ENTRY M0864 20150902 M081M086400000001 SUBENT M0864001 20150902 M081M086400100001 BIB 10 72 M086400100002 TITLE Systematic disagreements between partial photoneutron M086400100003 reactions cross sections: new approach to analysis M086400100004 evaluation. M086400100005 AUTHOR (B.S.Ishkhanov,V.N.Orlin,N.N.Peskov,M.E.Stepanov, M086400100006 V.V.Varlamov) M086400100007 REFERENCE (R,MSU-INP-2013-1/884,2013) In Russian. M086400100008 (J,IZV,77,(4),433,2013) M086400100009 #doi:10.7868/S0367676513040297 M086400100010 Cross sections of partial photoneutron reactions for M086400100011 the 115In nucleus and the neutron multiplicity M086400100012 sorting. M086400100013 (J,BAS,77,(4),388,2013) M086400100014 #doi:10.3103/S1062873813040291 M086400100015 English translation of IZV,77,(4),433,2013. M086400100016 (R,MSU-INP-2011-5/869,2011) In Russian. M086400100017 Analysis of reliability of experimental data on total M086400100018 and partial photoneutron reaction cross sections. M086400100019 New evaluated data for 159Tb. M086400100020 (J,YF,75,(11),1414,2012) M086400100021 New approach to analyzing and evaluating cross M086400100022 sections for partial photoneutron reactions. M086400100023 (J,PAN,75,(11),1339,2012) M086400100024 #doi:10.1134/S1063778812110191 M086400100025 English translation of YF,75,(11),1414,2012. M086400100026 (R,MSU-INP-2012-1/879,2012) In Russian. M086400100027 Investigation of 181Ta photodisintegration using M086400100028 methods of induced activity and neutron multiplicity M086400100029 sorting - data reliability and authenticity. M086400100030 (J,YF,76,(11),1484,2013) M086400100031 #doi:10.7868/S0044002713110159 M086400100032 New data on partial photoneutron reactions (g,n), M086400100033 (g,2n) and (g,3n). M086400100034 (J,PAN,76,(11),1403,2013) M086400100035 #doi:10.1134/S1063778813110148 M086400100036 English translation of YF,76,(11),1484,2013. M086400100037 (J,IZV,78,(5),599,2014) M086400100038 #doi:10.7868/S0367676514050263 M086400100039 (J,BAS,78,(5),412,2014) M086400100040 #doi:10.3103/S1062873814050207 M086400100041 English translation of IZV,78,(5),599,2014. M086400100042 INSTITUTE (4RUSMOS) M086400100043 INC-SOURCE (QMPH,ARAD) M086400100044 ANALYSIS The joint analysis of data for total (g,xn) and M086400100045 partial (g,n), (g,2n) and (g,3n) reactions obtained M086400100046 in various experiments was carried out. The new M086400100047 approach to analysis of systematic disagreements M086400100048 between data was proposed on the base of new criteria M086400100049 of systematic uncertainties presence - specially M086400100050 proposed transitional multiplicity functions M086400100051 Fi-theor = SIG(g,in)/SIG(g,xn). M086400100052 Using these functions calculated in the frame of M086400100053 combined photonuclear reaction model new reliable M086400100054 and free from problems of neutron multiplicity M086400100055 sorting data for photoneutron partial reactions M086400100056 cross sections