ENTRY M0978 20190925 M106M097800000001 SUBENT M0978001 20190925 M106M097800100001 BIB 9 48 M097800100002 TITLE Photoneutron reactions on 129Xe nuclei and their M097800100003 electromagnetic dissociation in colliders. M097800100004 AUTHOR (S.S.Belyshev,V.V.Varlamov,S.A.Gunin,A.I.Davydov, M097800100005 B.S.Ishkhanov,I.A.Pshenichnov,V.N.Orlin) M097800100006 REFERENCE (J,YF,83,2,2020) M097800100007 #doi:10.31857/S0044002719060047 M097800100008 (J,PAN,83,1,2020) M097800100009 #doi:10.1134/S1063778819060036 M097800100010 English translation of YF,83,2,2020. M097800100011 (J,MPM,3,1930413,2019) M097800100012 New data for 127I(g,xn) reaction cross section. M097800100013 INSTITUTE (4RUSMOS) M097800100014 INC-SOURCE (QMPH,ARAD) M097800100015 ANALYSIS Because one has no experimental photonuclear reaction M097800100016 data for 129Xe the joint analysis of cross-sections M097800100017 of partial (g,1n), (g,2n), and (g,3n) reactions as M097800100018 well as total (g,Sn)=(g,1n)+(g,2n)+(g,3n) and M097800100019 (g,xn)=(g,1n)+2(g,2n)+3(g,3n)reactions was carried M097800100020 out for several neighboring nuclei - 127I, 128Te, M097800100021 133Cs, and 138Ba. Experimental data were compared M097800100022 with the results of calculations using the combined M097800100023 model of photonucleon reactions (CMPNR) and code M097800100024 TALYS. It was found that results of both model for M097800100025 129Xe are close and that the best agreement of the M097800100026 theoretical cross sections was achieved for the M097800100027 experimental data for 127I. Therefore cross sections M097800100028 for photonuclear reactions on 129Xe were evaluated M097800100029 using experimental-theoretical method based on the M097800100030 experimental 127I(g,xn) reaction cross section. M097800100031 The joint analysis of data for total and partial M097800100032 (g,1n), (g,2n) and (g,3n) reactions obtained in M097800100033 various experiments was carried out. The new M097800100034 approach to analysis of systematic disagreements M097800100035 between data was proposed on the base of new M097800100036 criteria of systematic uncertainties presence - M097800100037 specially proposed transitional multiplicity M097800100038 functions M097800100039 Fi-theor = SIG(g,in)/SIG(g,xn). M097800100040 Using these functions calculated in the frame of M097800100041 CMPNR for 129Xe new reliable data for photoneutron M097800100042 partial reactions cross sections M097800100043 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M097800100044 for 129Xe were evaluated using experimental neutron M097800100045 yield reaction cross sections SIG-exp(g,xn) for 127I. M097800100046 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M097800100047 STATUS (APRVD) By V.Varlamov. M097800100048 HISTORY (20190925C) Data were compiled at the Russia MSU SINP M097800100049 CDFE by V.Varlamov. M097800100050 ENDBIB 48 0 M097800100051 NOCOMMON 0 0 M097800100052 ENDSUBENT 51 0 M097800199999 SUBENT M0978002 20190925 M106M097800200001 BIB 4 18 M097800200002 REACTION (53-I-127(G,X)0-NN-1,,SIG,,,EVAL) M097800200003 ANALYSIS The neutron yield reaction cross section obtained as M097800200004 sum: SIG(g,xn) = SIG(g,1n)+2SIG(g,2n))+3SIG(g,3n). M097800200005 Because experimental data for the total neutron yield M097800200006 reaction (g,xn) cross section for 127I were obtained M097800200007 only up to energy 24.89 MeV in evaluation procedure M097800200008 the sum (g,1n)+2(g,2n)+3(g,3n) of experimental cross M097800200009 sections was obtained up to energy 31.2 MeV. M097800200010 STATUS (TABLE) Data plotted in Fig. 2. M097800200011 (DEP,L0015003) M097800200012 (DEP,L0015004) M097800200013 (DEP,L0015005) M097800200014 REL-REF (R,L0015003,R.Bergere+,J,NP/A,133,417,1969) M097800200015 Experimental data for (g,1n) reaction cross section. M097800200016 (R,L0015004,R.Bergere+,J,NP/A,133,417,1969) M097800200017 Experimental data for (g,2n) reaction cross section. M097800200018 (R,L0015005,R.Bergere+,J,NP/A,133,417,1969) M097800200019 Experimental data for (g,3n) reaction cross section. M097800200020 ENDBIB 18 0 M097800200021 NOCOMMON 0 0 M097800200022 DATA 3 76 M097800200023 EN DATA DATA-ERR M097800200024 MEV MB MB M097800200025 8.89 1.20 8.08 M097800200026 9.16 9.10 8.72 M097800200027 9.44 21.10 9.65 M097800200028 9.71 21.70 9.77 M097800200029 9.98 30.00 10.43 M097800200030 10.25 38.90 11.14 M097800200031 10.52 45.40 11.68 M097800200032 10.80 46.50 11.85 M097800200033 11.07 56.80 12.65 M097800200034 11.34 69.00 13.58 M097800200035 11.61 76.00 14.15 M097800200036 11.88 90.30 15.24 M097800200037 12.16 104.20 16.29 M097800200038 12.43 129.30 18.13 M097800200039 12.70 148.80 19.59 M097800200040 12.97 169.40 21.11 M097800200041 13.24 200.40 23.36 M097800200042 13.52 220.30 24.84 M097800200043 13.79 250.00 27.00 M097800200044 14.06 272.10 28.63 M097800200045 14.33 296.30 30.41 M097800200046 14.60 300.70 30.80 M097800200047 14.88 308.10 36.56 M097800200048 15.15 300.20 36.06 M097800200049 15.42 298.90 36.02 M097800200050 15.69 285.70 35.15 M097800200051 15.96 277.00 34.59 M097800200052 16.24 261.95 33.43 M097800200053 16.51 255.62 33.05 M097800200054 16.78 248.90 30.36 M097800200055 17.05 251.17 27.02 M097800200056 17.32 242.50 22.50 M097800200057 17.60 236.58 19.72 M097800200058 17.87 230.10 18.47 M097800200059 18.14 218.34 17.67 M097800200060 18.41 209.43 17.42 M097800200061 18.68 195.80 17.10 M097800200062 18.96 182.55 16.71 M097800200063 19.23 164.99 16.19 M097800200064 19.50 168.30 16.55 M097800200065 19.77 147.94 15.71 M097800200066 20.04 147.34 15.95 M097800200067 20.32 128.58 15.40 M097800200068 20.59 118.09 14.97 M097800200069 20.86 119.50 15.07 M097800200070 21.13 103.68 14.37 M097800200071 21.40 96.53 14.05 M097800200072 21.68 94.75 13.77 M097800200073 21.95 81.97 13.22 M097800200074 22.22 78.57 13.07 M097800200075 22.49 79.73 13.16 M097800200076 22.76 66.93 9.55 M097800200077 23.04 67.71 9.56 M097800200078 23.31 63.63 9.39 M097800200079 23.58 60.59 9.43 M097800200080 23.85 60.96 9.44 M097800200081 24.12 61.54 9.47 M097800200082 24.40 56.26 9.25 M097800200083 24.67 