ENTRY M0863 20160411 M083M086300000001 SUBENT M0863001 20160411 M083M086300100001 BIB 9 37 M086300100002 TITLE Cross sections of partial photoneutron reactions for M086300100003 the 115In nucleus and the neutron multiplicity M086300100004 sorting. M086300100005 AUTHOR (V.V.Varlamov,V.N.Orlin,N.N.Peskov,M.E.Stepanov) M086300100006 REFERENCE (J,IZV,77,(4),433,2013) M086300100007 (J,BAS,77,(4),388,2013) M086300100008 #doi:10.3103/S1062873813040291 M086300100009 English translation of J,IZV,77,(4),433,2013. M086300100010 INSTITUTE (4RUSMOS) M086300100011 INC-SOURCE (QMPH,ARAD) M086300100012 STATUS (TABLE,APRVD) Approved by V.Varlamov. M086300100013 ANALYSIS The joint analysis of data for total (g,xn) and M086300100014 partial (g,n), (g,2n) and (g,3n) reactions obtained M086300100015 for 115 In in various experiments was carried out. M086300100016 Using specially proposed transitional multiplicity M086300100017 functions M086300100018 Fi-theor = SIG(g,in)/SIG(g,xn) M086300100019 calculated in the frame of combined photonuclear M086300100020 reaction model new reliable and free from problems M086300100021 of neutron multiplicity sorting data for M086300100022 photoneutron partial reactions cross sections M086300100023 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M086300100024 were evaluated using experimental neutron yield M086300100025 reaction cross section SIG-exp(g,xn). M086300100026 There was good agreement between 115In(g,xn) reaction M086300100027 cross sections obtained at Livermore and Saclay. M086300100028 However, since the Livermore cross section was M086300100029 determined in broader energy range (up to 31 MeV, M086300100030 but at Saclay only up to 24 MeV) that was covered M086300100031 energy range above B3n threshold of (g,3n) reaction, M086300100032 that was used as the source value for evaluation M086300100033 procedure. M086300100034 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M086300100035 HISTORY (20130905C) Data were compiled at the Russia MSU SINP M086300100036 CDFE by V.Varlamov. M086300100037 (20160411A) Corrected by V.Varlamov: REACTION in M086300100038 SUBENTS 003, 004, 005. M086300100039 ENDBIB 37 0 M086300100040 NOCOMMON 0 0 M086300100041 ENDSUBENT 40 0 M086300199999 SUBENT M0863002 20130905 M068M086300200001 BIB 4 19 M086300200002 REACTION ((49-IN-115(G,N)49-IN-114,,SIG,,,EVAL)+ M086300200003 (49-IN-115(G,N+P)48-CD-113,,SIG,,,EVAL)) M086300200004 ANALYSIS The contribution of partial reaction (g,n) cross M086300200005 section into the experimental total neutron yield M086300200006 reaction (g,xn) cross section obtained using M086300200007 quasimonoenergetic annihilation photons at M086300200008 Livermore (USA) was evaluated using specially M086300200009 theoretically calculated transitional multiplicity M086300200010 function - ratio M086300200011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M086300200012 by the way M086300200013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M086300200014 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M086300200015 Theoretical preequilibrium model of photonuclear M086300200016 reactions based on the Fermi gas densities. M086300200017 STATUS Data plotted in Fig. 4. M086300200018 (DEP,L0017002) M086300200019 The total neutron yield reaction (g,xn) cross M086300200020 section. M086300200021 ENDBIB 19 0 M086300200022 NOCOMMON 0 0 M086300200023 DATA 3 81 