M086400100057 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M086400100058 were evaluated using experimental neutron yield M086400100059 reaction cross sections SIG-exp(g,xn). M086400100060 ERR-ANALYS (DATA-ERR) Mean-root-squared errors. M086400100061 COMMENT New evaluated data are presented for 91,94Zr M086400100062 and 188,189,190,192Os, and 208Pb and added by data M086400100063 for 115In, 159Tb, and 181Ta published before. M086400100064 STATUS (TABLE,APRVD) Approved by V.Varlamov. M086400100065 HISTORY (20130911C) Data were compiled at the Russia MSU SINP M086400100066 CDFE by V.Varlamov. M086400100067 (20140120A) Corrected by V.Varlamov: REFERENCE. M086400100068 (20150901A) Corrected by V.Varlamov: REFERENCE, M086400100069 SUBENTs 002-008 deleted because of duplication M086400100070 of M0914.002-008, SUBENTs 017-024 deleted because M086400100071 of duplication of M0915.004-011. M086400100072 (20150902A) Corrected by V.Varlamov: SUBENTs 009-016 M086400100073 deleted because duplication of M0916. M086400100074 ENDBIB 72 0 M086400100075 NOCOMMON 0 0 M086400100076 ENDSUBENT 75 0 M086400199999 NOSUBENT M0864002 20150901 M080M086400200001 NOSUBENT M0864003 20150901 M080M086400300001 NOSUBENT M0864004 20150901 M080M086400400001 NOSUBENT M0864005 20150901 M080M086400500001 NOSUBENT M0864006 20150901 M080M086400600001 NOSUBENT M0864007 20150901 M080M086400700001 NOSUBENT M0864008 20150901 M080M086400800001 NOSUBENT M0864009 20150902 M081M086400900001 NOSUBENT M0864010 20150902 M081M086401000001 NOSUBENT M0864011 20150902 M081M086401100001 NOSUBENT M0864012 20150902 M081M086401200001 NOSUBENT M0864013 20150902 M081M086401300001 NOSUBENT M0864014 20150902 M081M086401400001 NOSUBENT M0864015 20150902 M081M086401500001 NOSUBENT M0864016 20150902 M081M086401600001 NOSUBENT M0864017 20150901 M080M086401700001 NOSUBENT M0864018 20150901 M080M086401800001 NOSUBENT M0864019 20150901 M080M086401900001 NOSUBENT M0864020 20150901 M080M086402000001 NOSUBENT M0864021 20150901 M080M086402100001 NOSUBENT M0864022 20150901 M080M086402200001 NOSUBENT M0864023 20150901 M080M086402300001 NOSUBENT M0864024 20150901 M080M086402400001 SUBENT M0864025 20130911 M068M086402500001 BIB 4 22 M086402500002 REACTION ((82-PB-208(G,N)82-PB-207,,SIG,,,EVAL)+ M086402500003 (82-PB-208(G,N+P)81-TL-206,,SIG,,,EVAL)) M086402500004 ANALYSIS The contribution of partial reaction (g,n) cross M086402500005 section into the experimental total neutron yield M086402500006 reaction (g,xn) cross section obtained using M086402500007 quasimonoenergetic annihilation photons at Saclay M086402500008 (France) was evaluated using specially theoretically M086402500009 calculated transitional multiplicity function - M086402500010 ratio M086402500011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M086402500012 by the way M086402500013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M086402500014 REL-REF (R,L0021013,A.Veyssiere+,J,NP/A,159,561,1970) M086402500015 Experimental