ENTRY M0972 20180823 M098M097200000001 SUBENT M0972001 20180823 M098M097200100001 BIB 9 27 M097200100002 TITLE Comparison of partial photoneutron reaction cross M097200100003 sections reliability for 140,142Ce. M097200100004 AUTHOR (V.V.Varlamov,V.A.Barbaryan,N.N.Peskov) M097200100005 REFERENCE (C,2017ALMATY,,26,2017) M097200100006 INSTITUTE (4RUSMOS) M097200100007 INC-SOURCE (QMPH,ARAD) M097200100008 ANALYSIS The joint analysis of data for total (g,xn) and M097200100009 partial (g,n), (g,2n) and (g,3n) reactions obtained M097200100010 in various experiments was carried out. The new M097200100011 approach to analysis of systematic disagreements M097200100012 between data was proposed on the base of new M097200100013 criteria of systematic uncertainties presence - M097200100014 specially proposed transitional multiplicity M097200100015 functions M097200100016 Fi-theor = SIG(g,in)/SIG(g,xn). M097200100017 Using these functions calculated in the frame of M097200100018 combined photonuclear reaction model new reliable M097200100019 and free from problems of neutron multiplicity M097200100020 sorting data for photoneutron partial reactions M097200100021 cross sections M097200100022 SIG-eval(g,in) = Fi-theor x SIG-exp(g,xn) M097200100023 were evaluated using experimental neutron yield M097200100024 reaction cross sections SIG-exp(g,xn). M097200100025 ERR-ANALYS (DATA-ERR) Root-mean-square errors. M097200100026 STATUS (APRVD) Approved by V.Varlamov. M097200100027 HISTORY (20180823C) Data were compiled at the Russia MSU SINP M097200100028 CDFE by V.Varlamov. M097200100029 ENDBIB 27 0 M097200100030 NOCOMMON 0 0 M097200100031 ENDSUBENT 30 0 M097200199999 SUBENT M0972002 20180823 M098M097200200001 BIB 3 8 M097200200002 REACTION (58-CE-140(G,X)0-NN-1,UNW,SIG,,,EVAL) M097200200003 ANALYSIS The total neutron reaction cross section obtained as M097200200004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097200200005 STATUS (TABLE) M097200200006 (DEP,M0972003) M097200200007 Evaluated (g,1n) reaction cross section. M097200200008 (DEP,M0972004) M097200200009 Evaluated (g,2n) reaction cross section. M097200200010 ENDBIB 8 0 M097200200011 NOCOMMON 0 0 M097200200012 DATA 3 43 M097200200013 EN DATA DATA-ERR M097200200014 MEV MB MB M097200200015 9.40 49.79 4.98 M097200200016 9.80 52.47 5.25 M097200200017 10.20 55.42 5.54 M097200200018 10.60 64.55 6.46 M097200200019 11.00 73.40 7.34 M097200200020 11.40 96.16 9.62 M097200200021 12.00 113.86 11.39 M097200200022 12.20 136.19 13.62 M097200200023 12.60 154.94 15.49 M097200200024 13.00 196.52 19.65 M097200200025 13.40 237.26 23.73 M097200200026 13.80 279.82 27.98 M097200200027 14.20 329.48 32.95 M097200200028 14.60 358.91 35.89 M097200200029 15.00 389.39 38.94 M097200200030 15.40 380.40 38.04 M097200200031 15.80 345.28 34.53 M097200200032 16.20 300.12 30.01 M097200200033 16.60 272.24 27.22 M097200200034 17.00 228.77 22.88 M097200200035 17.40 187.62 18.76 M097200200036 17.80 161.98 16.20 M097200200037 18.20 130.75 13.07 M097200200038 18.60 120.51 12.05 M097200200039 19.00 109.87 10.99 M097200200040 19.40 97.10 9.71 M097200200041 20.00 90.10 9.01 M097200200042 20.20 92.88 9.29 M097200200043 20.60 89.01 8.90 M097200200044 21.00 82.03 8.20 