M086300200024 EN DATA DATA-ERR M086300200025 MEV MB MB M086300200026 9.097 -0.78 0.16 M086300200027 9.407 3.83 0.43 M086300200028 9.717 11.88 1.27 M086300200029 10.026 19.03 2.02 M086300200030 10.336 25.56 2.67 M086300200031 10.646 33.08 3.45 M086300200032 10.955 40.29 4.18 M086300200033 11.265 43.78 4.59 M086300200034 11.575 53.48 5.45 M086300200035 11.885 64.7 6.60 M086300200036 12.194 73.38 7.47 M086300200037 12.504 91.52 9.39 M086300200038 12.814 103.86 10.51 M086300200039 13.123 120.47 12.29 M086300200040 13.433 139.32 14.07 M086300200041 13.743 160.85 16.38 M086300200042 14.053 190.38 19.12 M086300200043 14.362 216.2 21.83 M086300200044 14.517 226.4 22.80 M086300200045 14.672 234.8 23.57 M086300200046 14.827 248.8 24.96 M086300200047 14.982 250.4 25.22 M086300200048 15.136 255.1 25.69 M086300200049 15.291 264.7 26.65 M086300200050 15.446 261.9 26.40 M086300200051 15.601 265.49 26.70 M086300200052 15.756 261.76 26.64 M086300200053 15.911 256.19 25.81 M086300200054 16.066 252.58 25.76 M086300200055 16.22 247.68 24.86 M086300200056 16.375 238.31 24.42 M086300200057 16.53 225.79 23.21 M086300200058 16.685 207.46 21.24 M086300200059 16.84 186.60 18.76 M086300200060 16.995 165.04 16.85 M086300200061 17.15 148.01 14.91 M086300200062 17.304 129.14 13.19 M086300200063 17.459 113.67 11.48 M086300200064 17.769 88.87 9.03 M086300200065 18.079 70.83 7.27 M086300200066 18.388 57.32 5.90 M086300200067 18.698 47.31 4.89 M086300200068 19.008 37.75 3.93 M086300200069 19.317 34.32 3.58 M086300200070 19.627 29.63 3.12 M086300200071 19.937 26.07 2.78 M086300200072 20.247 24.87 2.67 M086300200073 20.556 24.45 2.67 M086300200074 20.866 21.72 2.32 M086300200075 21.176 22.01 2.38 M086300200076 21.485 22.47 2.42 M086300200077 21.795 20.47 2.16 M086300200078 22.105 19.85 2.29 M086300200079 22.414 19.98 2.18 M086300200080 22.724 17.43 2.06 M086300200081 23.034 17.41 1.93 M086300200082 23.344 16.23 2.00 M086300200083 23.653 16.27 1.81 M086300200084 23.963 13.11 1.76 M086300200085 24.273 13.53 1.59 M086300200086 24.582 10.04 1.52 M086300200087 24.892 13.33 1.82 M086300200088 25.202 14.35 2.06 M086300200089 25.511 13.69 1.95 M086300200090 25.821 10.33 1.82 M086300200091 26.131 10.25 1.77 M086300200092 26.441 8.99 1.40 M086300200093 26.75 8.49 1.43 M086300200094 27.06 8.00 1.38 M086300200095 27.37 6.77 1.31 M086300200096 27.679 7.24 1.70 M086300200097 27.989 6.39 1.66 M086300200098 28.299 5.58 1.62 M086300200099 28.608 5.16 1.50 M086300200100 28.918 5.57 1.58 M086300200101 29.228 4.59 1.07 M086300200102 29.538 5.47 1.47 M086300200103 29.847 5.86 1.83 M086300200104 30.157 4.22 2.05 M086300200105 30.467 5.58 1.79 M086300200106 31.086 8.59 2.10 M086300200107 ENDDATA 83 0 M086300200108 ENDSUBENT 107 0 M086300299999 SUBENT M0863003 20160411 M083M086300300001 BIB 5 21 M086300300002 REACTION ((49-IN-115(G,2N)49-IN-113,,SIG,,,EVAL)+ M086300300003 (49-IN-115(G,2N+P)48-CD-112,,SIG,,,EVAL)) M086300300004 ANALYSIS The contribution of partial reaction (g,2n) cross M086300300005 section into the experimental total neutron yield M086300300006 reaction (g,xn) cross section obtained using M086300300007 quasimonoenergetic annihilation photons at M086300300008 Livermore (USA) was evaluated using specially M086300300009 theoretically calculated transitional multiplicity M086300300010 function - ratio M086300300011 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M086300300012 by the way