ENTRY M0978 20190925 M106M0978 0 1 SUBENT M0978001 20190925 M106M0978 1 1 BIB 9 48 M0978 1 2 TITLE Photoneutron reactions on 129Xe nuclei and their M0978 1 3 electromagnetic dissociation in colliders. M0978 1 4 AUTHOR (S.S.Belyshev,V.V.Varlamov,S.A.Gunin,A.I.Davydov, M0978 1 5 B.S.Ishkhanov,I.A.Pshenichnov,V.N.Orlin) M0978 1 6 REFERENCE (J,YF,83,2,2020) M0978 1 7 #doi:10.31857/S0044002719060047 M0978 1 8 (J,PAN,83,1,2020) M0978 1 9 #doi:10.1134/S1063778819060036 M0978 1 10 English translation of YF,83,2,2020. M0978 1 11 (J,MPM,3,1930413,2019) M0978 1 12 New data for 127I(g,xn) reaction cross section. M0978 1 13 INSTITUTE (4RUSMOS) M0978 1 14 INC-SOURCE (QMPH,ARAD) M0978 1 15 ANALYSIS Because one has no experimental photonuclear reaction M0978 1 16 data for 129Xe the joint analysis of cross-sections M0978 1 17 of partial (g,1n), (g,2n), and (g,3n) reactions as M0978 1 18 well as total (g,Sn)=(g,1n)+(g,2n)+(g,3n) and M0978 1 19 (g,xn)=(g,1n)+2(g,2n)+3(g,3n)reactions was carried M0978 1 20 out for several neighboring nuclei - 127I, 128Te, M0978 1 21 133Cs, and 138Ba. Experimental data were compared M0978 1 22 with the results of calculations using the combined M0978 1 23 model of photonucleon reactions (CMPNR) and code M0978 1 24 TALYS. It was found that results of both model for M0978 1 25 129Xe are close and that the best agreement of the M0978 1 26 theoretical cross sections was achieved for the M0978 1 27 experimental data for 127I. Therefore cross sections M0978 1 28 for photonuclear reactions on 129Xe were evaluated M0978 1 29 using experimental-theoretical method based on the M0978 1 30 experimental 127I(g,xn) reaction cross section. M0978 1 31 The joint analysis of data for total and partial M0978 1 32 (g,1n), (g,2n) and (g,3n) reactions obtained in M0978 1 33 various experiments was carried out. The new M0978 1 34 approach to analysis of systematic disagreements M0978 1 35 between data was proposed on the base of new M0978 1 36 criteria of systematic uncertainties presence - M0978 1 37 specially proposed transitional multiplicity M0978 1 38 functions M0978 1 39 Fi-theor = SIG(g,in)/SIG(g,xn). M0978 1 40 Using these functions calculated in the frame of M0978 1 41 CMPNR for 129Xe new reliable data for photoneutron M0978 1 42 partial reactions cross sections M0978 1 43 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M0978 1 44 for 129Xe were evaluated using experimental neutron M0978 1 45 yield reaction cross sections SIG-exp(g,xn) for 127I. M0978 1 46 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M0978 1 47 STATUS (APRVD) By V.Varlamov. M0978 1 48 HISTORY (20190925C) Data were compiled at the Russia MSU SINP M0978 1 49 CDFE by V.Varlamov. M0978 1 50 ENDBIB 48 0 M0978 1 51 NOCOMMON 0 0 M0978 1 52 ENDSUBENT 51 0 M0978 199999 SUBENT