53.93 9.15 M097800200084 24.94 38.22 8.47 M097800200085 25.21 59.58 9.57 M097800200086 25.48 51.74 9.22 M097800200087 25.76 57.72 11.29 M097800200088 26.03 53.99 11.13 M097800200089 26.30 61.35 11.45 M097800200090 26.57 63.60 11.55 M097800200091 26.84 61.85 11.27 M097800200092 27.12 55.34 10.78 M097800200093 27.66 51.40 10.07 M097800200094 28.20 48.64 9.28 M097800200095 28.48 46.04 8.55 M097800200096 29.02 45.59 7.83 M097800200097 29.56 38.63 7.09 M097800200098 30.11 48.36 7.11 M097800200099 30.65 40.09 6.77 M097800200100 31.20 40.89 6.83 M097800200101 ENDDATA 78 0 M097800200102 ENDSUBENT 101 0 M097800299999 SUBENT M0978003 20190925 M106M097800300001 BIB 3 10 M097800300002 REACTION (54-XE-129(G,X)0-NN-1,UNW,SIG,,,EVAL) M097800300003 ANALYSIS The total neutron reaction cross section obtained as M097800300004 sum: SIG(g,Sn) = SIG(g,1n)+SIG(g,2n)+SIG(g,3n). M097800300005 STATUS (TABLE) Data plotted in Fig. 2. M097800300006 (DEP,M0978004) M097800300007 Evaluated (g,1n) reaction cross section. M097800300008 (DEP,M0978005) M097800300009 Evaluated (g,2n) reaction cross section. M097800300010 (DEP,M0978006) M097800300011 Evaluated (g,3n) reaction cross section. M097800300012 ENDBIB 10 0 M097800300013 NOCOMMON 0 0 M097800300014 DATA 3 76 M097800300015 EN DATA DATA-ERR M097800300016 MEV MB MB M097800300017 8.89 1.20 8.08 M097800300018 9.16 9.10 8.72 M097800300019 9.44 21.10 9.65 M097800300020 9.71 21.70 9.77 M097800300021 9.98 30.00 10.43 M097800300022 10.25 38.90 11.14 M097800300023 10.52 45.40 11.68 M097800300024 10.80 46.50 11.85 M097800300025 11.07 56.80 12.65 M097800300026 11.34 69.00 13.58 M097800300027 11.61 76.00 14.15 M097800300028 11.88 90.30 15.24 M097800300029 12.16 104.20 16.29 M097800300030 12.43 129.30 18.13 M097800300031 12.70 148.80 19.59 M097800300032 12.97 169.40 21.11 M097800300033 13.24 200.40 23.36 M097800300034 13.52 220.30 24.84 M097800300035 13.79 250.00 27.00 M097800300036 14.06 272.10 28.63 M097800300037 14.33 296.30 30.41 M097800300038 14.60 300.70 30.80 M097800300039 14.88 308.10 36.56 M097800300040 15.15 300.20 36.06 M097800300041 15.42 298.90 36.02 M097800300042 15.69 285.70 35.15 M097800300043 15.96 277.00 34.59 M097800300044 16.24 259.31 33.10 M097800300045 16.51 245.29 31.38 M097800300046 16.78 225.81 26.79 M097800300047 17.05 210.17 22.65 M097800300048 17.32 189.45 19.02 M097800300049 17.60 170.73 16.55 M097800300050 17.87 154.97 14.96 M097800300051 18.14 140.36 13.95 M097800300052 18.41 130.36 13.36 M097800300053 18.68 119.88 12.94 M097800300054 18.96 111.04 12.69 M097800300055 19.23 98.66 12.04 M097800300056 19.50 98.90 12.04 M097800300057 19.77 87.84 11.62 M097800300058 20.04 86.58 11.58 M097800300059 20.32 74.78 10.87 M097800300060 20.59 68.69 10.49 M097800300061 20.86 70.22 10.60 M097800300062 21.13 61.36 10.12 M097800300063 21.40 55.58 9.81 M097800300064 21.68 56.26 9.87 M097800300065 21.95 48.17 9.42 M097800300066 22.22 46.17 9.34 M097800300067 22.49 46.85 9.40 M097800300068 22.76 39.33 6.93 M097800300069 23.04 39.79 6.95 M097800300070 23.31 37.39 6.82 