ENTRY M1016 20201207 M110M101600000001 SUBENT M1016001 20201207 M110M101600100001 BIB 10 31 M101600100002 TITLE Photodisintegration of 127I: Systematic uncertainties M101600100003 of experiments and data evaluated using physical M101600100004 criteria. M101600100005 AUTHOR (V.V.Varlamov,A.I.Davydov,V.N.Orlin) M101600100006 REFERENCE (J,AJPA,8,64,2020) M101600100007 #doi:10.11648/j.ajpa.20200805.11 M101600100008 (J,MPM,,(3),1930413,2019) M101600100009 INSTITUTE (4RUSMOS) M101600100010 INC-SOURCE (QMPH,ARAD) M101600100011 ANALYSIS The joint analysis of total (g,xn) and partial ((g,n), M101600100012 (g,2n), (g,3n)) cross sections obtained in different M101600100013 experiments was carried out using a new approach. M101600100014 Such approach consists in analizing the systematic M101600100015 disagreement among data, attributed to the systematic M101600100016 uncertainty. New transitional multiplicity functions M101600100017 Fi-theor = SIG(g,in)/SIG(g,xn) M101600100018 were proposed in the framework of the combined M101600100019 photonucleon reaction model in order to evaluate M101600100020 photonuclear partial reaction cross sections using M101600100021 experimental neutron yields SIG-exp(g,xn), without M101600100022 the problems related to the neutron multiplicity M101600100023 sorting procedure M101600100024 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn). M101600100025 ERR-ANALYS (DATA-ERR) Root-mean-squared errors. M101600100026 COMMENT Integration cross-section data are presented for M101600100027 cross-section data from M0984 (MPM,3,1930413,2019) M101600100028 STATUS (APRVD) Approved by V.Varlamov. M101600100029 HISTORY (20201008C) Data were compiled at the Russia MSU SINP M101600100030 CDFE by V.Varlamov. M101600100031 (20201207A) Corrected by V.Varlamov: TITLE, STATUS, M101600100032 SUBENTs 007 - 011 added. M101600100033 ENDBIB 31 0 M101600100034 NOCOMMON 0 0 M101600100035 ENDSUBENT 34 0 M101600199999 SUBENT M1016002 20201207 M110M101600200001 BIB 4 5 M101600200002 REACTION (53-I-127(G,X)0-NN-1,,INT,,,EVAL) M101600200003 ANALYSIS Integration of evaluated cross section. M101600200004 STATUS (DEP,M1016007) Evaluated cross section. M101600200005 (TABLE) Data from Table 2, Am.J.Phys.Appl.,8,64,2020. M101600200006 HISTORY (20201207A) Corrected by V.Varlamov: STATUS. M101600200007 ENDBIB 5 0 M101600200008 NOCOMMON 0 0 M101600200009 DATA 3 39 M101600200010 EN-MAX DATA DATA-ERR M101600200011 MEV MB*MEV MB*MEV M101600200012 16.29 1142.82 23.20 M101600200013 25.83 2393.77 29.86 M101600200014 31.20 2661.26 31.42 M101600200015 ENDDATA 5 0 M101600200016 ENDSUBENT 15 0 M101600299999 SUBENT M1016003 20201207 M110M101600300001 BIB 4 5 M101600300002 REACTION (53-I-127(G,X)0-NN-1,UNW,INT,,,EVAL) M101600300003 ANALYSIS Integration of evaluated cross section. M101600300004 STATUS (DEP,M1016008) Evaluated cross section. M101600300005 (TABLE) Data from Table 2, Am.J.Phys.Appl.,8,64,2020. M101600300006 HISTORY (20201207A) Corrected by V.Varlamov: STATUS. M101600300007 