M086300300013 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M086300300014 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M086300300015 Theoretical preequilibrium model of photonuclear M086300300016 reactions based on the Fermi gas densities. M086300300017 STATUS Data plotted in Fig. 4. M086300300018 (DEP,L0017002) M086300300019 The neutron yield reaction (g,xn) cross M086300300020 section. M086300300021 HISTORY (20160411A) Corrected by V.Varlamov: Target and final M086300300022 nuclei. M086300300023 ENDBIB 21 0 M086300300024 NOCOMMON 0 0 M086300300025 DATA 3 51 M086300300026 EN DATA DATA-ERR M086300300027 MEV MB MB M086300300028 16.375 0.95 0.10 M086300300029 16.53 4.18 0.43 M086300300030 16.685 12.96 1.33 M086300300031 16.84 23.20 2.33 M086300300032 16.995 32.63 3.33 M086300300033 17.15 41.75 4.21 M086300300034 17.304 48.69 4.97 M086300300035 17.459 54.40 5.49 M086300300036 17.769 63.28 6.43 M086300300037 18.079 69.37 7.12 M086300300038 18.388 72.11 7.43 M086300300039 18.698 73.30 7.57 M086300300040 19.008 68.71 7.15 M086300300041 19.317 71.05 7.42 M086300300042 19.627 67.22 7.08 M086300300043 19.937 62.75 6.70 M086300300044 20.247 61.08 6.56 M086300300045 20.556 58.97 6.45 M086300300046 20.866 49.88 5.32 M086300300047 21.176 47.50 5.13 M086300300048 21.485 45.83 4.93 M086300300049 21.795 40.23 4.24 M086300300050 22.105 38.31 4.42 M086300300051 22.414 38.59 4.22 M086300300052 22.724 34.07 4.02 M086300300053 23.034 34.69 3.85 M086300300054 23.344 33.05 4.08 M086300300055 23.653 33.90 3.78 M086300300056 23.963 27.87 3.74 M086300300057 24.273 29.37 3.45 M086300300058 24.582 22.20 3.37 M086300300059 24.892 29.93 4.09 M086300300060 25.202 32.64 4.69 M086300300061 25.511 31.50 4.50 M086300300062 25.821 23.97 4.22 M086300300063 26.131 23.90 4.14 M086300300064 26.441 20.88 3.26 M086300300065 26.75 19.45 3.27 M086300300066 27.06 17.88 3.08 M086300300067 27.37 14.60 2.83 M086300300068 27.679 14.97 3.51 M086300300069 27.989 12.58 3.26 M086300300070 28.299 10.40 3.01 M086300300071 28.608 9.06 2.63 M086300300072 28.918 9.22 2.62 M086300300073 29.228 7.19 1.68 M086300300074 29.538 8.07 2.17 M086300300075 29.847 8.14 2.54 M086300300076 30.157 5.52 2.68 M086300300077 30.467 6.90 2.22 M086300300078 31.086 9.59 2.34 M086300300079 ENDDATA 53 0 M086300300080 ENDSUBENT 79 0 M086300399999 SUBENT M0863004 20160411 M083M086300400001 BIB 5 21 M086300400002 REACTION ((49-IN-115(G,3N)49-IN-112,,SIG,,,EVAL)+ M086300400003 (49-IN-115(G,3N+P)48-CD-111,,SIG,,,EVAL)) M086300400004 ANALYSIS The contribution of partial reaction (g,3n) cross M086300400005 section into the experimental total neutron yield M086300400006 reaction (g,xn) cross section obtained using M086300400007 quasimonoenergetic annihilation photons at M086300400008 Livermore (USA) was evaluated using specially M086300400009 theoretically calculated transitional multiplicity M086300400010 function - ratio M086300400011 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M086300400012 by the way M086300400013 SIG-eval(g,3n) = (F3-theor)x(SIG-exp(g,xn)). M086300400014 REL-REF (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M086300400015 Theoretical preequilibrium model of photonuclear M086300400016 reactions based on the Fermi gas densities. M086300400017 STATUS Data plotted in Fig. 4. M086300400018 (DEP,L0017002) M086300400019 The neutron yield reaction (g,xn) cross M086300400020 section. M086300400021 