M097800300071 23.58 34.27 6.65 M097800300072 23.85 34.83 6.68 M097800300073 24.12 35.17 6.70 M097800300074 24.40 31.90 6.52 M097800300075 24.67 29.47 6.28 M097800300076 24.94 20.88 5.68 M097800300077 25.21 31.01 5.95 M097800300078 25.48 26.93 5.47 M097800300079 25.76 28.86 6.18 M097800300080 26.03 26.45 5.79 M097800300081 26.30 29.42 5.54 M097800300082 26.57 30.50 5.38 M097800300083 26.84 29.95 5.07 M097800300084 27.12 26.18 4.71 M097800300085 27.66 23.26 4.43 M097800300086 28.20 21.97 4.44 M097800300087 28.48 20.30 4.30 M097800300088 29.02 19.40 4.27 M097800300089 29.56 16.44 4.33 M097800300090 30.11 20.36 4.61 M097800300091 30.65 16.46 4.54 M097800300092 31.20 16.53 4.52 M097800300093 ENDDATA 78 0 M097800300094 ENDSUBENT 93 0 M097800399999 SUBENT M0978004 20190925 M106M097800400001 BIB 4 16 M097800400002 REACTION ((54-XE-129(G,N)54-XE-128,,SIG,,,EVAL)+ M097800400003 (54-XE-129(G,N+P)53-I-127,,SIG,,,EVAL)) M097800400004 ANALYSIS The contribution of partial reaction (g,1n) cross M097800400005 section into the experimental total neutron yield M097800400006 reaction (g,xn) cross section obtained using M097800400007 the neutron yield reaction 127I(g,xn) cross section M097800400008 obtained up to energy 31.2 MeV as sum of experimental M097800400009 partial reaction cross sections. M097800400010 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097800400011 Theoretical preequilibrium model of photonuclear M097800400012 reactions based on the Fermi gas densities. M097800400013 STATUS (TABLE) Data plotted in Fig. 2. M097800400014 (DEP,M0978002) M097800400015 The neutron yield reaction 127I(g,xn) cross section M097800400016 obtained up to energy 31.2 MeV as sum of experimental M097800400017 partial reaction cross sections. M097800400018 ENDBIB 16 0 M097800400019 NOCOMMON 0 0 M097800400020 DATA 3 76 M097800400021 EN DATA DATA-ERR M097800400022 MEV MB MB M097800400023 8.89 1.20 8.08 M097800400024 9.16 9.10 8.72 M097800400025 9.44 21.10 9.65 M097800400026 9.71 21.70 9.77 M097800400027 9.98 30.00 10.43 M097800400028 10.25 38.90 11.14 M097800400029 10.52 45.40 11.68 M097800400030 10.80 46.50 11.85 M097800400031 11.07 56.80 12.65 M097800400032 11.34 69.00 13.58 M097800400033 11.61 76.00 14.15 M097800400034 11.88 90.30 15.24 M097800400035 12.16 104.20 16.29 M097800400036 12.43 129.30 18.13 M097800400037 12.70 148.80 19.59 M097800400038 12.97 169.40 21.11 M097800400039 13.24 200.40 23.36 M097800400040 13.52 220.30 24.84 M097800400041 13.79 250.00 27.00 M097800400042 14.06 272.10 28.63 M097800400043 14.33 296.30 30.41 M097800400044 14.60 300.70 30.80 M097800400045 14.88 308.10 36.56 M097800400046 15.15 300.20 36.06 M097800400047 15.42 298.90 36.02 M097800400048 15.69 285.70 35.15 M097800400049 15.96 277.00 34.59 M097800400050 16.24 259.31 33.10 M097800400051 16.51 242.71 31.38 M097800400052 16.78 205.28 26.66 M097800400053 17.05 169.16 22.01 M097800400054 17.32 133.88 17.57 M097800400055 17.60 104.88 14.02 M097800400056 17.87 82.18 11.20 M097800400057 18.14 64.61 9.05 M097800400058 18.41 55.56 7.97 