ENDBIB 5 0 M101600300008 NOCOMMON 0 0 M101600300009 DATA 3 39 M101600300010 EN-MAX DATA DATA-ERR M101600300011 MEV MB*MEV MB*MEV M101600300012 16.29 1142.82 23.20 M101600300013 25.83 2008.23 28.89 M101600300014 31.20 2146.73 29.10 M101600300015 ENDDATA 5 0 M101600300016 ENDSUBENT 15 0 M101600399999 SUBENT M1016004 20201207 M110M101600400001 BIB 4 6 M101600400002 REACTION ((53-I-127(G,N)53-I-126,,INT,,,EVAL)+ M101600400003 (53-I-127(G,N+P)52-TE-125,,INT,,,EVAL)) M101600400004 ANALYSIS Integration of evaluated cross section. M101600400005 STATUS (DEP,M1016009) Evaluated cross section. M101600400006 (TABLE) Data from Table 2, Am.J.Phys.Appl.,8,64,2020. M101600400007 HISTORY (20201207A) Corrected by V.Varlamov: STATUS. M101600400008 ENDBIB 6 0 M101600400009 NOCOMMON 0 0 M101600400010 DATA 3 39 M101600400011 EN-MAX DATA DATA-ERR M101600400012 MEV MB*MEV MB*MEV M101600400013 16.29 1142.82 23.20 M101600400014 25.83 1622.70 26.63 M101600400015 31.20 1650.24 26.67 M101600400016 ENDDATA 5 0 M101600400017 ENDSUBENT 16 0 M101600499999 SUBENT M1016005 20201207 M110M101600500001 BIB 4 5 M101600500002 REACTION (53-I-127(G,2N)53-I-125,,INT,,,EVAL) M101600500003 ANALYSIS Integration of evaluated cross section. M101600500004 STATUS (DEP,M1016010) Evaluated cross section. M101600500005 (TABLE) Data from Table 2, Am.J.Phys.Appl.,8,64,2020. M101600500006 HISTORY (20201207A) Corrected by V.Varlamov: STATUS. M101600500007 ENDBIB 5 0 M101600500008 NOCOMMON 0 0 M101600500009 DATA 3 29 M101600500010 EN-MAX DATA DATA-ERR M101600500011 MEV MB*MEV MB*MEV M101600500012 25.83 385.53 9.54 M101600500013 31.20 478.43 11.47 M101600500014 ENDDATA 4 0 M101600500015 ENDSUBENT 14 0 M101600599999 SUBENT M1016006 20201207 M110M101600600001 BIB 4 5 M101600600002 REACTION (53-I-127(G,3N)53-I-124,,INT,,,EVAL) M101600600003 ANALYSIS Integration of evaluated cross section. M101600600004 STATUS (DEP,M1016011) Evaluated cross section. M101600600005 (TABLE) Data from Table 2, Am.J.Phys.Appl.,8,64,2020. M101600600006 HISTORY (20201207A) Corrected by V.Varlamov: STATUS. M101600600007 ENDBIB 5 0 M101600600008 NOCOMMON 0 0 M101600600009 DATA 3 19 M101600600010 EN-MAX DATA DATA-ERR M101600600011 MEV MB*MEV MB*MEV M101600600012 31.20 18.04 2.07 M101600600013 ENDDATA 3 0 M101600600014 ENDSUBENT 13 0 M101600699999 SUBENT M1016007 20201207 M110M101600700001 BIB 5 20 M101600700002 REACTION (53-I-127(G,X)0-NN-1,,SIG,,,EVAL) M101600700003 ANALYSIS The neutron yield reaction cross section obtained as M101600700004 sum: SIG(g,xn) = SIG(g,1n)+2SIG(g,2n))+3SIG(g,3n). M101600700005 Because experimental data for the total neutron yield M101600700006 reaction (g,xn) cross section for 127I were obtained M101600700007 only up to energy 24.89 MeV in evaluation procedure M101600700008 the sum (g,1n)+2(g,2n)+3(g,3n) of experimental cross M101600700009 sections was obtained up to energy 31.2 MeV. M101600700010 STATUS (TABLE) Data from Fig. 3a, Am.J.Phys.Appl.,8,64,2020. M101600700011 (DEP,L0015003) M101600700012 (DEP,L0015004) M101600700013 (DEP,L0015005) M101600700014 REL-REF (R,L0015003,R.Bergere+,J,NP/A,133,417,1969) M101600700015 Experimental data for (g,1n) reaction cross section. M101600700016 (R,L0015004,R.Bergere+,J,NP/A,133,417,1969) M101600700017 Experimental data for (g,2n) reaction cross section. M101600700018 (R,L0015005,R.Bergere+,J,NP/A,133,417,1969) M101600700019 Experimental data for (g,3n) reaction cross section. M101600700020 HISTORY (20201207C) Data were compiled at the Russia MSU SINP M101600700021 CDFE by V.Varlamov. M101600700022 ENDBIB 20 0 M101600700023 NOCOMMON 0 0 M101600700024 DATA 3 76 M101600700025 EN DATA DATA-ERR M101600700026 MEV MB MB M101600700027 8.89 1.20 8.08 M101600700028 9.16 9.10 8.72 M101600700029 9.44 21.10 9.65 M101600700030 9.71 21.70 9.77 M101600700031 9.98 30.00 10.43 M101600700032 10.25 38.90 11.14 M101600700033 10.52 45.40 11.68 M101600700034 10.80 46.50 11.85 M101600700035 11.07 56.80 12.65 M101600700036 11.34 69.00 13.58 M101600700037 11.61 76.00 14.15 M101600700038 11.88 90.30 15.24 M101600700039 12.16 104.20 16.29 M101600700040 12.43 129.30 18.13 M101600700041 12.70 148.80 19.59 M101600700042 12.97 169.40 21.11 M101600700043 13.24 200.40 23.36 M101600700044 13.52 220.30 24.84 M101600700045 13.79 250.00 27.00 M101600700046 14.06 272.10 28.63 M101600700047 14.33 296.30 30.41 M101600700048 14.60 300.70 30.80 M101600700049 14.88 308.10 36.56 M101600700050 15.15 300.20 36.06 M101600700051 15.42 298.90 36.02 M101600700052 15.69 285.70 35.15 M101600700053 15.96 277.00 34.59 M101600700054 16.24 261.95 33.43 M101600700055 16.51 255.62 33.05 M101600700056 16.78 248.90 30.36 M101600700057 17.05 251.17 27.02 M101600700058 17.32 242.50 22.50 M101600700059 17.60 236.58 19.72 M101600700060 17.87 230.10 18.47 M101600700061 18.14 218.34 17.67 M101600700062 18.41 209.43 17.42 M101600700063 18.68 195.80 17.10 M101600700064 18.96 182.55 16.71 M101600700065 19.23 164.99 16.19 M101600700066 19.50 168.30 16.55 M101600700067 19.77 147.94 15.71 M101600700068 20.04 147.34 15.95 M101600700069 20.32 128.58 15.40 M101600700070 20.59 118.09 14.97 M101600700071 20.86 119.50 15.07 M101600700072 21.13 103.68 14.37 M101600700073 21.40 96.53 14.05 M101600700074 21.68 94.75 13.77 M101600700075 21.95 81.97 13.22 M101600700076 22.22 78.57 13.07 M101600700077 22.49 79.73 13.16 M101600700078 22.76 66.93 9.55 M101600700079 23.04 67.71 9.56 M101600700080 23.31 63.63 9.39 M101600700081 23.58 60.59 9.43 M101600700082 23.85 60.96 9.44 M101600700083 24.12 61.54 9.47 M101600700084 24.40 56.26 9.25 M101600700085 24.67 53.93 9.15 M101600700086 24.94 38.22 8.47 M101600700087 25.21 59.58 9.57 M101600700088 25.48 51.74 9.22 M101600700089 25.76 57.72 11.29 M101600700090 26.03 53.99 11.13 M101600700091 26.30 61.35 11.45 M101600700092 26.57 63.60 11.55 M101600700093 26.84 61.85 11.27 M101600700094 27.12 55.34 10.78 M101600700095 27.66 51.40 10.07 M101600700096 28.20 48.64 9.28 M101600700097 28.48 46.04 8.55 M101600700098 29.02 45.59 7.83 M101600700099 29.56 