M0978002 20190925 M106M0978 2 1 BIB 4 18 M0978 2 2 REACTION (53-I-127(G,X)0-NN-1,,SIG,,,EVAL) M0978 2 3 ANALYSIS The neutron yield reaction cross section obtained as M0978 2 4 sum: SIG(g,xn) = SIG(g,1n)+2SIG(g,2n))+3SIG(g,3n). M0978 2 5 Because experimental data for the total neutron yield M0978 2 6 reaction (g,xn) cross section for 127I were obtained M0978 2 7 only up to energy 24.89 MeV in evaluation procedure M0978 2 8 the sum (g,1n)+2(g,2n)+3(g,3n) of experimental cross M0978 2 9 sections was obtained up to energy 31.2 MeV. M0978 2 10 STATUS (TABLE) Data plotted in Fig. 2. M0978 2 11 (DEP,L0015003) M0978 2 12 (DEP,L0015004) M0978 2 13 (DEP,L0015005) M0978 2 14 REL-REF (R,L0015003,R.Bergere+,J,NP/A,133,417,1969) M0978 2 15 Experimental data for (g,1n) reaction cross section. M0978 2 16 (R,L0015004,R.Bergere+,J,NP/A,133,417,1969) M0978 2 17 Experimental data for (g,2n) reaction cross section. M0978 2 18 (R,L0015005,R.Bergere+,J,NP/A,133,417,1969) M0978 2 19 Experimental data for (g,3n) reaction cross section. M0978 2 20 ENDBIB 18 0 M0978 2 21 NOCOMMON 0 0 M0978 2 22 DATA 3 76 M0978 2 23 EN DATA DATA-ERR M0978 2 24 MEV MB MB M0978 2 25 8.89 1.20 8.08 M0978 2 26 9.16 9.10 8.72 M0978 2 27 9.44 21.10 9.65 M0978 2 28 9.71 21.70 9.77 M0978 2 29 9.98 30.00 10.43 M0978 2 30 10.25 38.90 11.14 M0978 2 31 10.52 45.40 11.68 M0978 2 32 10.80 46.50 11.85 M0978 2 33 11.07 56.80 12.65 M0978 2 34 11.34 69.00 13.58 M0978 2 35 11.61 76.00 14.15 M0978 2 36 11.88 90.30 15.24 M0978 2 37 12.16 104.20 16.29 M0978 2 38 12.43 129.30 18.13 M0978 2 39 12.70 148.80 19.59 M0978 2 40 12.97 169.40 21.11 M0978 2 41 13.24 200.40 23.36 M0978 2 42 13.52 220.30 24.84 M0978 2 43 13.79 250.00 27.00 M0978 2 44 14.06 272.10 28.63 M0978 2 45 14.33 296.30 30.41 M0978 2 46 14.60 300.70 30.80 M0978 2 47 14.88 308.10 36.56 M0978 2 48 15.15 300.20 36.06 M0978 2 49 15.42 298.90 36.02 M0978 2 50 15.69 285.70 35.15 M0978 2 51 15.96 277.00 34.59 M0978 2 52 16.24 261.95 33.43 M0978 2 53 16.51 255.62 33.05 M0978 2 54 16.78 248.90 30.36 M0978 2 55 17.05 251.17 27.02 M0978 2 56 17.32 242.50 22.50 M0978 2 57 17.60 236.58 19.72 M0978 2 58 17.87 230.10 18.47 M0978 2 59 18.14 218.34 17.67 M0978 2 60 18.41 209.43 17.42 M0978 2 61 18.68 195.80 17.10 M0978 2 62 18.96 182.55 16.71 M0978 2 63 19.23 164.99 16.19 M0978 2 64 19.50 168.30 16.55 M0978 2 65 19.77 147.94 15.71 M0978 2 66 20.04 147.34 15.95 M0978 2 67 20.32 128.58 15.40 M0978 2 68 20.59 118.09 14.97 M0978 2 69 20.86 119.50 15.07 M0978 2 70 21.13 103.68 14.37 M0978 2 71 21.40 96.53 14.05 M0978 2 72 21.68 94.75 13.77 M0978 2 73 21.95 81.97 13.22 M0978 2 74 22.22 78.57 13.07 M0978 2 75 22.49 79.73 13.16 M0978 2 76 22.76 66.93 9.55 M0978 2 77 23.04 67.71 9.56 M0978 2 78 23.31 63.63 9.39 M0978 2 79 23.58 60.59 9.43 M0978 2 80 23.85 60.96 9.44 M0978 2 81 