M097800400059 18.68 45.95 6.83 M097800400060 18.96 37.64 5.79 M097800400061 19.23 32.32 5.27 M097800400062 19.50 31.23 5.04 M097800400063 19.77 26.20 4.54 M097800400064 20.04 25.82 4.53 M097800400065 20.32 22.30 4.05 M097800400066 20.59 20.49 3.71 M097800400067 20.86 20.94 3.75 M097800400068 21.13 19.04 3.61 M097800400069 21.40 16.58 3.31 M097800400070 21.68 16.78 3.33 M097800400071 21.95 14.37 3.03 M097800400072 22.22 13.77 3.01 M097800400073 22.49 13.97 3.03 M097800400074 22.76 11.04 2.04 M097800400075 23.04 11.17 2.05 M097800400076 23.31 10.50 2.01 M097800400077 23.58 9.18 1.83 M097800400078 23.85 9.33 1.83 M097800400079 24.12 9.42 1.84 M097800400080 24.40 8.12 1.66 M097800400081 24.67 7.23 1.59 M097800400082 24.94 5.12 1.47 M097800400083 25.21 7.30 1.48 M097800400084 25.48 6.34 1.42 M097800400085 25.76 6.48 1.57 M097800400086 26.03 6.06 1.55 M097800400087 26.30 6.89 1.59 M097800400088 26.57 7.14 1.61 M097800400089 26.84 7.16 1.61 M097800400090 27.12 5.95 1.40 M097800400091 27.66 5.41 1.37 M097800400092 28.20 4.71 1.20 M097800400093 28.48 4.46 1.19 M097800400094 29.02 4.37 1.18 M097800400095 29.56 3.70 1.15 M097800400096 30.11 4.58 1.19 M097800400097 30.65 3.38 1.00 M097800400098 31.20 3.48 1.01 M097800400099 ENDDATA 78 0 M097800400100 ENDSUBENT 99 0 M097800499999 SUBENT M0978005 20190925 M106M097800500001 BIB 4 18 M097800500002 REACTION (54-XE-129(G,2N)54-XE-127,,SIG,,,EVAL) M097800500003 ANALYSIS The contribution of partial reaction (g,2n) cross M097800500004 section into the experimental total neutron yield M097800500005 reaction (g,xn) cross section obtained using M097800500006 quasimonoenergetic annihilation photons at Saclay M097800500007 (France) was evaluated using specially theoretically M097800500008 calculated transitional multiplicity function ratio M097800500009 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097800500010 by the way M097800500011 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097800500012 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097800500013 Theoretical preequilibrium model of photonuclear M097800500014 reactions based on the Fermi gas densities. M097800500015 STATUS (TABLE) Data plotted in Fig. 2. M097800500016 (DEP,M0978002) M097800500017 The neutron yield reaction 127I(g,xn) cross section M097800500018 obtained up to energy 31.2 MeV as sum of experimental M097800500019 partial reaction cross sections. M097800500020 ENDBIB 18 0 M097800500021 NOCOMMON 0 0 M097800500022 DATA 3 48 M097800500023 EN DATA DATA-ERR M097800500024 MEV MB MB M097800500025 16.51 2.58 0.33 M097800500026 16.78 20.53 2.67 M097800500027 17.05 41.01 5.34 M097800500028 17.32 55.57 7.29 M097800500029 17.60 65.85 8.80 M097800500030 17.87 72.79 9.92 M097800500031 18.14 75.75 10.61 M097800500032 18.41 74.80 10.72 M097800500033 18.68 73.93 10.99 M097800500034 18.96 73.40 11.29 M097800500035 19.23 66.34 10.82 M097800500036 19.50 67.67 10.93 M097800500037 19.77 61.64 10.69 M097800500038 20.04 60.76 10.65 M097800500039 20.32 52.48 10.09 M097800500040 20.59 48.20 9.81 M097800500041 