M097200200045 21.40 77.93 7.79 M097200200046 21.80 73.31 7.33 M097200200047 22.20 68.46 6.85 M097200200048 22.60 70.00 7.00 M097200200049 23.00 60.24 6.02 M097200200050 23.40 53.13 5.31 M097200200051 23.80 51.64 5.16 M097200200052 24.20 53.66 5.37 M097200200053 24.60 44.48 4.45 M097200200054 25.00 52.23 5.22 M097200200055 25.40 46.37 4.36 M097200200056 25.80 44.70 4.42 M097200200057 26.20 48.14 4.81 M097200200058 ENDDATA 45 0 M097200200059 ENDSUBENT 58 0 M097200299999 SUBENT M0972003 20180823 M098M097200300001 BIB 4 23 M097200300002 REACTION ((58-CE-140(G,N)58-CE-139,,SIG,,,EVAL)+ M097200300003 (58-CE-140(G,N+P)57-LA-138,,SIG,,,EVAL)) M097200300004 ANALYSIS The contribution of partial reaction (g,n) cross M097200300005 section into the experimental total neutron yield M097200300006 reaction (g,xn) cross section obtained using M097200300007 quasimonoenergetic annihilation photons at Saclay M097200300008 was evaluated using specially theoretically M097200300009 calculated transitional multiplicity function - M097200300010 ratio M097200300011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097200300012 by the way M097200300013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097200300014 The neutron yield cross section was obtained at M097200300015 Saclay by Beil. M097200300016 REL-REF (R,L0042016,A.Lepretre+,J,NP/A,258,350,1976) M097200300017 Experimental data for the total neutron yield M097200300018 reaction (g,xn) cross section. M097200300019 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097200300020 Theoretical preequilibrium model of photonuclear M097200300021 reactions based on the Fermi gas densities. M097200300022 STATUS (TABLE) M097200300023 (DEP,L0042016) M097200300024 The neutron yield reaction (g,xn) cross section. M097200300025 ENDBIB 23 0 M097200300026 NOCOMMON 0 0 M097200300027 DATA 3 43 M097200300028 EN DATA DATA-ERR M097200300029 MEV MB MB M097200300030 9.4 49.79 8.85 M097200300031 9.8 52.47 9.33 M097200300032 10.2 55.42 9.85 M097200300033 10.6 64.55 11.48 M097200300034 11.0 73.40 13.05 M097200300035 11.4 96.16 17.10 M097200300036 11.8 113.86 20.24 M097200300037 12.2 136.19 24.21 M097200300038 12.6 154.94 27.55 M097200300039 13.0 196.52 34.94 M097200300040 13.4 237.26 42.18 M097200300041 13.8 279.82 49.75 M097200300042 14.2 329.48 58.57 M097200300043 14.6 358.90 63.81 M097200300044 15.0 389.39 69.23 M097200300045 15.4 380.40 67.63 M097200300046 15.8 345.28 61.38 M097200300047 16.2 300.12 53.36 M097200300048 16.6 272.24 48.40 M097200300049 17.0 222.82 39.55 M097200300050 17.4 157.13 27.69 M097200300051 17.8 110.13 19.29 M097200300052 18.2 70.99 12.38 M097200300053 18.6 53.63 9.32 M097200300054 19.0 41.92 7.28 M097200300055 19.4 33.55 5.82 M097200300056 19.8 29.43 5.10 M097200300057 20.2 30.51 5.29 M097200300058 20.6 30.22 5.24 M097200300059 21.0 29.06 5.04 M097200300060 21.4 27.99 4.85 M097200300061 21.8 25.65 4.43 M097200300062 22.2 22.71 3.90 M097200300063 22.6 21.95 3.75 M097200300064 23.0 17.98 3.06 M097200300065 23.4 15.12 2.57 M097200300066 23.8 14.27 2.42 M097200300067 24.2 14.54 2.46 M097200300068 24.6 11.92 2.01 M097200300069 25.0 13.82 2.33 M097200300070 25.4 11.42 1.93 M097200300071 25.8 12.90 2.07 M097200300072 26.2 13.67 2.10 M097200300073 