24.12 61.54 9.47 M0978 2 82 24.40 56.26 9.25 M0978 2 83 24.67 53.93 9.15 M0978 2 84 24.94 38.22 8.47 M0978 2 85 25.21 59.58 9.57 M0978 2 86 25.48 51.74 9.22 M0978 2 87 25.76 57.72 11.29 M0978 2 88 26.03 53.99 11.13 M0978 2 89 26.30 61.35 11.45 M0978 2 90 26.57 63.60 11.55 M0978 2 91 26.84 61.85 11.27 M0978 2 92 27.12 55.34 10.78 M0978 2 93 27.66 51.40 10.07 M0978 2 94 28.20 48.64 9.28 M0978 2 95 28.48 46.04 8.55 M0978 2 96 29.02 45.59 7.83 M0978 2 97 29.56 38.63 7.09 M0978 2 98 30.11 48.36 7.11 M0978 2 99 30.65 40.09 6.77 M0978 2 100 31.20 40.89 6.83 M0978 2 101 ENDDATA 78 0 M0978 2 102 ENDSUBENT 101 0 M0978 299999 SUBENT M0978003 20190925 M106M0978 3 1 BIB 3 10 M0978 3 2 REACTION (54-XE-129(G,X)0-NN-1,UNW,SIG,,,EVAL) M0978 3 3 ANALYSIS The total neutron reaction cross section obtained as M0978 3 4 sum: SIG(g,Sn) = SIG(g,1n)+SIG(g,2n)+SIG(g,3n). M0978 3 5 STATUS (TABLE) Data plotted in Fig. 2. M0978 3 6 (DEP,M0978004) M0978 3 7 Evaluated (g,1n) reaction cross section. M0978 3 8 (DEP,M0978005) M0978 3 9 Evaluated (g,2n) reaction cross section. M0978 3 10 (DEP,M0978006) M0978 3 11 Evaluated (g,3n) reaction cross section. M0978 3 12 ENDBIB 10 0 M0978 3 13 NOCOMMON 0 0 M0978 3 14 DATA 3 76 M0978 3 15 EN DATA DATA-ERR M0978 3 16 MEV MB MB M0978 3 17 8.89 1.20 8.08 M0978 3 18 9.16 9.10 8.72 M0978 3 19 9.44 21.10 9.65 M0978 3 20 9.71 21.70 9.77 M0978 3 21 9.98 30.00 10.43 M0978 3 22 10.25 38.90 11.14 M0978 3 23 10.52 45.40 11.68 M0978 3 24 10.80 46.50 11.85 M0978 3 25 11.07 56.80 12.65 M0978 3 26 11.34 69.00 13.58 M0978 3 27 11.61 76.00 14.15 M0978 3 28 11.88 90.30 15.24 M0978 3 29 12.16 104.20 16.29 M0978 3 30 12.43 129.30 18.13 M0978 3 31 12.70 148.80 19.59 M0978 3 32 12.97 169.40 21.11 M0978 3 33 13.24 200.40 23.36 M0978 3 34 13.52 220.30 24.84 M0978 3 35 13.79 250.00 27.00 M0978 3 36 14.06 272.10 28.63 M0978 3 37 14.33 296.30 30.41 M0978 3 38 14.60 300.70 30.80 M0978 3 39 14.88 308.10 36.56 M0978 3 40 15.15 300.20 36.06 M0978 3 41 15.42 298.90 36.02 M0978 3 42 15.69 285.70 35.15 M0978 3 43 15.96 277.00 34.59 M0978 3 44 16.24 259.31 33.10 M0978 3 45 16.51 245.29 31.38 M0978 3 46 16.78 225.81 26.79 M0978 3 47 17.05 210.17 22.65 M0978 3 48 17.32 189.45 19.02 M0978 3 49 17.60 170.73 16.55 M0978 3 50 17.87 154.97 14.96 M0978 3 51 18.14 140.36 13.95 M0978 3 52 18.41 130.36 13.36 M0978 3 53 18.68 119.88 12.94 M0978 3 54 18.96 111.04 12.69 M0978 3 55 19.23 98.66 12.04 M0978 3 56 19.50 98.90 12.04 M0978 3 57 19.77 87.84 11.62 M0978 3 58 20.04 86.58 11.58 M0978 3 59 20.32 74.78 10.87 M0978 3 60 20.59 68.69 10.49 M0978 3 61 20.86 70.22 10.60 M0978 3 62 21.13 61.36 10.12 M0978 3 63 21.40 55.58 9.81 M0978 3 64 21.68 56.26 9.87 M0978 3 65 21.95 48.17 9.42 M0978 3 66 22.22 46.17 9.34 M0978 3 67 22.49 46.85 9.40 M0978 3 68 22.76 39.33 6.93 M0978 3 69 23.04 39.79 