data for the total neutron yield M086402500016 reaction (g,xn) cross section. M086402500017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M086402500018 Theoretical preequilibrium model of photonuclear M086402500019 reactions based on the Fermi gas densities. M086402500020 STATUS Data plotted in Fig. 16. M086402500021 (DEP,L0011008) M086402500022 The total neutron yield reaction (g,xn) cross M086402500023 section. M086402500024 ENDBIB 22 0 M086402500025 NOCOMMON 0 0 M086402500026 DATA 3 101 M086402500027 EN DATA DATA-ERR M086402500028 MEV MB MB M086402500029 7.50 19.99 2.25 M086402500030 7.80 26.14 2.20 M086402500031 8.10 28.89 2.36 M086402500032 8.40 31.28 2.58 M086402500033 8.70 36.22 3.01 M086402500034 9.00 47.60 3.45 M086402500035 9.30 63.39 3.95 M086402500036 9.60 80.83 4.37 M086402500037 9.90 106.40 4.97 M086402500038 10.20 123.60 5.43 M086402500039 10.50 158.60 6.18 M086402500040 10.80 206.20 7.05 M086402500041 11.10 272.20 8.31 M086402500042 11.40 316.10 9.09 M086402500043 11.70 363.70 9.95 M086402500044 12.00 413.40 11.02 M086402500045 12.30 458.70 12.26 M086402500046 12.60 520.90 14.23 M086402500047 12.90 580.20 27.22 M086402500048 13.20 622.30 28.85 M086402500049 13.50 633.60 31.23 M086402500050 13.80 620.70 29.59 M086402500051 14.10 586.80 28.76 M086402500052 14.40 518.30 26.70 M086402500053 14.70 436.40 25.09 M086402500054 15.00 358.10 22.34 M086402500055 15.30 281.20 20.00 M086402500056 15.60 222.80 17.51 M086402500057 15.90 173.00 15.01 M086402500058 16.20 134.70 13.20 M086402500059 16.50 107.50 11.48 M086402500060 16.80 86.94 9.96 M086402500061 17.10 70.51 8.85 M086402500062 17.40 57.27 7.96 M086402500063 17.70 48.61 7.24 M086402500064 18.00 41.88 6.67 M086402500065 18.30 35.59 6.15 M086402500066 18.60 30.96 5.70 M086402500067 18.90 27.37 5.46 M086402500068 19.20 24.24 5.24 M086402500069 19.50 20.80 4.93 M086402500070 19.80 18.62 4.74 M086402500071 20.10 18.11 4.64 M086402500072 20.40 17.22 4.53 M086402500073 20.70 15.96 4.57 M086402500074 21.00 11.89 2.46 M086402500075 21.30 11.87 2.47 M086402500076 21.60 12.89 2.51 M086402500077 21.90 12.18 2.46 M086402500078 22.20 10.94 2.37 M086402500079 22.50 9.34 2.23 M086402500080 22.80 9.94 3.34 M086402500081 23.10 10.71 3.24 M086402500082 23.40 10.76 3.32 M086402500083 23.70 10.45 3.55 M086402500084 24.00 10.14 3.49 M086402500085 24.30 10.13 3.25 M086402500086 24.60 10.17 3.29 M086402500087 24.90 9.83 3.41 M086402500088 25.20 7.52 3.84 M086402500089 25.50 7.24 3.35 M086402500090 25.80 7.49 4.15 M086402500091 26.10 6.12 3.20 M086402500092 26.40 3.72 1.60 M086402500093 26.70 4.74 1.40 M086402500094 27.00 5.34 1.46 M086402500095 27.30 5.77 1.50 M086402500096 27.60 6.20 1.79 M086402500097 27.90 5.55 1.50 M086402500098 28.20 4.62 1.63 M086402500099 28.50 5.19 1.43 M086402500100 28.80 5.89 1.80 M086402500101 29.10 5.55 1.48 M086402500102 29.40 5.19 1.68 M086402500103 29.70 5.47 1.48 M086402500104 30.00 5.66 1.71 M086402500105 30.30 5.42 1.55 M086402500106 30.60 