20.86 49.28 9.91 M097800500042 21.13 42.32 9.45 M097800500043 21.40 39.00 9.24 M097800500044 21.68 39.48 9.30 M097800500045 21.95 33.80 8.92 M097800500046 22.22 32.40 8.84 M097800500047 22.49 32.88 8.90 M097800500048 22.76 28.29 6.62 M097800500049 23.04 28.62 6.64 M097800500050 23.31 26.90 6.52 M097800500051 23.58 25.09 6.39 M097800500052 23.85 25.50 6.42 M097800500053 24.12 25.75 6.44 M097800500054 24.40 23.78 6.30 M097800500055 24.67 22.24 6.08 M097800500056 24.94 15.37 5.49 M097800500057 25.21 22.50 5.76 M097800500058 25.48 18.48 5.25 M097800500059 25.76 18.85 5.88 M097800500060 26.03 16.53 5.43 M097800500061 26.30 16.90 5.03 M097800500062 26.57 16.23 4.70 M097800500063 26.84 14.32 4.14 M097800500064 27.12 11.90 3.68 M097800500065 27.66 8.66 2.89 M097800500066 28.20 6.80 2.33 M097800500067 28.48 5.94 2.13 M097800500068 29.02 4.85 1.76 M097800500069 29.56 3.29 1.37 M097800500070 30.11 3.56 1.25 M097800500071 30.65 2.53 1.03 M097800500072 31.20 2.18 0.86 M097800500073 ENDDATA 50 0 M097800500074 ENDSUBENT 73 0 M097800599999 SUBENT M0978006 20190925 M106M097800600001 BIB 4 18 M097800600002 REACTION (54-XE-129(G,3N)54-XE-126,,SIG,,,EVAL) M097800600003 ANALYSIS The contribution of partial reaction (g,2n) cross M097800600004 section into the experimental total neutron yield M097800600005 reaction (g,xn) cross section obtained using M097800600006 quasimonoenergetic annihilation photons at Saclay M097800600007 (France) was evaluated using specially theoretically M097800600008 calculated transitional multiplicity function ratio M097800600009 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M097800600010 by the way M097800600011 SIG-eval(g,3n) = (F3-theor)x(SIG-exp(g,xn)). M097800600012 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097800600013 Theoretical preequilibrium model of photonuclear M097800600014 reactions based on the Fermi gas densities. M097800600015 STATUS (TABLE) Data plotted in Fig. 2. M097800600016 (DEP,M0978002) M097800600017 The neutron yield reaction 127I(g,xn) cross section M097800600018 obtained up to energy 31.2 MeV as sum of experimental M097800600019 partial reaction cross sections. M097800600020 ENDBIB 18 0 M097800600021 NOCOMMON 0 0 M097800600022 DATA 3 18 M097800600023 EN DATA DATA-ERR M097800600024 MEV MB MB M097800600025 24.67 0.00 0.00 M097800600026 24.94 0.39 0.14 M097800600027 25.21 1.22 0.31 M097800600028 25.48 2.11 0.60 M097800600029 25.76 3.53 1.10 M097800600030 26.03 3.86 1.27 M097800600031 26.30 5.63 1.68 M097800600032 26.57 7.14 2.07 M097800600033 26.84 8.46 2.44 M097800600034 27.12 8.33 2.58 M097800600035 27.66 9.20 3.07 M097800600036 28.20 10.46 3.58 M097800600037 28.48 9.90 3.54 M097800600038 29.02 10.19 3.71 M097800600039 29.56 9.45 3.94 M097800600040 30.11 12.22 4.28 M097800600041 30.65 10.55 4.30 M097800600042 31.20 10.88 4.32 M097800600043 ENDDATA 20 0 M097800600044 ENDSUBENT 43 0 M097800699999 SUBENT M0978007 20190925 M106M097800700001 BIB 3 8 M097800700002 REACTION (54-XE-129(G,X)0-NN-1,,INT,,,EVAL) M097800700003 ANALYSIS Integration