6.95 M0978 3 70 23.31 37.39 6.82 M0978 3 71 23.58 34.27 6.65 M0978 3 72 23.85 34.83 6.68 M0978 3 73 24.12 35.17 6.70 M0978 3 74 24.40 31.90 6.52 M0978 3 75 24.67 29.47 6.28 M0978 3 76 24.94 20.88 5.68 M0978 3 77 25.21 31.01 5.95 M0978 3 78 25.48 26.93 5.47 M0978 3 79 25.76 28.86 6.18 M0978 3 80 26.03 26.45 5.79 M0978 3 81 26.30 29.42 5.54 M0978 3 82 26.57 30.50 5.38 M0978 3 83 26.84 29.95 5.07 M0978 3 84 27.12 26.18 4.71 M0978 3 85 27.66 23.26 4.43 M0978 3 86 28.20 21.97 4.44 M0978 3 87 28.48 20.30 4.30 M0978 3 88 29.02 19.40 4.27 M0978 3 89 29.56 16.44 4.33 M0978 3 90 30.11 20.36 4.61 M0978 3 91 30.65 16.46 4.54 M0978 3 92 31.20 16.53 4.52 M0978 3 93 ENDDATA 78 0 M0978 3 94 ENDSUBENT 93 0 M0978 399999 SUBENT M0978004 20190925 M106M0978 4 1 BIB 4 16 M0978 4 2 REACTION ((54-XE-129(G,N)54-XE-128,,SIG,,,EVAL)+ M0978 4 3 (54-XE-129(G,N+P)53-I-127,,SIG,,,EVAL)) M0978 4 4 ANALYSIS The contribution of partial reaction (g,1n) cross M0978 4 5 section into the experimental total neutron yield M0978 4 6 reaction (g,xn) cross section obtained using M0978 4 7 the neutron yield reaction 127I(g,xn) cross section M0978 4 8 obtained up to energy 31.2 MeV as sum of experimental M0978 4 9 partial reaction cross sections. M0978 4 10 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0978 4 11 Theoretical preequilibrium model of photonuclear M0978 4 12 reactions based on the Fermi gas densities. M0978 4 13 STATUS (TABLE) Data plotted in Fig. 2. M0978 4 14 (DEP,M0978002) M0978 4 15 The neutron yield reaction 127I(g,xn) cross section M0978 4 16 obtained up to energy 31.2 MeV as sum of experimental M0978 4 17 partial reaction cross sections. M0978 4 18 ENDBIB 16 0 M0978 4 19 NOCOMMON 0 0 M0978 4 20 DATA 3 76 M0978 4 21 EN DATA DATA-ERR M0978 4 22 MEV MB MB M0978 4 23 8.89 1.20 8.08 M0978 4 24 9.16 9.10 8.72 M0978 4 25 9.44 21.10 9.65 M0978 4 26 9.71 21.70 9.77 M0978 4 27 9.98 30.00 10.43 M0978 4 28 10.25 38.90 11.14 M0978 4 29 10.52 45.40 11.68 M0978 4 30 10.80 46.50 11.85 M0978 4 31 11.07 56.80 12.65 M0978 4 32 11.34 69.00 13.58 M0978 4 33 11.61 76.00 14.15 M0978 4 34 11.88 90.30 15.24 M0978 4 35 12.16 104.20 16.29 M0978 4 36 12.43 129.30 18.13 M0978 4 37 12.70 148.80 19.59 M0978 4 38 12.97 169.40 21.11 M0978 4 39 13.24 200.40 23.36 M0978 4 40 13.52 220.30 24.84 M0978 4 41 13.79 250.00 27.00 M0978 4 42 14.06 272.10 28.63 M0978 4 43 14.33 296.30 30.41 M0978 4 44 14.60 300.70 30.80 M0978 4 45 14.88 308.10 36.56 M0978 4 46 15.15 300.20 36.06 M0978 4 47 15.42 298.90 36.02 M0978 4 48 15.69 285.70 35.15 M0978 4 49 15.96 277.00 34.59 M0978 4 50 16.24 259.31 33.10 M0978 4 51 16.51 242.71 31.38 M0978 4 52 16.78 205.28 26.66 M0978 4 53 17.05 169.16 22.01 M0978 4 54 17.32 133.88 17.57 M0978 4 55 17.60 104.88 14.02 M0978 4 56 17.87 82.18 11.20 M0978 4 57 18.14 64.61 9.05 M0978 4 