5.19 1.66 M086402500107 30.90 4.23 1.45 M086402500108 31.20 3.98 1.55 M086402500109 31.50 3.92 1.54 M086402500110 31.80 3.45 1.45 M086402500111 32.10 3.41 1.47 M086402500112 32.40 3.39 1.29 M086402500113 32.70 3.39 1.41 M086402500114 33.00 3.64 1.32 M086402500115 33.30 4.21 1.58 M086402500116 33.60 3.85 1.33 M086402500117 33.90 3.45 1.48 M086402500118 34.20 3.30 1.27 M086402500119 34.50 3.25 1.48 M086402500120 34.80 3.16 1.26 M086402500121 35.10 3.08 1.44 M086402500122 35.40 2.80 1.29 M086402500123 35.70 2.76 1.42 M086402500124 36.00 3.00 1.42 M086402500125 36.30 2.94 1.45 M086402500126 36.60 2.04 1.30 M086402500127 36.90 1.48 1.12 M086402500128 37.20 0.40 1.10 M086402500129 37.50 0.29 0.87 M086402500130 ENDDATA 103 0 M086402500131 ENDSUBENT 130 0 M086402599999 SUBENT M0864026 20130911 M068M086402600001 BIB 4 22 M086402600002 REACTION ((82-PB-208(G,2N)82-PB-206,,SIG,,,EVAL)+ M086402600003 (82-PB-208(G,2N+P)81-TL-205,,SIG,,,EVAL)) M086402600004 ANALYSIS The contribution of partial reaction (g,n) cross M086402600005 section into the experimental total neutron yield M086402600006 reaction (g,xn) cross section obtained using M086402600007 quasimonoenergetic annihilation photons at Saclay M086402600008 (France) was evaluated using specially theoretically M086402600009 calculated transitional multiplicity function - M086402600010 ratio M086402600011 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M086402600012 by the way M086402600013 SIG-eval(g,n) = (F2-theor)x(SIG-exp(g,xn)). M086402600014 REL-REF (R,L0021013,A.Veyssiere+,J,NP/A,159,561,1970) M086402600015 Experimental data for the total neutron yield M086402600016 reaction (g,xn) cross section. M086402600017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M086402600018 Theoretical preequilibrium model of photonuclear M086402600019 reactions based on the Fermi gas densities. M086402600020 STATUS Data plotted in Fig. 16. M086402600021 (DEP,L0011008) M086402600022 The total neutron yield reaction (g,xn) cross M086402600023 section. M086402600024 ENDBIB 22 0 M086402600025 NOCOMMON 0 0 M086402600026 DATA 3 81 M086402600027 EN DATA DATA-ERR M086402600028 MEV MB MB M086402600029 13.50 0.01 1.70 M086402600030 13.80 0.32 1.68 M086402600031 14.10 3.90 1.74 M086402600032 14.40 16.61 2.20 M086402600033 14.70 36.97 3.20 M086402600034 15.00 57.91 4.36 M086402600035 15.30 73.12 5.60 M086402600036 15.60 84.77 6.72 M086402600037 15.90 90.81 7.60 M086402600038 16.20 93.42 8.57 M086402600039 16.50 95.07 9.28 M086402600040 16.80 94.88 9.74 M086402600041 17.10 92.10 10.26 M086402600042 17.40 87.21 10.70 M086402600043 17.70 84.39 11.06 M086402600044 18.00 81.26 11.40 M086402600045 18.30 75.90 11.63 M086402600046 18.60 71.52 11.78 M086402600047 18.90 67.61 12.21 M086402600048 19.20 63.38 12.57 M086402600049 19.50 57.00 12.60 M086402600050 19.80 53.04 12.76 M086402600051 20.10 53.30 13.02 M086402600052 20.40 52.04 13.21 M086402600053 20.70 49.32 13.79 M086402600054 21.00 37.44 7.58 M086402600055 