38.63 7.09 M101600700100 30.11 48.36 7.11 M101600700101 30.65 40.09 6.77 M101600700102 31.20 40.89 6.83 M101600700103 ENDDATA 78 0 M101600700104 ENDSUBENT 103 0 M101600799999 SUBENT M1016008 20201207 M110M101600800001 BIB 4 12 M101600800002 REACTION (53-I-127(G,X)0-NN-1,UNW,SIG,,,EVAL) M101600800003 ANALYSIS The total neutron reaction cross section obtained as M101600800004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M101600800005 STATUS (TABLE) Data from Fig. 3b, Am.J.Phys.Appl.,8,64,2020. M101600800006 (DEP,M0984004) M101600800007 Evaluated (g,1n) reaction cross section. M101600800008 (DEP,M0984005) M101600800009 Evaluated (g,2n) reaction cross section. M101600800010 (DEP,M0984006) M101600800011 Evaluated (g,3n) reaction cross section. M101600800012 HISTORY (20201207C) Data were compiled at the Russia MSU SINP M101600800013 CDFE by V.Varlamov. M101600800014 ENDBIB 12 0 M101600800015 NOCOMMON 0 0 M101600800016 DATA 3 76 M101600800017 EN DATA DATA-ERR M101600800018 MEV MB MB M101600800019 8.89 1.20 8.08 M101600800020 9.16 9.10 8.72 M101600800021 9.44 21.10 9.65 M101600800022 9.71 21.70 9.77 M101600800023 9.98 30.00 10.43 M101600800024 10.25 38.90 11.14 M101600800025 10.52 45.40 11.68 M101600800026 10.80 46.50 11.85 M101600800027 11.07 56.80 12.65 M101600800028 11.34 69.00 13.58 M101600800029 11.61 76.00 14.15 M101600800030 11.88 90.30 15.24 M101600800031 12.16 104.20 16.29 M101600800032 12.43 129.30 18.13 M101600800033 12.70 148.80 19.59 M101600800034 12.97 169.40 21.11 M101600800035 13.24 200.40 23.36 M101600800036 13.52 220.30 24.84 M101600800037 13.79 250.00 27.00 M101600800038 14.06 272.10 28.63 M101600800039 14.33 296.30 30.41 M101600800040 14.60 300.70 30.80 M101600800041 14.88 308.10 36.56 M101600800042 15.15 300.20 36.06 M101600800043 15.42 298.90 36.02 M101600800044 15.69 285.70 35.15 M101600800045 15.96 277.00 34.59 M101600800046 16.24 261.95 33.43 M101600800047 16.51 255.62 33.05 M101600800048 16.78 241.20 30.34 M101600800049 17.05 228.11 26.85 M101600800050 17.32 202.08 21.86 M101600800051 17.60 180.49 18.23 M101600800052 17.87 164.36 16.16 M101600800053 18.14 147.05 14.57 M101600800054 18.41 134.63 13.73 M101600800055 18.68 121.88 13.10 M101600800056 18.96 111.04 12.57 M101600800057 19.23 98.66 12.04 M101600800058 19.50 98.90 12.18 M101600800059 19.77 86.30 11.51 M101600800060 20.04 85.06 11.63 M101600800061 20.32 73.47 11.17 M101600800062 20.59 67.48 10.86 M101600800063 20.86 67.76 10.90 M101600800064 21.13 59.25 10.39 M101600800065 21.40 55.58 10.16 M101600800066 21.68 54.29 9.94 M101600800067 21.95 47.32 9.55 M101600800068 22.22 45.36 9.42 M101600800069 22.49 46.03 9.48 M101600800070 22.76 38.64 6.88 M101600800071 23.04 39.09 6.88 M101600800072 23.31 36.74 6.76 M101600800073 23.58 34.88 6.78 M101600800074 23.85 34.83 6.77 M101600800075 24.12 35.17 6.79 M101600800076 24.40 31.90 6.63 M101600800077 24.67 30.58 6.56 M101600800078 24.94 21.67 6.07 M101600800079 25.21 33.44 6.84 M101600800080 25.48 29.04 6.59 M101600800081 25.76 32.40 