ENTRY 22655 20120120 Y0082265500000001 SUBENT 22655001 20120120 Y0082265500100001 BIB 19 186 2265500100002 INSTITUTE (2ZZZGEL) Reimer, Plompen 2265500100003 (2GERJUL) Qaim, Sudar 2265500100004 (2NEDNRG) A.Koning . 2265500100005 REFERENCE (J,NP/A,815,1,2009) Data are given. Main reference. 2265500100006 ((T,REIMER,20011013)=(R,JUEL-3980,2001)) 2265500100007 Data are given. 2265500100008 ((S,ISINN-8,159,2000)= 2265500100009 (S,JINR-E3-2000-192,159,2000)) 2265500100010 Prelim.data for Tc-99(n,a) and Tc-99(n,p) on Fig.2 . 2265500100011 AUTHOR (P.Reimer, S.Sudar, A.J.M.Plompen, S.M.Qaim,A.J.Koning,2265500100012 V.Avrigeanu) 2265500100013 TITLE -Neutron induced reaction cross sections for the 2265500100014 radioactive target nucleus Tc-99. 2265500100015 FACILITY (VDG,2ZZZGEL) 7-MV Van de Graaff Accelerator, 2265500100016 Neutron Physics Unit, IRMM, Belgium . 2265500100017 (CYCLO,2GERJUL) Compact Cyclotron CV-28, 2265500100018 Institute For Nuclear Chemistry, Juelich, Germany. 2265500100019 INC-SOURCE (P-T) H-3(P,N)He-3. Protons incident on a metal 2265500100020 titanium-tritium target (1.923 mg/cm**2 thick) 2265500100021 on a silver backing (0.5 mm thick). Neutron energies 2265500100022 range 0.5 to 6 MeV. Energy scale uncertainty is 5 keV.2265500100023 (D-D) H-2(D,N)He-3. Deuterons incident on a 2265500100024 deuterium gas target. Neutrons in energies range 2265500100025 7.4 to 12.5 MeV. Energy scale uncertainty is 5 keV. 2265500100026 (D-T) H-3(D,N)He-4. Deuterons incident on a metal 2265500100027 titanium-tritium target (1.923 mg/cm**2 thick) 2265500100028 on a silver backing (0.5 mm thick). Neutrons with 2265500100029 energies in the range 13.4 to 20.6 MeV. 2265500100030 Energy scale uncertainty is 5 keV. 2265500100031 INC-SPECT -The primary neutron spectra from each of the sources 2265500100032 used were quasi-monoenergetic. A continuum spectrum 2265500100033 of low-energy neutrons was present for each source 2265500100034 reaction. 2265500100035 -Secondary neutron spectra were derived from comparison2265500100036 of secondary monitor foil activity with known 2265500100037 excitation function . 2265500100038 SAMPLE -All the sample materials were metallic. These were 2265500100039 then sealed in aluminum containers with a wall 2265500100040 thickness of 0.2 mm in order to guarantee mechanical 2265500100041 stability of the samples and prevent contamination 2265500100042 of the environment with radioactive material. The 2265500100043 aluminum capsules were further sealed in polyethylene 2265500100044 bags (0.2 mm thick). Foils of indium, nickel, 2265500100045 aluminum, iron, cobalt, and niobium with thicknesses 2265500100046 in the range 50 to 250 micro-meters and 13-mm diameter2265500100047 were used along with the technetium sample capsules 2265500100048 to form sample packets. 2265500100049 -Some of these foils served as primary or secondary 2265500100050 standards for neutron fluence determination. 2265500100051 METHOD (ACTIV) Cross sections were measured using the neutron 2265500100052 activation method. 2265500100053 The reaction products are relatively short-lived. 2265500100054 In the case of the D-D measurements using a deuterium 2265500100055 gas target, irradiations were also carried out using 2265500100056 an empty cell before and after each main irradiation 2265500100057 so that corrections for background neutrons from the 2265500100058 target could be determined. 2265500100059 These intrinsically radioactive samples. This 2265500100060 background was reduced to manageable levels by 2265500100061 either counting at a distance and/or inserting lead 2265500100062 sheet (1 or 2 mm thick) between sample and detector. 2265500100063 (CHSEP) For thick samples and elements with great 2265500100064 half-life . 