21.30 38.02 7.86 M086402600056 21.60 41.87 8.24 M086402600057 21.90 40.08 8.33 M086402600058 22.20 36.43 8.24 M086402600059 22.50 31.44 7.94 M086402600060 22.80 33.76 11.91 M086402600061 23.10 36.56 11.86 M086402600062 23.40 36.73 12.28 M086402600063 23.70 35.49 13.13 M086402600064 24.00 34.03 12.90 M086402600065 24.30 33.29 11.97 M086402600066 24.60 32.45 11.91 M086402600067 24.90 30.22 11.96 M086402600068 25.20 22.19 12.62 M086402600069 25.50 20.32 10.82 M086402600070 25.80 19.95 12.59 M086402600071 26.10 15.47 9.35 M086402600072 26.40 8.90 4.60 M086402600073 26.70 10.76 4.17 M086402600074 27.00 11.47 4.24 M086402600075 27.30 11.71 4.22 M086402600076 27.60 11.86 4.66 M086402600077 27.90 10.00 3.79 M086402600078 28.20 7.83 3.65 M086402600079 28.50 8.28 3.26 M086402600080 28.80 8.84 3.77 M086402600081 29.10 7.84 3.08 M086402600082 29.40 6.90 3.13 M086402600083 29.70 6.85 2.77 M086402600084 30.00 6.67 2.94 M086402600085 30.30 6.01 2.58 M086402600086 30.60 5.42 2.53 M086402600087 30.90 4.17 2.06 M086402600088 31.20 3.71 2.04 M086402600089 31.50 3.48 1.92 M086402600090 31.80 2.91 1.71 M086402600091 32.10 2.74 1.65 M086402600092 32.40 2.61 1.45 M086402600093 32.70 2.49 1.48 M086402600094 33.00 2.57 1.40 M086402600095 33.30 2.85 1.60 M086402600096 33.60 2.51 1.35 M086402600097 33.90 2.17 1.36 M086402600098 34.20 2.01 1.17 M086402600099 34.50 1.91 1.27 M086402600100 34.80 1.81 1.10 M086402600101 35.10 1.71 1.17 M086402600102 35.40 1.52 1.02 M086402600103 35.70 1.46 1.07 M086402600104 36.00 1.55 1.08 M086402600105 36.30 1.49 1.07 M086402600106 36.60 1.01 0.88 M086402600107 36.90 0.72 0.71 M086402600108 37.20 0.19 0.57 M086402600109 37.50 0.13 0.44 M086402600110 ENDDATA 83 0 M086402600111 ENDSUBENT 110 0 M086402699999 SUBENT M0864027 20130911 M068M086402700001 BIB 5 25 M086402700002 REACTION ((82-PB-208(G,3N)82-PB-205,,SIG,,,EVAL)+ M086402700003 (82-PB-208(G,3N+P)81-TL-204,,SIG,,,EVAL)) M086402700004 ANALYSIS The contribution of partial reaction (g,n) cross M086402700005 section into the experimental total neutron yield M086402700006 reaction (g,xn) cross section obtained using M086402700007 quasimonoenergetic annihilation photons at Saclay M086402700008 (France) was evaluated using specially theoretically M086402700009 calculated transitional multiplicity function - M086402700010 ratio M086402700011 F3-theor = SIG-theor(g,3n)/SIG-theor(g,xn) M086402700012 by the way M086402700013 SIG-eval(g,n) = (F3-theor)x(SIG-exp(g,xn)). M086402700014 REL-REF (R,L0021013,A.Veyssiere+,J,NP/A,159,561,1970) M086402700015 Experimental data for the total neutron yield M086402700016 reaction (g,xn) cross section. M086402700017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M086402700018 Theoretical preequilibrium model of photonuclear M086402700019 reactions based on the Fermi gas densities. M086402700020 COMMENT Data for (g,3n) reaction cross section uncertainties M086402700021 are substituted in comparison with data published M086402700022 