ENDDATA 45 0 M097200300074 ENDSUBENT 73 0 M097200399999 SUBENT M0972004 20180823 M098M097200400001 BIB 4 22 M097200400002 REACTION (58-CE-140(G,2N)58-CE-138,,SIG,,,EVAL) M097200400003 ANALYSIS The contribution of partial reaction (g,2n) cross M097200400004 section into the experimental total neutron yield M097200400005 reaction (g,xn) cross section obtained using M097200400006 quasimonoenergetic annihilation photons at Saclay M097200400007 was evaluated using specially theoretically M097200400008 calculated transitional multiplicity function - M097200400009 ratio M097200400010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097200400011 by the way M097200400012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097200400013 The neutron yield cross section was obtained at M097200400014 Saclay by Beil. M097200400015 REL-REF (R,L0042016,A.Lepretre+,J,NP/A,258,350,1976) M097200400016 Experimental data for the total neutron yield M097200400017 reaction (g,xn) cross section. M097200400018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097200400019 Theoretical preequilibrium model of photonuclear M097200400020 reactions based on the Fermi gas densities. M097200400021 STATUS (TABLE) M097200400022 (DEP,L0025016) M097200400023 The neutron yield reaction (g,xn) cross section. M097200400024 ENDBIB 22 0 M097200400025 NOCOMMON 0 0 M097200400026 DATA 3 24 M097200400027 EN DATA DATA-ERR M097200400028 MEV MB MB M097200400029 17.0 5.99 1.04 M097200400030 17.4 30.65 5.33 M097200400031 17.8 52.04 9.04 M097200400032 18.2 59.92 10.40 M097200400033 18.6 67.02 11.62 M097200400034 19.0 68.06 11.80 M097200400035 19.4 63.65 11.03 M097200400036 19.8 60.76 10.53 M097200400037 20.2 62.46 10.83 M097200400038 20.6 58.89 10.21 M097200400039 21.0 53.07 9.21 M097200400040 21.4 50.09 8.70 M097200400041 21.8 47.89 8.32 M097200400042 22.2 46.06 8.02 M097200400043 22.6 48.48 8.45 M097200400044 23.0 42.70 7.45 M097200400045 23.4 38.45 6.71 M097200400046 23.8 37.82 6.60 M097200400047 24.2 39.61 6.92 M097200400048 24.6 32.99 5.76 M097200400049 25.0 38.92 6.80 M097200400050 25.4 32.64 5.71 M097200400051 25.8 36.18 6.38 M097200400052 26.2 38.15 6.7 M097200400053 ENDDATA 26 0 M097200400054 ENDSUBENT 53 0 M097200499999 SUBENT M0972005 20180823 M098M097200500001 BIB 3 8 M097200500002 REACTION (58-CE-142(G,X)0-NN-1,UNW,SIG,,,EVAL) M097200500003 ANALYSIS The total neutron reaction cross section obtained as M097200500004 sum: SIG(g,sn) = SIG(g,1n) + SIG(g,2n) + SIG(g,3n). M097200500005 STATUS (TABLE) M097200500006 (DEP,M0972006) M097200500007 Evaluated (g,1n) reaction cross section. M097200500008 (DEP,M0972007) M097200500009 Evaluated (g,2n) reaction cross section. M097200500010 ENDBIB 8 0 M097200500011 NOCOMMON 0 0 M097200500012 DATA 3 59 M097200500013 EN DATA DATA-ERR M097200500014 MEV MB MB M097200500015 7.76 27.80 6.61 M097200500016 8.03 39.40 7.22 M097200500017 8.30 37.80 7.18 M097200500018 8.57 29.90 6.85 M097200500019 8.84 43.00 7.55 M097200500020 9.11 39.70 7.41 M097200500021 9.38 51.60 8.15 M097200500022 9.65 44.10 7.74 M097200500023 9.92 64.80 9.11 M097200500024 10.20 64.60 9.14 M097200500025 10.47 80.90 10.39 M097200500026 10.74 75.50 10.01 M097200500027 11.01 97.10 11.75 M097200500028 11.28 