2265500100065 (GSPEC) Standard gamma-ray spectroscopy for measurement2265500100066 of radioactivity. 2265500100067 DETECTOR (HPGE) Several (four) high purity germanium detectors. 2265500100068 (SCIN) Bonner sphere detector. 2265500100069 (BF3) Boron-trifluoride detector in a long counter 2265500100070 configuration. 2265500100071 (LONGC) Long counter for relative measurements. 2265500100072 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) Primary Standard 2265500100073 used for measurements with neutron energy above 6 MeV.2265500100074 (49-IN-115(N,INL)49-IN-115-M,,SIG) Primary Standard 2265500100075 used for measurements with neutron energy below 6 MeV.2265500100076 (13-AL-27(N,P)12-MG-27,,SIG) Secondary Standard. 2265500100077 (26-FE-56(N,P)25-MN-56,,SIG) Secondary Standard . 2265500100078 (27-CO-59(N,2N)27-CO-58,,SIG) Secondary Standard . 2265500100079 (28-NI-58(N,P)27-CO-58,,SIG) Secondary Standard . 2265500100080 (41-NB-93(N,2N)41-NB-92-M,,SIG) Secondary Standard. 2265500100081 All measurements involving secondary standards were 2265500100082 eventually referenced to the primary standards. 2265500100083 All relative measurements were eventually normalized 2265500100084 to the primary standards. 2265500100085 DECAY-MON (11-NA-24,14.9590HR,DG,1369.,1.0) 2265500100086 (12-MG-27,9.458MIN,DG,843.76,0.718) 2265500100087 (25-MN-56,2.5749HR,DG,846.75,0.989) 2265500100088 (27-CO-58,70.82D,DG,810.78,0.9945) 2265500100089 (41-NB-92-M,10.15D,DG,934.44,0.9907) 2265500100090 (49-IN-115-M,4.486HR,DG,336.24,0.458) 2265500100091 MONIT-REF (,H.Conde,R,INDC(SEC)-101,1992) Also H.Conde, 2265500100092 R,NEANDC-311"U" 2265500100093 (,M.Wagner+,B,PH-DAT,13,1355,1990) 2265500100094 (,A.B.Smith+,R,ANL-NDM-115,1990) 2265500100095 (,P.F.Rose+,R,ENDF-201,1991) Evaluated Nuclear 2265500100096 Data File, ENDF/B-VI.6 2265500100097 (,H.Conde,R,INDC(SEC)-101,1992) See also 2265500100098 H,Conde,R,NEANDC-311/U,1992 2265500100099 M.Wagner+,R,INDC(AUS)-D14,199110 2265500100100 ANALYSIS -The neutron scattering corrections were derived by 2265500100101 the Monte-Carlo method using the computer code MCNP. 2265500100102 The low-energy neutron corrections were deduced 2265500100103 using a representation of the neutron spectrum, 2265500100104 evaluated cross sections for the monitor reactions, 2265500100105 and estimates of the unknown technetium cross section 2265500100106 shape. The neutron spectrum determined by time-of- 2265500100107 flight measurement was transformed into a few group 2265500100108 representation which was then adjusted by an 2265500100109 application of the generalized least-squares method 2265500100110 that employed measured reaction rates for several 2265500100111 monitor reactions. Final cross sections were deduced 2265500100112 from the cross ratios and values for the primary 2265500100113 standards. In those cases where measurements were 2265500100114 made relative to secondary standards or to relative 2265500100115 neutron fluence monitors, the data were normalized to 2265500100116 the primary standards by specific ratio measurements 2265500100117 of the secondary standards to the primary standards 2265500100118 or by calibration of the relative monitors to these 2265500100119 standards. 2265500100120 ADD-RES (THEO) For all measurements nuclear model calculations2265500100121 were produced using models of the Hauser- 2265500100122 Feshbach type (HELGA, GNASH, EMPIRE, STAPRE, 2265500100123 STAPRE-H) 2265500100124 CORRECTION -The raw experimental data were corrected for the 2265500100125 following effects: 2265500100126 . Gamma-ray detection efficiency. 2265500100127 . Gamma-ray branching factors. 2265500100128 . Gamma-ray coincidence summing effects. 2265500100129 . Geometric effects. 2265500100130 . Gamma-ray absorption. 2265500100131 . Absorption and scattering of neutrons. 