in J,YF,76,(11),1,2013 (Fig. 4). M086402700023 STATUS Data plotted in Fig. 16. M086402700024 (DEP,L0011008) M086402700025 The total neutron yield reaction (g,xn) cross M086402700026 section. M086402700027 ENDBIB 25 0 M086402700028 NOCOMMON 0 0 M086402700029 DATA 3 51 M086402700030 EN DATA DATA-ERR M086402700031 MEV MB MB M086402700032 22.50 0.01 0.06 M086402700033 22.80 0.06 0.08 M086402700034 23.10 0.19 0.13 M086402700035 23.40 0.45 0.22 M086402700036 23.70 0.84 0.37 M086402700037 24.00 1.36 0.58 M086402700038 24.30 2.08 0.81 M086402700039 24.60 2.98 1.15 M086402700040 24.90 3.84 1.58 M086402700041 25.20 3.71 2.15 M086402700042 25.50 4.58 2.48 M086402700043 25.80 5.81 3.69 M086402700044 26.10 5.66 3.43 M086402700045 26.40 4.01 2.08 M086402700046 26.70 5.87 2.27 M086402700047 27.00 7.48 2.76 M086402700048 27.30 9.05 3.23 M086402700049 27.60 10.76 4.19 M086402700050 27.90 10.56 3.95 M086402700051 28.20 9.53 4.39 M086402700052 28.50 11.55 4.45 M086402700053 28.80 13.99 5.85 M086402700054 29.10 13.99 5.35 M086402700055 29.40 13.81 6.12 M086402700056 29.70 15.29 6.00 M086402700057 30.00 16.53 7.07 M086402700058 30.30 16.45 6.82 M086402700059 30.60 16.29 7.35 M086402700060 30.90 13.68 6.52 M086402700061 31.20 13.21 6.99 M086402700062 31.50 13.34 7.10 M086402700063 31.80 11.96 6.76 M086402700064 32.10 12.03 6.95 M086402700065 32.40 12.13 6.44 M086402700066 32.70 12.23 6.96 M086402700067 33.00 13.24 6.89 M086402700068 33.30 15.36 8.22 M086402700069 33.60 14.04 7.16 M086402700070 33.90 12.55 7.50 M086402700071 34.20 11.93 6.65 M086402700072 34.50 11.61 7.36 M086402700073 34.80 11.14 6.46 M086402700074 35.10 10.70 7.00 M086402700075 35.40 9.55 6.21 M086402700076 35.70 9.20 6.53 M086402700077 36.00 9.77 6.57 M086402700078 36.30 9.31 6.50 M086402700079 36.60 6.29 5.32 M086402700080 36.90 4.42 4.31 M086402700081 37.20 1.16 3.44 M086402700082 37.50 0.81 2.64 M086402700083 ENDDATA 53 0 M086402700084 ENDSUBENT 83 0 M086402799999 SUBENT M0864028 20130911 M068M086402800001 BIB 3 10 M086402800002 REACTION (82-PB-208(G,X)0-NN-1,UNW,SIG,,,EVAL) M086402800003 ANALYSIS The total neutron reaction cross section obtained M086402800004 as sum: SIG(g,sn) = SIG(g,n) + SIG(g,2n) + SIG(g,3n). M086402800005 STATUS Data plotted in Fig. 16. M086402800006 (DEP,M0864025) M086402800007 Evaluated (g,n) reaction cross section. M086402800008 (DEP,M0864026) M086402800009 Evaluated (g,2n) reaction cross section. M086402800010 (DEP,M0864027) M086402800011 Evaluated (g,3n) reaction cross section. M086402800012 ENDBIB 10 0 M086402800013 NOCOMMON 0 0 M086402800014 DATA 3 101 M086402800015 EN DATA DATA-ERR M086402800016 MEV MB MB M086402800017 7.50 19.99 2.33 M086402800018 7.80 26.14 2.29 M086402800019 8.10 28.89 2.46 M086402800020 8.40 31.28 2.69 M086402800021 8.70 36.22 3.14 M086402800022 9.00 47.60 3.62 M086402800023 9.30 63.39 4.18 M086402800024 9.60 80.83 4.66 M086402800025 9.90 106.40 5.35 M086402800026 10.20 123.60 5.86 M086402800027 10.50 158.60 6.74 