93.70 11.50 M097200500029 11.55 110.40 12.92 M097200500030 11.82 128.50 14.53 M097200500031 12.09 135.20 16.69 M097200500032 12.36 165.80 19.33 M097200500033 12.63 185.50 21.12 M097200500034 12.91 222.32 23.61 M097200500035 13.18 238.32 22.94 M097200500036 13.45 253.05 21.69 M097200500037 13.72 292.07 22.66 M097200500038 13.99 299.18 22.05 M097200500039 14.26 313.90 22.79 M097200500040 14.53 339.01 24.69 M097200500041 14.80 344.23 25.39 M097200500042 15.07 331.38 24.99 M097200500043 15.34 326.51 25.05 M097200500044 15.62 321.79 25.29 M097200500045 15.89 292.44 23.60 M097200500046 16.16 274.12 22.66 M097200500047 16.43 240.35 20.59 M097200500048 16.70 216.98 19.08 M097200500049 16.97 209.83 8.53 M097200500050 17.24 184.36 16.74 M097200500051 17.51 163.08 15.35 M097200500052 17.78 148.28 14.22 M097200500053 18.05 138.24 13.47 M097200500054 18.33 118.35 12.14 M097200500055 18.60 112.57 11.75 M097200500056 18.87 109.87 11.59 M097200500057 19.14 104.81 11.17 M097200500058 19.41 93.37 10.43 M097200500059 19.68 86.78 10.05 M097200500060 19.95 84.89 9.98 M097200500061 20.22 74.14 9.37 M097200500062 20.49 78.68 9.53 M097200500063 20.76 76.79 9.47 M097200500064 21.04 68.92 9.06 M097200500065 21.31 70.35 9.20 M097200500066 21.58 52.80 8.26 M097200500067 21.85 65.35 9.04 M097200500068 22.12 55.38 8.64 M097200500069 22.39 71.34 9.49 M097200500070 22.66 32.89 7.93 M097200500071 22.93 66.06 9.34 M097200500072 23.20 69.47 9.57 M097200500073 23.47 45.82 8.58 M097200500074 ENDDATA 61 0 M097200500075 ENDSUBENT 74 0 M097200599999 SUBENT M0972006 20180823 M098M097200600001 BIB 4 21 M097200600002 REACTION ((58-CE-142(G,N)58-CE-141,,SIG,,,EVAL)+ M097200600003 (58-CE-142(G,N+P)57-LA-140,,SIG,,,EVAL)) M097200600004 ANALYSIS The contribution of partial reaction (g,n) cross M097200600005 section into the experimental total neutron yield M097200600006 reaction (g,xn) cross section obtained using M097200600007 quasimonoenergetic annihilation photons at Saclay M097200600008 was evaluated using specially theoretically M097200600009 calculated transitional multiplicity function - M097200600010 ratio M097200600011 F1-theor = SIG-theor(g,n)/SIG-theor(g,xn) M097200600012 by the way M097200600013 SIG-eval(g,n) = (F1-theor)x(SIG-exp(g,xn)). M097200600014 The neutron yield cross section was obtained at M097200600015 Saclay by Beil. M097200600016 REL-REF (R,L0042019,A.Lepretre+,J,NP/A,258,350,1976) M097200600017 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) M097200600018 Theoretical preequilibrium model of photonuclear M097200600019 reactions based on the Fermi gas densities. M097200600020 STATUS (TABLE) M097200600021 (DEP,L0025019) M097200600022 The neutron yield reaction (g,xn) cross section. M097200600023 ENDBIB 21 0 M097200600024 NOCOMMON 0 0 M097200600025 DATA 3 59 M097200600026 EN DATA DATA-ERR M097200600027 MEV MB MB M097200600028 7.76 27.80 6.61 M097200600029 8.03 39.40 7.22 M097200600030 8.30 37.80 7.18 M097200600031 8.57 29.90 6.85 M097200600032 8.84 43.00 7.55 M097200600033 9.11 39.70 7.41 M097200600034 9.38 51.60 8.15 M097200600035 9.65 44.10 7.74 M097200600036 9.92 64.80 9.11 M097200600037 10.20 64.60 9.14 M097200600038 10.47 80.90 10.39 M097200600039 10.74 75.50 10.01 M097200600040 