8.07 M101600800082 26.03 30.31 7.95 M101600800083 26.30 34.43 8.18 M101600800084 26.57 35.70 8.25 M101600800085 26.84 34.50 8.04 M101600800086 27.12 30.94 7.69 M101600800087 27.66 28.13 7.19 M101600800088 28.20 25.63 6.60 M101600800089 28.48 23.76 6.06 M101600800090 29.02 22.80 5.49 M101600800091 29.56 18.50 4.85 M101600800092 30.11 22.40 4.71 M101600800093 30.65 18.15 4.38 M101600800094 31.20 17.84 4.28 M101600800095 ENDDATA 78 0 M101600800096 ENDSUBENT 95 0 M101600899999 SUBENT M1016009 20201207 M110M101600900001 BIB 5 22 M101600900002 REACTION ((53-I-127(G,N)53-I-126,,SIG,,,EVAL)+ M101600900003 (53-I-127(G,N+P)52-TE-125,,SIG,,,EVAL)) M101600900004 ANALYSIS The contribution of partial reaction (g,1n) cross M101600900005 section into the experimental total neutron yield M101600900006 reaction (g,xn) cross section obtained using M101600900007 quasimonoenergetic annihilation photons at Livermore M101600900008 (USA) was evaluated using specially theoretically M101600900009 calculated transitional multiplicity function - M101600900010 ratio M101600900011 F1-theor = SIG-theor(g,1n)/SIG-theor(g,xn) M101600900012 by the way M101600900013 SIG-eval(g,1n) = (F1-theor)x(SIG-exp(g,xn)). M101600900014 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M101600900015 Theoretical preequilibrium model of photonuclear M101600900016 reactions based on the Fermi gas densities. M101600900017 STATUS (TABLE) Data from Fig. 3c, Am.J.Phys.Appl.,8,64,2020. M101600900018 (DEP,M0984002) M101600900019 The neutron yield reaction 127I(g,xn) cross section M101600900020 obtained up to energy 31.2 MeV as sum of experimental M101600900021 partial reaction cross sections. M101600900022 HISTORY (20201207C) Data were compiled at the Russia MSU SINP M101600900023 CDFE by V.Varlamov. M101600900024 ENDBIB 22 0 M101600900025 NOCOMMON 0 0 M101600900026 DATA 3 76 M101600900027 EN DATA DATA-ERR M101600900028 MEV MB MB M101600900029 8.89 1.20 8.08 M101600900030 9.16 9.10 8.72 M101600900031 9.44 21.10 9.65 M101600900032 9.71 21.70 9.77 M101600900033 9.98 30.00 10.43 M101600900034 10.25 38.90 11.14 M101600900035 10.52 45.40 11.68 M101600900036 10.80 46.50 11.85 M101600900037 11.07 56.80 12.65 M101600900038 11.34 69.00 13.58 M101600900039 11.61 76.00 14.15 M101600900040 11.88 90.30 15.24 M101600900041 12.16 104.20 16.29 M101600900042 12.43 129.30 18.13 M101600900043 12.70 148.80 19.59 M101600900044 12.97 169.40 21.11 M101600900045 13.24 200.40 23.36 M101600900046 13.52 220.30 24.84 M101600900047 13.79 250.00 27.00 M101600900048 14.06 272.10 28.63 M101600900049 14.33 296.30 30.41 M101600900050 14.60 300.70 30.80 M101600900051 14.88 308.10 36.56 M101600900052 15.15 300.20 36.06 M101600900053 15.42 298.90 36.02 M101600900054 15.69 285.70 35.15 M101600900055 15.96 277.00 34.59 M101600900056 16.24 261.95 33.43 M101600900057 16.51 255.62 33.05 M101600900058 16.78 233.51 30.32 M101600900059 17.05 205.04 26.68 M101600900060 17.32 161.66 21.21 M101600900061 17.60 124.39 16.62 M101600900062 17.87 98.62 