HISTORY (20160411A) Corrected by V.Varlamov: Target and final M086300400022 nuclei. M086300400023 ENDBIB 21 0 M086300400024 NOCOMMON 0 0 M086300400025 DATA 3 18 M086300400026 EN DATA DATA-ERR M086300400027 MEV MB MB M086300400028 25.511 -7.31E-5 1.04E-5 M086300400029 25.821 0.003 5.02E-4 M086300400030 26.131 0.06 0.01 M086300400031 26.441 0.25 0.04 M086300400032 26.75 0.60 0.10 M086300400033 27.06 1.07 0.18 M086300400034 27.37 1.47 0.28 M086300400035 27.679 2.28 0.53 M086300400036 27.989 2.70 0.70 M086300400037 28.299 3.00 0.87 M086300400038 28.608 3.38 0.98 M086300400039 28.918 4.30 1.22 M086300400040 29.228 4.06 0.95 M086300400041 29.538 5.44 1.46 M086300400042 29.847 6.46 2.01 M086300400043 30.157 5.08 2.46 M086300400044 30.467 7.22 2.32 M086300400045 31.086 12.55 3.07 M086300400046 ENDDATA 20 0 M086300400047 ENDSUBENT 46 0 M086300499999 SUBENT M0863005 20160411 M083M086300500001 BIB 4 11 M086300500002 REACTION (49-IN-115(G,X)0-NN-1,UNW,SIG,,,EVAL) M086300500003 ANALYSIS The total neutron reaction cross section obtained M086300500004 as sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M086300500005 STATUS Data plotted in Fig. 4. M086300500006 (DEP,M0863002) M086300500007 Evaluated (g,n) reaction cross section. M086300500008 (DEP,M0863003) M086300500009 Evaluated (g,2n) reaction cross section. M086300500010 (DEP,M0863004) M086300500011 Evaluated (g,3n) reaction cross section. M086300500012 HISTORY (20160411A) Corrected by V.Varlamov: Target nucleus. M086300500013 ENDBIB 11 0 M086300500014 NOCOMMON 0 0 M086300500015 DATA 3 81 M086300500016 EN DATA DATA-ERR M086300500017 MEV MB MB M086300500018 9.097 -0.78 0.16 M086300500019 9.407 3.83 0.43 M086300500020 9.717 11.88 1.27 M086300500021 10.026 19.03 2.02 M086300500022 10.336 25.56 2.67 M086300500023 10.646 33.08 3.45 M086300500024 10.955 40.29 4.18 M086300500025 11.265 43.78 4.59 M086300500026 11.575 53.48 5.45 M086300500027 11.885 64.70 6.60 M086300500028 12.194 73.38 7.47 M086300500029 12.504 91.52 9.39 M086300500030 12.814 103.86 10.51 M086300500031 13.123 120.47 12.29 M086300500032 13.433 139.32 14.07 M086300500033 13.743 160.85 16.38 M086300500034 14.053 190.38 19.12 M086300500035 14.362 216.20 21.83 M086300500036 14.517 226.40 22.80 M086300500037 14.672 234.80 23.57 M086300500038 14.827 248.80 24.96 M086300500039 14.982 250.40 25.22 M086300500040 15.136 255.10 25.69 M086300500041 15.291 264.70 26.65 M086300500042 15.446 261.90 26.40 M086300500043 15.601 265.49 26.70 M086300500044 15.756 261.76 26.64 M086300500045 15.911 256.19 25.81 M086300500046 16.066 252.58 25.76 M086300500047 16.22 247.68 24.86 M086300500048 16.375 239.27 24.42 M086300500049 16.53 229.98 23.21 M086300500050 16.685 220.43 21.28 M086300500051 16.84 209.81 18.91 M086300500052 16.995 197.67 17.18 M086300500053 17.15 189.76 15.50 M086300500054 17.304 177.82 14.09 M086300500055 17.459 168.07 12.73 M086300500056 17.769 152.15 11.10 M086300500057 18.079 140.21 10.18 M086300500058 18.388 129.44 9.49 M086300500059 18.698 120.61 9.01 M086300500060 19.008 106.46 8.16 M086300500061 19.317 105.37 8.24 M086300500062 19.627 96.85 7.73 M086300500063 19.937 88.81 7.25 M086300500064 20.247 85.95 7.08 M086300500065 20.556 83.43 6.98 M086300500066 20.866 71.59 5.80 M086300500067 21.176 69.50 5.65 M086300500068 21.485 68.29 5.49 M086300500069 21.795 60.69 4.75 M086300500070 22.105 58.15 4.98 M086300500071 22.414 58.58 4.75 