58 18.41 55.56 7.97 M0978 4 59 18.68 45.95 6.83 M0978 4 60 18.96 37.64 5.79 M0978 4 61 19.23 32.32 5.27 M0978 4 62 19.50 31.23 5.04 M0978 4 63 19.77 26.20 4.54 M0978 4 64 20.04 25.82 4.53 M0978 4 65 20.32 22.30 4.05 M0978 4 66 20.59 20.49 3.71 M0978 4 67 20.86 20.94 3.75 M0978 4 68 21.13 19.04 3.61 M0978 4 69 21.40 16.58 3.31 M0978 4 70 21.68 16.78 3.33 M0978 4 71 21.95 14.37 3.03 M0978 4 72 22.22 13.77 3.01 M0978 4 73 22.49 13.97 3.03 M0978 4 74 22.76 11.04 2.04 M0978 4 75 23.04 11.17 2.05 M0978 4 76 23.31 10.50 2.01 M0978 4 77 23.58 9.18 1.83 M0978 4 78 23.85 9.33 1.83 M0978 4 79 24.12 9.42 1.84 M0978 4 80 24.40 8.12 1.66 M0978 4 81 24.67 7.23 1.59 M0978 4 82 24.94 5.12 1.47 M0978 4 83 25.21 7.30 1.48 M0978 4 84 25.48 6.34 1.42 M0978 4 85 25.76 6.48 1.57 M0978 4 86 26.03 6.06 1.55 M0978 4 87 26.30 6.89 1.59 M0978 4 88 26.57 7.14 1.61 M0978 4 89 26.84 7.16 1.61 M0978 4 90 27.12 5.95 1.40 M0978 4 91 27.66 5.41 1.37 M0978 4 92 28.20 4.71 1.20 M0978 4 93 28.48 4.46 1.19 M0978 4 94 29.02 4.37 1.18 M0978 4 95 29.56 3.70 1.15 M0978 4 96 30.11 4.58 1.19 M0978 4 97 30.65 3.38 1.00 M0978 4 98 31.20 3.48 1.01 M0978 4 99 ENDDATA 78 0 M0978 4 100 ENDSUBENT 99 0 M0978 499999 SUBENT M0978005 20190925 M106M0978 5 1 BIB 4 18 M0978 5 2 REACTION (54-XE-129(G,2N)54-XE-127,,SIG,,,EVAL) M0978 5 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0978 5 4 section into the experimental total neutron yield M0978 5 5 reaction (g,xn) cross section obtained using M0978 5 6 quasimonoenergetic annihilation photons at Saclay M0978 5 7 (France) was evaluated using specially theoretically M0978 5 8 calculated transitional multiplicity function ratio M0978 5 9 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M0978 5 10 by the way M0978 5 11 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M0978 5 12 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0978 5 13 Theoretical preequilibrium model of photonuclear M0978 5 14 reactions based on the Fermi gas densities. M0978 5 15 STATUS (TABLE) Data plotted in Fig. 2. M0978 5 16 (DEP,M0978002) M0978 5 17 The neutron yield reaction 127I(g,xn) cross section M0978 5 18 obtained up to energy 31.2 MeV as sum of experimental M0978 5 19 partial reaction cross sections. M0978 5 20 ENDBIB 18 0 M0978 5 21 NOCOMMON 0 0 M0978 5 22 DATA 3 48 M0978 5 23 EN DATA DATA-ERR M0978 5 24 MEV MB MB M0978 5 25 16.51 2.58 0.33 M0978 5 26 16.78 20.53 2.67 M0978 5 27 17.05 41.01 5.34 M0978 5 28 17.32 55.57 7.29 M0978 5 29 17.60 65.85 8.80 M0978 5 30 17.87 72.79 9.92 M0978 5 31 18.14 75.75 10.61 M0978 5 32 18.41 74.80 10.72 M0978 5 33 18.68 73.93 10.99 M0978 5 34 18.96 73.40 11.29 M0978 5 35 19.23 66.34 10.82 M0978 5 36 19.50 67.67 10.93 M0978 5 37 19.77 61.64 10.69 M0978 5 38 20.04 60.76 10.65 M0978 5 39 20.32 52.48 10.09 M0978 5 40 20.59 48.20 9.81 