)+ M0971 6 3 (60-ND-148(G,N+P)59-PR-146,,SIG,,,EVAL)) M0971 6 4 ANALYSIS The contribution of partial reaction (g,n) cross M0971 6 5 section into the experimental total neutron yield M0971 6 6 reaction (g,xn) cross section obtained using M0971 6 7 quasimonoenergetic annihilation photons at Saclay M0971 6 8 was evaluated using specially theoretically M0971 6 9 calculated transitional multiplicity function - M0971 6 10 ratio M0971 6 11 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M0971 6 12 by the way M0971 6 13 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M0971 6 14 The neutron yield cross section was obtained at M0971 6 15 Saclay by Beil. M0971 6 16 REL-REF (R,L0025017,P.Carlos+,J,NP/A,172,437,1971) M0971 6 17 Experimental data for the total neutron yield M0971 6 18 reaction (g,xn) cross section. M0971 6 19 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0971 6 20 Theoretical preequilibrium model of photonuclear M0971 6 21 reactions based on the Fermi gas densities. M0971 6 22 STATUS (TABLE) Data plotted in Fig. 10b. M0971 6 23 (DEP,L0025017) M0971 6 24 The neutron yield reaction (g,xn) cross section. M0971 6 25 ENDBIB 23 0 M0971 6 26 NOCOMMON 0 0 M0971 6 27 DATA 3 28 M0971 6 28 EN DATA DATA-ERR M0971 6 29 MEV MB MB M0971 6 30 8.13 27.00 6.67 M0971 6 31 8.53 14.00 6.35 M0971 6 32 8.93 22.00 6.76 M0971 6 33 9.33 44.00 7.84 M0971 6 34 9.73 49.00 8.26 M0971 6 35 10.13 58.00 8.93 M0971 6 36 10.53 83.00 10.82 M0971 6 37 10.93 98.00 12.10 M0971 6 38 11.33 115.00 13.59 M0971 6 39 11.73 151.00 16.81 M0971 6 40 12.13 176.00 19.15 M0971 6 41 12.53 197.40 21.77 M0971 6 42 12.93 219.27 23.55 M0971 6 43 13.33 171.01 18.09 M0971 6 44 13.73 128.76 13.42 M0971 6 45 14.13 98.88 10.19 M0971 6 46 14.53 75.91 7.79 M0971 6 47 14.93 65.21 6.67 M0971 6 48 15.33 55.22 5.65 M0971 6 49 15.73 50.01 5.11 M0971 6 50 16.13 42.06 4.33 M0971 6 51 16.53 38.81 4.01 M0971 6 52 16.93 33.06 3.45 M0971 6 53 17.33 30.90 3.25 M0971 6 54 17.73 26.96 2.88 M0971 6 55 18.13 25.73 2.77 M0971 6 56 18.53 20.14 2.29 M0971 6 57 18.93 19.72 2.26 M0971 6 58 ENDDATA 30 0 M0971 6 59 ENDSUBENT 58 0 M0971 699999 SUBENT M0971007 20180803 M097M0971 7 1 BIB 4 22 M0971 7 2 REACTION (60-ND-148(G,2N)60-ND-146,,SIG,,,EVAL) M0971 7 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0971 7 4 section into the experimental total neutron yield M0971 7 5 reaction (g,xn) cross section obtained using M0971 7 6 quasimonoenergetic annihilation photons at Saclay M0971 7 7 was evaluated using specially theoretically M0971 7 8 calculated transitional multiplicity function - M0971 7 9 ratio M0971 7 10 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0971 7 11 by the way M0971 7 12 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0971 7 13 The neutron yield cross section was obtained at M0971 7 14 Saclay by Beil. M0971 7 15 REL-REF (R,L0025017,P.Carlos+,J,NP/A,172,437,1971) M0971 7 16 Experimental data for the total neutron yield M0971 7 17 reaction (g,xn) cross section. M0971 7 18 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0971 7 19 Theoretical preequilibrium model of photonuclear M0971 7 20 reactions based on the Fermi gas densities. M0971 7 21 STATUS (TABLE) Data Data plotted in Fig. 10c. M0971 7 22 (DEP,L0026017) M0971 7 23 The neutron yield reaction (g,xn) cross section. M0971 7 24 ENDBIB 22 0 M0971 7 25 NOCOMMON 0 0 M0971 7 26 DATA 3 16 M0971 7 27 EN DATA DATA-ERR M0971 7 28 MEV MB MB M0971 7 29 12.93 9.06 0.97 M0971 7 30 13.33 50.39 5.33 M0971 7 31 13.73 97.51 10.16 M0971 7 32 14.13 142.55 14.69 M0971 7 33 14.53 170.14 17.47 M0971 7 34 14.93 197.59 20.21 M0971 7 35 15.33 204.38 20.91 