13.44 M101600900063 18.14 75.75 10.61 M101600900064 18.41 59.84 8.58 M101600900065 18.68 47.95 7.13 M101600900066 18.96 39.52 6.08 M101600900067 19.23 32.32 5.27 M101600900068 19.50 29.50 4.76 M101600900069 19.77 24.66 4.28 M101600900070 20.04 22.79 3.99 M101600900071 20.32 18.37 3.53 M101600900072 20.59 16.87 3.43 M101600900073 20.86 16.02 3.22 M101600900074 21.13 14.81 3.08 M101600900075 21.40 14.63 3.04 M101600900076 21.68 13.82 2.83 M101600900077 21.95 12.68 2.76 M101600900078 22.22 12.15 2.59 M101600900079 22.49 12.33 2.60 M101600900080 22.76 10.35 1.89 M101600900081 23.04 10.47 1.81 M101600900082 23.31 9.84 1.78 M101600900083 23.58 9.18 1.74 M101600900084 23.85 8.71 1.61 M101600900085 24.12 8.79 1.62 M101600900086 24.40 7.54 1.51 M101600900087 24.67 7.23 1.50 M101600900088 24.94 5.12 1.39 M101600900089 25.21 7.30 1.39 M101600900090 25.48 6.34 1.34 M101600900091 25.76 7.07 1.64 M101600900092 26.03 6.61 1.62 M101600900093 26.30 7.51 1.67 M101600900094 26.57 7.79 1.68 M101600900095 26.84 7.16 1.52 M101600900096 27.12 6.55 1.48 M101600900097 27.66 5.95 1.45 M101600900098 28.20 4.71 1.20 M101600900099 28.48 4.46 1.19 M101600900100 29.02 4.37 1.18 M101600900101 29.56 3.29 1.00 M101600900102 30.11 4.07 1.04 M101600900103 30.65 3.38 1.00 M101600900104 31.20 3.05 0.86 M101600900105 ENDDATA 78 0 M101600900106 ENDSUBENT 105 0 M101600999999 SUBENT M1016010 20201207 M110M101601000001 BIB 5 21 M101601000002 REACTION (53-I-127(G,2N)53-I-125,,SIG,,,EVAL) M101601000003 ANALYSIS The contribution of partial reaction (g,2n) cross M101601000004 section into the experimental total neutron yield M101601000005 reaction (g,xn) cross section obtained using M101601000006 quasimonoenergetic annihilation photons at Livermore M101601000007 (USA) was evaluated using specially theoretically M101601000008 calculated transitional multiplicity function - M101601000009 ratio M101601000010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M101601000011 by the way M101601000012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M101601000013 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M101601000014 Theoretical preequilibrium model of photonuclear M101601000015 reactions based on the Fermi gas densities. M101601000016 STATUS (TABLE) Data from Fig. 3d, Am.J.Phys.Appl.,8,64,2020. M101601000017 (DEP,M0984002) M101601000018 The neutron yield reaction 127I(g,xn) cross section M101601000019 obtained up to energy 31.2 MeV as sum of experimental M101601000020 partial reaction cross sections. M101601000021 HISTORY (20201207C) Data were compiled at the Russia MSU SINP M101601000022 CDFE by V.Varlamov. M101601000023 ENDBIB 21 0 M101601000024 NOCOMMON 0 0 M101601000025 DATA 3 47 M101601000026 EN DATA DATA-ERR M101601000027 MEV MB MB M101601000028 16.78 7.70 1.00 M101601000029 17.05 23.07 3.00 M101601000030 17.32 40.42 5.30 M101601000031 17.60 56.10 7.50 M101601000032 17.87 65.74 8.96 M101601000033 18.14 71.30 9.99 M101601000034 18.41 74.80 10.72 M101601000035 18.68 73.93 10.99 