M0978 5 41 20.86 49.28 9.91 M0978 5 42 21.13 42.32 9.45 M0978 5 43 21.40 39.00 9.24 M0978 5 44 21.68 39.48 9.30 M0978 5 45 21.95 33.80 8.92 M0978 5 46 22.22 32.40 8.84 M0978 5 47 22.49 32.88 8.90 M0978 5 48 22.76 28.29 6.62 M0978 5 49 23.04 28.62 6.64 M0978 5 50 23.31 26.90 6.52 M0978 5 51 23.58 25.09 6.39 M0978 5 52 23.85 25.50 6.42 M0978 5 53 24.12 25.75 6.44 M0978 5 54 24.40 23.78 6.30 M0978 5 55 24.67 22.24 6.08 M0978 5 56 24.94 15.37 5.49 M0978 5 57 25.21 22.50 5.76 M0978 5 58 25.48 18.48 5.25 M0978 5 59 25.76 18.85 5.88 M0978 5 60 26.03 16.53 5.43 M0978 5 61 26.30 16.90 5.03 M0978 5 62 26.57 16.23 4.70 M0978 5 63 26.84 14.32 4.14 M0978 5 64 27.12 11.90 3.68 M0978 5 65 27.66 8.66 2.89 M0978 5 66 28.20 6.80 2.33 M0978 5 67 28.48 5.94 2.13 M0978 5 68 29.02 4.85 1.76 M0978 5 69 29.56 3.29 1.37 M0978 5 70 30.11 3.56 1.25 M0978 5 71 30.65 2.53 1.03 M0978 5 72 31.20 2.18 0.86 M0978 5 73 ENDDATA 50 0 M0978 5 74 ENDSUBENT 73 0 M0978 599999 SUBENT M0978006 20190925 M106M0978 6 1 BIB 4 18 M0978 6 2 REACTION (54-XE-129(G,3N)54-XE-126,,SIG,,,EVAL) M0978 6 3 ANALYSIS The contribution of partial reaction (g,2n) cross M0978 6 4 section into the experimental total neutron yield M0978 6 5 reaction (g,xn) cross section obtained using M0978 6 6 quasimonoenergetic annihilation photons at Saclay M0978 6 7 (France) was evaluated using specially theoretically M0978 6 8 calculated transitional multiplicity function ratio M0978 6 9 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M0978 6 10 by the way M0978 6 11 SIG-eval(g,3n) = (F3-theor)x(SIG-exp(g,xn)). M0978 6 12 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M0978 6 13 Theoretical preequilibrium model of photonuclear M0978 6 14 reactions based on the Fermi gas densities. M0978 6 15 STATUS (TABLE) Data plotted in Fig. 2. M0978 6 16 (DEP,M0978002) M0978 6 17 The neutron yield reaction 127I(g,xn) cross section M0978 6 18 obtained up to energy 31.2 MeV as sum of experimental M0978 6 19 partial reaction cross sections. M0978 6 20 ENDBIB 18 0 M0978 6 21 NOCOMMON 0 0 M0978 6 22 DATA 3 18 M0978 6 23 EN DATA DATA-ERR M0978 6 24 MEV MB MB M0978 6 25 24.67 0.00 0.00 M0978 6 26 24.94 0.39 0.14 M0978 6 27 25.21 1.22 0.31 M0978 6 28 25.48 2.11 0.60 M0978 6 29 25.76 3.53 1.10 M0978 6 30 26.03 3.86 1.27 M0978 6 31 26.30 5.63 1.68 M0978 6 32 26.57 7.14 2.07 M0978 6 33 26.84 8.46 2.44 M0978 6 34 27.12 8.33 2.58 M0978 6 35 27.66 9.20 3.07 M0978 6 36 28.20 10.46 3.58 M0978 6 37 28.48 9.90 3.54 M0978 6 38 29.02 10.19 3.71 M0978 6 39 29.56 9.45 3.94 M0978 6 40 30.11 12.22 4.28 M0978 6 41 30.65 10.55 4.30 M0978 6 42 31.20 10.88 4.32 M0978 6 43 ENDDATA 20 0 M0978 6 44 ENDSUBENT 43 0 M0978 699999 SUBENT M0978007 20190925 M106M0978 7 1 BIB 3 8 M0978 7 2 REACTION (54-XE-129(G,X)0-NN-1,,INT,,,EVAL) M0978 7 3 ANALYSIS Integration