M086402800028 10.80 206.20 7.78 M086402800029 11.10 272.20 9.27 M086402800030 11.40 316.10 10.21 M086402800031 11.70 363.70 11.23 M086402800032 12.00 413.40 12.47 M086402800033 12.30 458.70 13.87 M086402800034 12.60 520.90 16.06 M086402800035 12.90 580.20 29.26 M086402800036 13.20 622.30 31.04 M086402800037 13.50 633.60 33.47 M086402800038 13.80 621.10 31.79 M086402800039 14.10 590.70 31.01 M086402800040 14.40 534.90 29.36 M086402800041 14.70 473.40 28.72 M086402800042 15.00 416.00 27.11 M086402800043 15.30 354.30 25.96 M086402800044 15.60 307.60 24.56 M086402800045 15.90 263.80 22.91 M086402800046 16.20 228.10 22.04 M086402800047 16.50 202.50 21.02 M086402800048 16.80 181.80 19.94 M086402800049 17.10 162.60 19.33 M086402800050 17.40 144.50 18.86 M086402800051 17.70 133.00 18.48 M086402800052 18.00 123.10 18.24 M086402800053 18.30 111.50 17.93 M086402800054 18.60 102.50 17.63 M086402800055 18.90 94.98 17.82 M086402800056 19.20 87.62 17.95 M086402800057 19.50 77.80 17.65 M086402800058 19.80 71.66 17.61 M086402800059 20.10 71.41 17.77 M086402800060 20.40 69.26 17.85 M086402800061 20.70 65.28 18.47 M086402800062 21.00 49.32 10.12 M086402800063 21.30 49.89 10.41 M086402800064 21.60 54.76 10.83 M086402800065 21.90 52.26 10.88 M086402800066 22.20 47.38 10.70 M086402800067 22.50 40.79 10.25 M086402800068 22.80 43.77 15.34 M086402800069 23.10 47.47 15.24 M086402800070 23.40 47.94 15.83 M086402800071 23.70 46.78 17.06 M086402800072 24.00 45.54 16.98 M086402800073 24.30 45.50 16.03 M086402800074 24.60 45.60 16.36 M086402800075 24.90 43.90 16.96 M086402800076 25.20 33.42 18.62 M086402800077 25.50 32.16 16.67 M086402800078 25.80 33.26 20.44 M086402800079 26.10 27.25 16.00 M086402800080 26.40 16.64 8.28 M086402800081 26.70 21.39 7.84 M086402800082 27.00 24.31 8.47 M086402800083 27.30 26.54 8.95 M086402800084 27.60 28.82 10.65 M086402800085 27.90 26.13 9.24 M086402800086 28.20 21.99 9.67 M086402800087 28.50 25.03 9.14 M086402800088 28.80 28.73 11.43 M086402800089 29.10 27.38 9.91 M086402800090 29.40 25.90 10.94 M086402800091 29.70 27.61 10.27 M086402800092 30.00 28.87 11.74 M086402800093 30.30 27.88 10.97 M086402800094 30.60 26.91 11.56 M086402800095 30.90 22.08 10.04 M086402800096 31.20 20.91 10.59 M086402800097 31.50 20.74 10.58 M086402800098 31.80 18.33 9.93 M086402800099 32.10 18.19 10.08 M086402800100 32.40 18.14 9.19 M086402800101 32.70 18.12 9.86 M086402800102 33.00 19.46 9.62 M086402800103 33.30 22.44 11.41 M086402800104 33.60 20.41 9.84 M086402800105 33.90 18.19 10.34 M086402800106 34.20 17.25 9.10 M086402800107 34.50 16.78 10.12 M086402800108 34.80 16.12 8.82 M086402800109 35.10 15.50 9.62 M086402800110 35.40 13.89 8.53 M086402800111 35.70 13.43 9.03 M086402800112 36.00 14.34 9.07 M086402800113 36.30 13.75 9.02 M086402800114 36.60 9.35 7.50 M086402800115 36.90 6.63 6.16 M086402800116 37.20 1.76 5.12 M086402800117 37.50 1.24 3.97 M086402800118 ENDDATA 103 0 M086402800119 ENDSUBENT 118 0 M086402899999 ENDENTRY 28 0 M086499999999