11.01 97.10 11.75 M097200600041 11.28 93.70 11.50 M097200600042 11.55 110.40 12.92 M097200600043 11.82 128.50 14.53 M097200600044 12.09 135.20 16.69 M097200600045 12.36 165.80 19.33 M097200600046 12.63 185.50 21.12 M097200600047 12.91 215.45 23.60 M097200600048 13.18 211.84 22.76 M097200600049 13.45 197.50 20.88 M097200600050 13.72 195.99 20.35 M097200600051 13.99 170.96 17.64 M097200600052 14.26 156.95 16.11 M097200600053 14.53 148.32 15.16 M097200600054 14.80 136.60 13.95 M097200600055 15.07 115.98 11.85 M097200600056 15.34 105.15 10.75 M097200600057 15.62 92.72 9.49 M097200600058 15.89 75.63 7.77 M097200600059 16.16 63.63 6.56 M097200600060 16.43 48.07 4.99 M097200600061 16.70 39.45 4.14 M097200600062 16.97 38.15 4.02 M097200600063 17.24 30.73 3.28 M097200600064 17.51 24.16 2.63 M097200600065 17.78 21.97 2.44 M097200600066 18.05 20.48 2.31 M097200600067 18.33 15.63 1.82 M097200600068 18.60 14.87 1.77 M097200600069 18.87 14.51 1.74 M097200600070 19.14 15.53 1.91 M097200600071 19.41 13.83 1.79 M097200600072 19.68 12.86 1.72 M097200600073 19.95 12.58 1.71 M097200600074 20.22 10.98 1.61 M097200600075 20.49 13.11 1.87 M097200600076 20.76 12.80 1.86 M097200600077 21.04 12.53 1.97 M097200600078 21.31 12.79 1.99 M097200600079 21.58 10.56 2.00 M097200600080 21.85 12.84 2.15 M097200600081 22.12 10.88 2.05 M097200600082 22.39 12.97 2.06 M097200600083 22.66 5.98 1.72 M097200600084 22.93 12.01 2.02 M097200600085 23.20 12.63 2.07 M097200600086 23.47 8.33 1.86 M097200600087 ENDDATA 61 0 M097200600088 ENDSUBENT 87 0 M097200699999 SUBENT M0972007 20180823 M098M097200700001 BIB 4 22 M097200700002 REACTION (58-CE-142(G,2N)58-CE-140,,SIG,,,EVAL) M097200700003 ANALYSIS The contribution of partial reaction (g,2n) cross M097200700004 section into the experimental total neutron yield M097200700005 reaction (g,xn) cross section obtained using M097200700006 quasimonoenergetic annihilation photons at Saclay M097200700007 was evaluated using specially theoretically M097200700008 calculated transitional multiplicity function - M097200700009 ratio M097200700010 F2-theor = SIG-theor(g,2n)/SIG-theor(g,xn) M097200700011 by the way M097200700012 SIG-eval(g,2n) = (F2-theor)x(SIG-exp(g,xn)). M097200700013 The neutron yield cross section was obtained at M097200700014 Saclay by Beil. M097200700015 REL-REF (R,L0042019,A.Lepretre+,J,NP/A,258,350,1976) M097200700016 Experimental data for the total neutron yield M097200700017 reaction (g,xn) cross section. M097200700018 (E,,B.S.Ishkhanov+,J,YF,71,517,2008) ????? M097200700019 Theoretical preequilibrium model of photonuclear M097200700020 reactions based on the Fermi gas densities. M097200700021 STATUS (TABLE) M097200700022 (DEP,L0026019) M097200700023 The neutron yield reaction (g,xn) cross section. M097200700024 ENDBIB 22 0 M097200700025 NOCOMMON 0 0 M097200700026 DATA 3 40 M097200700027 EN DATA DATA-ERR M097200700028 MEV MB MB M097200700029 12.91 6.87 0.75 M097200700030 13.18 26.48 2.84 M097200700031 13.45 55.55 5.87 M097200700032 13.72 96.07 9.97 M097200700033 13.99 128.22 13.23 M097200700034 14.26 156.95 16.11 M097200700035 14.53 190.69 19.49 M097200700036 14.80 207.63 21.21 M097200700037 15.07 215.40 22.00 M097200700038 15.34 221.36 22.62 M097200700039 