of evaluated cross section. M0978 7 4 STATUS (DEP,M0978002) Neutron yield cross section of M0978 7 5 127I(g,xn) reaction obtained as the sum of the M0978 7 6 experimental partial reaction cross sections was M0978 7 7 assumed as equal to the 129Xe(g,xn) yield cross M0978 7 8 section used for correspondent evaluations. M0978 7 9 (TABLE) Data from Table 1. M0978 7 10 ENDBIB 8 0 M0978 7 11 NOCOMMON 0 0 M0978 7 12 DATA 3 39 M0978 7 13 EN-MAX DATA DATA-ERR M0978 7 14 MEV MB*MEV MB*MEV M0978 7 15 16.52 1210.9 24.0 M0978 7 16 23.85 2283.8 31.6 M0978 7 17 31.20 2647.7 33.5 M0978 7 18 ENDDATA 5 0 M0978 7 19 ENDSUBENT 18 0 M0978 799999 SUBENT M0978008 20190925 M106M0978 8 1 BIB 3 4 M0978 8 2 REACTION (54-XE-129(G,X)0-NN-1,UNW,INT,,,EVAL) M0978 8 3 ANALYSIS Integration of evaluated cross section. M0978 8 4 STATUS (DEP,M0978003) Evaluated cross section. M0978 8 5 (TABLE) Data from Table 1. M0978 8 6 ENDBIB 4 0 M0978 8 7 NOCOMMON 0 0 M0978 8 8 DATA 3 39 M0978 8 9 EN-MAX DATA DATA-ERR M0978 8 10 MEV MB*MEV MB*MEV M0978 8 11 16.52 1212.5 10.1 M0978 8 12 23.85 1929.1 27.5 M0978 8 13 31.20 2105.7 28.2 M0978 8 14 ENDDATA 5 0 M0978 8 15 ENDSUBENT 14 0 M0978 899999 SUBENT M0978009 20190925 M106M0978 9 1 BIB 3 5 M0978 9 2 REACTION ((54-XE-129(G,N)54-XE-128,,INT,,,EVAL)+ M0978 9 3 (54-XE-129(G,N+P)53-I-127,,INT,,,EVAL)) M0978 9 4 ANALYSIS Integration of evaluated cross section. M0978 9 5 STATUS (DEP,M0978004) Evaluated cross section. M0978 9 6 (TABLE) Data from Table 1. M0978 9 7 ENDBIB 5 0 M0978 9 8 NOCOMMON 0 0 M0978 9 9 DATA 3 39 M0978 9 10 EN-MAX DATA DATA-ERR M0978 9 11 MEV MB*MEV MB*MEV M0978 9 12 16.52 1212.1 9.4 M0978 9 13 23.85 1574.4 26.0 M0978 9 14 31.20 1615.5 26.1 M0978 9 15 ENDDATA 5 0 M0978 9 16 ENDSUBENT 15 0 M0978 999999 SUBENT M0978010 20190925 M106M0978 10 1 BIB 3 4 M0978 10 2 REACTION (54-XE-129(G,2N)54-XE-127,,INT,,,EVAL) M0978 10 3 ANALYSIS Integration of evaluated cross section. M0978 10 4 STATUS (DEP,M0978005) Evaluated cross section. M0978 10 5 (TABLE) Data from Table 1. M0978 10 6 ENDBIB 4 0 M0978 10 7 NOCOMMON 0 0 M0978 10 8 DATA 3 39 M0978 10 9 EN-MAX DATA DATA-ERR M0978 10 10 MEV MB*MEV MB*MEV M0978 10 11 16.52 1.4 3.8 M0978 10 12 23.85 354.7 9.0 M0978 10 13 31.20 438.7 9.9 M0978 10 14 ENDDATA 5 0 M0978 10 15 ENDSUBENT 14 0 M0978 1099999 SUBENT M0978011 20190925 M106M0978 11 1 BIB 3 4 M0978 11 2 REACTION (54-XE-129(G,3N)54-XE-126,,INT,,,EVAL) M0978 11 3 ANALYSIS Integration of evaluated cross section. M0978 11 4 STATUS (DEP,M0978006) Evaluated cross section. M0978 11 5 (TABLE) Data from Table 1. M0978 11 6 ENDBIB 4 0 M0978 11 7 NOCOMMON 0 0 M0978 11 8 DATA 3 19 M0978 11 9 EN-MAX DATA DATA-ERR M0978 11 10 MEV MB*MEV MB*MEV M0978 11 11 31.20 51.6 4.0 M0978 11 12 ENDDATA 3 0 M0978 11 13 ENDSUBENT 12 0 M0978 1199999 ENDENTRY 11 0 M097899999999