M086300500072 22.724 51.50 4.52 M086300500073 23.034 52.11 4.31 M086300500074 23.344 49.28 4.55 M086300500075 23.653 50.17 4.19 M086300500076 23.963 40.99 4.13 M086300500077 24.273 42.90 3.80 M086300500078 24.582 32.24 3.70 M086300500079 24.892 43.27 4.47 M086300500080 25.202 46.99 5.12 M086300500081 25.511 45.20 4.90 M086300500082 25.821 34.30 4.60 M086300500083 26.131 34.21 4.50 M086300500084 26.441 30.12 3.54 M086300500085 26.75 28.54 3.57 M086300500086 27.06 26.95 3.38 M086300500087 27.37 22.84 3.13 M086300500088 27.679 24.50 3.93 M086300500089 27.989 21.66 3.73 M086300500090 28.299 18.99 3.53 M086300500091 28.608 17.60 3.18 M086300500092 28.918 19.09 3.29 M086300500093 29.228 15.84 2.21 M086300500094 29.538 18.97 3.01 M086300500095 29.847 20.47 3.72 M086300500096 30.157 14.82 4.18 M086300500097 30.467 19.70 3.68 M086300500098 31.086 30.73 4.39 M086300500099 ENDDATA 83 0 M086300500100 ENDSUBENT 99 0 M086300599999 SUBENT M0863006 20130905 M068M086300600001 BIB 3 4 M086300600002 REACTION (49-IN-115(G,X)0-NN-1,UNW,INT,,,EVAL) M086300600003 ANALYSIS Integration of evaluated cross section. M086300600004 STATUS (DEP,M0863005) Evaluated cross section. M086300600005 Data from the Table 2. M086300600006 ENDBIB 4 0 M086300600007 NOCOMMON 0 0 M086300600008 DATA 3 2 M086300600009 EN-MAX DATA DATA-ERR M086300600010 MEV MB*MEV MB*MEV M086300600011 24. 1687. 22.7 M086300600012 31.1 1889. M086300600013 ENDDATA 4 0 M086300600014 ENDSUBENT 13 0 M086300699999 SUBENT M0863007 20130905 M068M086300700001 BIB 3 5 M086300700002 REACTION ((49-IN-115(G,N)49-IN-114,,INT,,,EVAL)+ M086300700003 (49-IN-115(G,N+P)48-CD-113,,INT,,,EVAL)) M086300700004 ANALYSIS Integration of evaluated cross section. M086300700005 STATUS (DEP,M0863002) Evaluated cross section. M086300700006 Data from the Table 2. M086300700007 ENDBIB 5 0 M086300700008 NOCOMMON 0 0 M086300700009 DATA 3 2 M086300700010 EN-MAX DATA DATA-ERR M086300700011 MEV MB*MEV MB*MEV M086300700012 24. 1311.4 21. M086300700013 31.1 1371.3 M086300700014 ENDDATA 4 0 M086300700015 ENDSUBENT 14 0 M086300799999 SUBENT M0863008 20130905 M068M086300800001 BIB 3 5 M086300800002 REACTION ((49-IN-115(G,2N)49-IN-113,,INT,,,EVAL)+ M086300800003 (49-IN-115(G,2N+P)48-CD-112,,INT,,,EVAL)) M086300800004 ANALYSIS Integration of evaluated cross section. M086300800005 STATUS (DEP,M0863003) Evaluated cross section. M086300800006 Data from the Table 2. M086300800007 ENDBIB 5 0 M086300800008 NOCOMMON 0 0 M086300800009 DATA 3 2 M086300800010 EN-MAX DATA DATA-ERR M086300800011 MEV MB*MEV MB*MEV M086300800012 24. 376.2 8.4 M086300800013 31.1 494.2 M086300800014 ENDDATA 4 0 M086300800015 ENDSUBENT 14 0 M086300899999 SUBENT M0863009 20130905 M068M086300900001 BIB 4 8 M086300900002 REACTION ((49-IN-115(G,3N)49-IN-112,,INT,,,EVAL)+ M086300900003 (49-IN-115(G,3N+P)48-CD-111,,INT,,,EVAL)) M086300900004 ANALYSIS Integration of evaluated cross section. M086300900005 STATUS (DEP,M0500004) Evaluated cross section. M086300900006 Data from the Table 2. M086300900007 CRITIQUE All integrated cross section data for M086300900008 EN-MAX = 24 MeV are equal to 0 because M086300900009 of threshold B3n = 26 MeV. M086300900010 ENDBIB 8 0 M086300900011 NOCOMMON 0 0 M086300900012 DATA 3 1 M086300900013 EN-MAX DATA DATA-ERR M086300900014 MEV MB*MEV MB*MEV M086300900015 31.1 23.6 2.5 M086300900016 ENDDATA 3 0 M086300900017 ENDSUBENT 16 0 M086300999999 ENDENTRY 9 0 M086399999999