M101601000036 18.96 71.52 11.00 M101601000037 19.23 66.34 10.82 M101601000038 19.50 69.40 11.21 M101601000039 19.77 61.64 10.69 M101601000040 20.04 62.28 10.92 M101601000041 20.32 55.10 10.60 M101601000042 20.59 50.61 10.30 M101601000043 20.86 51.74 10.41 M101601000044 21.13 44.44 9.92 M101601000045 21.40 40.95 9.70 M101601000046 21.68 40.47 9.53 M101601000047 21.95 34.65 9.14 M101601000048 22.22 33.21 9.06 M101601000049 22.49 33.70 9.12 M101601000050 22.76 28.29 6.62 M101601000051 23.04 28.62 6.64 M101601000052 23.31 26.90 6.52 M101601000053 23.58 25.70 6.55 M101601000054 23.85 26.12 6.58 M101601000055 24.12 26.38 6.60 M101601000056 24.40 24.36 6.46 M101601000057 24.67 23.35 6.38 M101601000058 24.94 16.55 5.91 M101601000059 25.21 26.14 6.69 M101601000060 25.48 22.70 6.45 M101601000061 25.76 25.33 7.90 M101601000062 26.03 23.69 7.79 M101601000063 26.30 26.92 8.01 M101601000064 26.57 27.91 8.08 M101601000065 26.84 27.34 7.90 M101601000066 27.12 24.40 7.55 M101601000067 27.66 21.10 7.03 M101601000068 28.20 18.83 6.45 M101601000069 28.48 16.34 5.85 M101601000070 29.02 14.07 5.12 M101601000071 29.56 10.28 4.28 M101601000072 30.11 10.69 3.74 M101601000073 30.65 7.60 3.10 M101601000074 31.20 6.53 2.59 M101601000075 ENDDATA 49 0 M101601000076 ENDSUBENT 75 0 M101601099999 SUBENT M1016011 20201207 M110M101601100001 BIB 5 21 M101601100002 REACTION (53-I-127(G,3N)53-I-124,,SIG,,,EVAL) M101601100003 ANALYSIS The contribution of partial reaction (g,3n) cross M101601100004 section into the experimental total neutron yield M101601100005 reaction (g,xn) cross section obtained using M101601100006 quasimonoenergetic annihilation photons at Livermore M101601100007 (USA) was evaluated using specially theoretically M101601100008 calculated transitional multiplicity function - M101601100009 ratio M101601100010 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M101601100011 by the way M101601100012 SIG-eval(g,3n) = (F2-theor)x(SIG-exp(g,xn)). M101601100013 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M101601100014 Theoretical preequilibrium model of photonuclear M101601100015 reactions based on the Fermi gas densities. M101601100016 STATUS (TABLE) Data from Fig. 3e, Am.J.Phys.Appl.,8,64,2020. M101601100017 (DEP,L0016006) M101601100018 The neutron yield reaction 127I(g,xn) cross section M101601100019 obtained up to energy 31.2 MeV as sum of experimental M101601100020 partial reaction cross sections. M101601100021 HISTORY (20201207C) Data were compiled at the Russia MSU SINP M101601100022 CDFE by V.Varlamov. M101601100023 ENDBIB 21 0 M101601100024 NOCOMMON 0 0 M101601100025 DATA 3 8 M101601100026 EN DATA DATA-ERR M101601100027 MEV MB MB M101601100028 27.66 1.08 0.36 M101601100029 28.20 2.09 0.72 M101601100030 28.48 2.97 1.06 M101601100031 29.02 4.37 1.59 M101601100032 29.56 4.93 2.06 M101601100033 30.11 7.64 2.67 M101601100034 30.65 7.17 2.92 M101601100035 31.20 8.27 3.29 M101601100036 ENDDATA 10 0 M101601100037 ENDSUBENT 36 0 M101601199999 ENDENTRY 11 0 M101699999999