of evaluated cross section. M097800700004 STATUS (DEP,M0978002) Neutron yield cross section of M097800700005 127I(g,xn) reaction obtained as the sum of the M097800700006 experimental partial reaction cross sections was M097800700007 assumed as equal to the 129Xe(g,xn) yield cross M097800700008 section used for correspondent evaluations. M097800700009 (TABLE) Data from Table 1. M097800700010 ENDBIB 8 0 M097800700011 NOCOMMON 0 0 M097800700012 DATA 3 39 M097800700013 EN-MAX DATA DATA-ERR M097800700014 MEV MB*MEV MB*MEV M097800700015 16.52 1210.9 24.0 M097800700016 23.85 2283.8 31.6 M097800700017 31.20 2647.7 33.5 M097800700018 ENDDATA 5 0 M097800700019 ENDSUBENT 18 0 M097800799999 SUBENT M0978008 20190925 M106M097800800001 BIB 3 4 M097800800002 REACTION (54-XE-129(G,X)0-NN-1,UNW,INT,,,EVAL) M097800800003 ANALYSIS Integration of evaluated cross section. M097800800004 STATUS (DEP,M0978003) Evaluated cross section. M097800800005 (TABLE) Data from Table 1. M097800800006 ENDBIB 4 0 M097800800007 NOCOMMON 0 0 M097800800008 DATA 3 39 M097800800009 EN-MAX DATA DATA-ERR M097800800010 MEV MB*MEV MB*MEV M097800800011 16.52 1212.5 10.1 M097800800012 23.85 1929.1 27.5 M097800800013 31.20 2105.7 28.2 M097800800014 ENDDATA 5 0 M097800800015 ENDSUBENT 14 0 M097800899999 SUBENT M0978009 20190925 M106M097800900001 BIB 3 5 M097800900002 REACTION ((54-XE-129(G,N)54-XE-128,,INT,,,EVAL)+ M097800900003 (54-XE-129(G,N+P)53-I-127,,INT,,,EVAL)) M097800900004 ANALYSIS Integration of evaluated cross section. M097800900005 STATUS (DEP,M0978004) Evaluated cross section. M097800900006 (TABLE) Data from Table 1. M097800900007 ENDBIB 5 0 M097800900008 NOCOMMON 0 0 M097800900009 DATA 3 39 M097800900010 EN-MAX DATA DATA-ERR M097800900011 MEV MB*MEV MB*MEV M097800900012 16.52 1212.1 9.4 M097800900013 23.85 1574.4 26.0 M097800900014 31.20 1615.5 26.1 M097800900015 ENDDATA 5 0 M097800900016 ENDSUBENT 15 0 M097800999999 SUBENT M0978010 20190925 M106M097801000001 BIB 3 4 M097801000002 REACTION (54-XE-129(G,2N)54-XE-127,,INT,,,EVAL) M097801000003 ANALYSIS Integration of evaluated cross section. M097801000004 STATUS (DEP,M0978005) Evaluated cross section. M097801000005 (TABLE) Data from Table 1. M097801000006 ENDBIB 4 0 M097801000007 NOCOMMON 0 0 M097801000008 DATA 3 39 M097801000009 EN-MAX DATA DATA-ERR M097801000010 MEV MB*MEV MB*MEV M097801000011 16.52 1.4 3.8 M097801000012 23.85 354.7 9.0 M097801000013 31.20 438.7 9.9 M097801000014 ENDDATA 5 0 M097801000015 ENDSUBENT 14 0 M097801099999 SUBENT M0978011 20190925 M106M097801100001 BIB 3 4 M097801100002 REACTION (54-XE-129(G,3N)54-XE-126,,INT,,,EVAL) M097801100003 ANALYSIS Integration of evaluated cross section. M097801100004 STATUS (DEP,M0978006) Evaluated cross section. M097801100005 (TABLE) Data from Table 1. M097801100006 ENDBIB 4 0 M097801100007 NOCOMMON 0 0 M097801100008 DATA 3 19 M097801100009 EN-MAX DATA DATA-ERR M097801100010 MEV MB*MEV MB*MEV M097801100011 31.20 51.6 4.0 M097801100012 ENDDATA 3 0 M097801100013 ENDSUBENT 12 0 M097801199999 ENDENTRY 11 0 M097899999999