15.62 229.07 23.44 M097200700040 15.89 216.81 22.29 M097200700041 16.16 210.48 21.69 M097200700042 16.43 192.28 19.98 M097200700043 16.70 177.52 18.62 M097200700044 16.97 171.67 18.09 M097200700045 17.24 153.63 16.41 M097200700046 17.51 138.92 15.12 M097200700047 17.78 126.32 14.00 M097200700048 18.05 117.76 13.27 M097200700049 18.33 102.72 11.99 M097200700050 18.60 97.70 11.61 M097200700051 18.87 95.36 11.46 M097200700052 19.14 89.29 11.00 M097200700053 19.41 79.53 10.27 M097200700054 19.68 73.92 9.90 M097200700055 19.95 72.31 9.83 M097200700056 20.22 63.16 9.23 M097200700057 20.49 65.56 9.35 M097200700058 20.76 63.99 9.29 M097200700059 21.04 56.38 8.85 M097200700060 21.31 57.55 8.98 M097200700061 21.58 42.24 8.01 M097200700062 21.85 52.51 8.78 M097200700063 22.12 44.50 8.39 M097200700064 22.39 58.36 9.26 M097200700065 22.66 26.91 7.74 M097200700066 22.93 54.04 9.11 M097200700067 23.20 56.83 9.34 M097200700068 23.47 37.48 8.37 M097200700069 ENDDATA 42 0 M097200700070 ENDSUBENT 69 0 M097200799999 SUBENT M0972008 20180823 M098M097200800001 BIB 3 5 M097200800002 REACTION ((58-CE-140(G,N)58-CE-139,,INT,,,EVAL)+ M097200800003 (58-CE-140(G,N+P)57-LA-138,,INT,,,EVAL)) M097200800004 ANALYSIS Integration of evaluated cross section. M097200800005 STATUS (DEP,M0972003) Evaluated cross section. M097200800006 (TABLE) M097200800007 ENDBIB 5 0 M097200800008 NOCOMMON 0 0 M097200800009 DATA 3 29 M097200800010 EN-MAX DATA DATA-ERR M097200800011 MEV MB*MEV MB*MEV M097200800012 16.7 1554.48 71.76 M097200800013 26.4 1961.40 75.17 M097200800014 ENDDATA 4 0 M097200800015 ENDSUBENT 14 0 M097200899999 SUBENT M0972009 20180823 M098M097200900001 BIB 3 4 M097200900002 REACTION (58-CE-140(G,2N)58-CE-138,,INT,,,EVAL) M097200900003 ANALYSIS Integration of evaluated cross section. M097200900004 STATUS (DEP,M0972004) Evaluated cross section. M097200900005 (TABLE) M097200900006 ENDBIB 4 0 M097200900007 NOCOMMON 0 0 M097200900008 DATA 3 19 M097200900009 EN-MAX DATA DATA-ERR M097200900010 MEV MB*MEV MB*MEV M097200900011 26.4 448.22 16.54 M097200900012 ENDDATA 3 0 M097200900013 ENDSUBENT 12 0 M097200999999 SUBENT M0972010 20180823 M098M097201000001 BIB 3 5 M097201000002 REACTION ((58-CE-142(G,N)58-CE-141,,INT,,,EVAL)+ M097201000003 (58-CE-142(G,N+P)57-LA-140,,INT,,,EVAL)) M097201000004 ANALYSIS Integration of evaluated cross section. M097201000005 STATUS (DEP,M0972006) Evaluated cross section. M097201000006 (TABLE) M097201000007 ENDBIB 5 0 M097201000008 NOCOMMON 0 0 M097201000009 DATA 3 29 M097201000010 EN-MAX DATA DATA-ERR M097201000011 MEV MB*MEV MB*MEV M097201000012 12.6 410.7 13.7 M097201000013 21.6 1029.3 21.1 M097201000014 ENDDATA 4 0 M097201000015 ENDSUBENT 14 0 M097201099999 SUBENT M0972011 20180823 M098M097201100001 BIB 3 4 M097201100002 REACTION (58-CE-142(G,2N)58-CE-140,,INT,,,EVAL) M097201100003 ANALYSIS Integration of evaluated cross section. M097201100004 STATUS (DEP,M0972007) Evaluated cross section. M097201100005 (TABLE) M097201100006 ENDBIB 4 0 M097201100007 NOCOMMON 0 0 M097201100008 DATA 3 19 M097201100009 EN-MAX DATA DATA-ERR M097201100010 MEV MB*MEV MB*MEV M097201100011 21.6 1083.8 23.0 M097201100012 ENDDATA 3 0 M097201100013 ENDSUBENT 12 0 M097201199999 ENDENTRY 11 0 M097299999999