M0971 7 36 15.73 208.89 21.37 M0971 7 37 16.13 188.66 19.42 M0971 7 38 16.53 180.28 18.63 M0971 7 39 16.93 155.76 16.29 M0971 7 40 17.33 145.85 15.35 M0971 7 41 17.73 126.71 13.58 M0971 7 42 18.13 120.93 13.05 M0971 7 43 18.53 91.82 10.45 M0971 7 44 18.93 89.63 10.28 M0971 7 45 ENDDATA 18 0 M0971 7 46 ENDSUBENT 45 0 M0971 799999 SUBENT M0971008 20180803 M097M0971 8 1 BIB 3 4 M0971 8 2 REACTION (60-ND-145(G,X)0-NN-1,UNW,INT,,,EVAL) M0971 8 3 ANALYSIS Integration of evaluated cross section. M0971 8 4 STATUS (DEP,M0971002) Evaluated cross section. M0971 8 5 (TABLE) Data presented in Table 5. M0971 8 6 ENDBIB 4 0 M0971 8 7 NOCOMMON 0 0 M0971 8 8 DATA 3 39 M0971 8 9 EN-MAX DATA DATA-ERR M0971 8 10 MEV MB*MEV MB*MEV M0971 8 11 13.6 465.97 22.93 M0971 8 12 19.7 1888.57 39.82 M0971 8 13 20.3 1999.58 41.29 M0971 8 14 ENDDATA 5 0 M0971 8 15 ENDSUBENT 14 0 M0971 899999 SUBENT M0971009 20180803 M097M0971 9 1 BIB 3 5 M0971 9 2 REACTION ((60-ND-145(G,N)60-ND-144,,INT,,,EVAL)+ M0971 9 3 (60-ND-145(G,N+P)59-PR-143,,INT,,,EVAL)) M0971 9 4 ANALYSIS Integration of evaluated cross section. M0971 9 5 STATUS (DEP,M0971003) Evaluated cross section. M0971 9 6 (TABLE) Data presented in Table 5. M0971 9 7 ENDBIB 5 0 M0971 9 8 NOCOMMON 0 0 M0971 9 9 DATA 3 39 M0971 9 10 EN-MAX DATA DATA-ERR M0971 9 11 MEV MB*MEV MB*MEV M0971 9 12 13.6 465.97 22.93 M0971 9 13 19.7 1310.49 35.07 M0971 9 14 20.3 1351.43 35.50 M0971 9 15 ENDDATA 5 0 M0971 9 16 ENDSUBENT 15 0 M0971 999999 SUBENT M0971010 20180803 M097M0971 10 1 BIB 3 4 M0971 10 2 REACTION (60-ND-145(G,2N)60-ND-143,,INT,,,EVAL) M0971 10 3 ANALYSIS Integration of evaluated cross section. M0971 10 4 STATUS (DEP,M0971004) Evaluated cross section. M0971 10 5 (TABLE) Data presented in Table 5. M0971 10 6 ENDBIB 4 0 M0971 10 7 NOCOMMON 0 0 M0971 10 8 DATA 3 29 M0971 10 9 EN-MAX DATA DATA-ERR M0971 10 10 MEV MB*MEV MB*MEV M0971 10 11 19.7 578.08 18.86 M0971 10 12 20.3 648.15 21.09 M0971 10 13 ENDDATA 4 0 M0971 10 14 ENDSUBENT 13 0 M0971 1099999 SUBENT M0971011 20180803 M097M0971 11 1 BIB 3 4 M0971 11 2 REACTION (60-ND-148(G,X)0-NN-1,UNW,INT,,,EVAL) M0971 11 3 ANALYSIS Integration of evaluated cross section. M0971 11 4 STATUS (DEP,M0971005) Evaluated cross section. M0971 11 5 (TABLE) Data presented in Table 6. M0971 11 6 ENDBIB 4 0 M0971 11 7 NOCOMMON 0 0 M0971 11 8 DATA 3 29 M0971 11 9 EN-MAX DATA DATA-ERR M0971 11 10 MEV MB*MEV MB*MEV M0971 11 11 12.6 385.78 17.49 M0971 11 12 19.0 1726.55 33.65 M0971 11 13 ENDDATA 4 0 M0971 11 14 ENDSUBENT 13 0 M0971 1199999 SUBENT M0971012 20180803 M097M0971 12 1 BIB 3 5 M0971 12 2 REACTION ((60-ND-148(G,N)60-ND-147,,INT,,,EVAL)+ M0971 12 3 (60-ND-148(G,N+P)59-PR-146,,INT,,,EVAL)) M0971 12 4 ANALYSIS Integration of evaluated cross section. M0971 12 5 STATUS (DEP,M0971006) Evaluated cross section. M0971 12 6 (TABLE) Data presented in Table 6. M0971 12 7 ENDBIB 5 0 M0971 12 8 NOCOMMON 0 0 M0971 12 9 DATA 3 29 M0971 12 10 EN-MAX DATA DATA-ERR M0971 12 11 MEV MB*MEV MB*MEV M0971 12 12 12.6 385.78 17.49 M0971 12 13 19.0 1185.62 23.07 M0971 12 14 ENDDATA 4 0 M0971 12 15 ENDSUBENT 14 0 M0971 1299999 SUBENT M0971013 20180803 M097M0971 13 1 BIB 3 4 M0971 13 2 REACTION (60-ND-148(G,2N)60-ND-146,,INT,,,EVAL) M0971 13 3 ANALYSIS Integration of evaluated cross section. M0971 13 4 STATUS (DEP,M0971007) Evaluated cross section. M0971 13 5 (TABLE) Data presented in Table 6. M0971 13 6 ENDBIB 4 0 M0971 13 7 NOCOMMON 0 0 M0971 13 8 DATA 3 19 M0971 13 9 EN-MAX DATA DATA-ERR M0971 13 10 MEV MB*MEV MB*MEV M0971 13 11 19.0 656.62 24.50 M0971 13 12 ENDDATA 3 0 M0971 13 13 ENDSUBENT 12 0 M0971 1399999 ENDENTRY 13 0 M097199999999