2265500100132 . Low-energy neutrons from the target. 2265500100133 . Decay of product nuclei. 2265500100134 . Fluctuations in neutron flux during the 2265500100135 irradiation period. 2265500100136 . Isotopic abundances. 2265500100137 . Sample chemical composition and impurities. 2265500100138 ERR-ANALYS (ERR-T) Total errors for the cross sections were 2265500100139 deduced by combining partial errors from 2265500100140 various sources in quadrature. Error sources 2265500100141 considered were: 2265500100142 (ERR-S,,25.) Max Statistical counting error - 25% 2265500100143 (ERR-1,,3.) Max Uncertainty in detector 2265500100144 efficiencies - 3% 2265500100145 (ERR-2,,8.) Max Uncertainty in gamma-emission 2265500100146 probability - 8% 2265500100147 (ERR-3,,8.) Max Uncertainty in decay half lives - 8% 2265500100148 (ERR-4,,7.) Max Uncertainty in coincidence summing 2265500100149 corrections - 7% 2265500100150 (ERR-5,,3.) Max Uncertainty in the absorption of 2265500100151 gamma-rays - 3% 2265500100152 (ERR-6,,1.) Max Uncertainty due to sample mass - 1% 2265500100153 (ERR-7,,1.) Max Uncertainty due to counting time - 1% 2265500100154 (ERR-8,,1.) Max Uncertainty due to cooling time - 1% 2265500100155 (ERR-9,,6.) Max Uncertainty due to gas-in/gas-out 2265500100156 background neutrons - 6% 2265500100157 (ERR-10,,16.) Max Uncertainty due to breakup 2265500100158 neutrons - 16% 2265500100159 (ERR-11,,12.) Max Uncertainty in low-energy neutron 2265500100160 corrections - 12% 2265500100161 (ERR-12,,0.5) Max Uncertainty due to neutron flux 2265500100162 fluctuations - 0.5% 2265500100163 (ERR-13,,10.) Max Uncertainty due to reference cross 2265500100164 section error - valid for Tc-99(N,N'GAMMA) 2265500100165 and In-115(N,N'GAMMA) reactions - 10% 2265500100166 (ERR-14) Most frequently occurring uncertainty due to 2265500100167 reference cross section error . 2265500100168 EN-ERR Max Error in the center of neutron energy line2265500100169 - 5. keV . 2265500100170 COMMENT -Monitor cross-section values at arbitrary neutron 2265500100171 energies were derived from tabulated values by means 2265500100172 of linear interpolation. 2265500100173 HISTORY (20011013) Compiled by the authors. 2265500100174 (20020710A) Corrected J.O.S. 2265500100175 (20030505A) Error structure given 2265500100176 BIB-information specified. 2265500100177 (20030511U) Last checking has been done. 2265500100178 (20090812A) M.M. Reference J,NP/A,815 was added. 2265500100179 BIB information was added. 2265500100180 Subents 005-007 were added. 2265500100181 Maximal errors values were moved from COMMON block 2265500100182 into ERR-ANALYS lines. Corrected : ERR-1 -> ERR-S . 2265500100183 Errors number were re-numerated. 2265500100184 Reference (C,2001TSUKUB,,(901),200110) was deleted , 2265500100185 because does not contain the data for Tc . 2265500100186 (#901 is article of page 192 of 2001TSUKUBA). 2265500100187 (20120120A) NDS(VZ): REL-REF: ND/B->NDS in 007. 2265500100188 ENDBIB 186 0 2265500100189 COMMON 1 3 2265500100190 ERR-14 2265500100191 PER-CENT 2265500100192 3. 2265500100193 ENDCOMMON 3 0 2265500100194 ENDSUBENT 193 0 2265500199999 SUBENT 22655002 20090812 22142265500200001 BIB 4 9 2265500200002 REACTION (43-TC-99(N,A)41-NB-96,,SIG) 2265500200003 DECAY-DATA (41-NB-96,23.35HR,DG,568.9,0.58) 2265500200004 SAMPLE The technetium samples were produced by pressing 2265500200005 about 0.5 g of metal into disks of 13-mm diameter. 2265500200006 Admixture of Tc-98 (HL-4.2E+6 YR) is negligible . 2265500200007 STATUS (APRVD) A.Plompen, 2002-07-13 2265500200008 (TABLE) Data provided in tabular form by an author. 2265500200009 From Table 5.14 of T,REIMER,2001, either. 2265500200010 (SPSDD,22655005) Superseded as newer publication. 2265500200011 ENDBIB 9 0 2265500200012 NOCOMMON 0 0 2265500200013 DATA 4 12 2265500200014 EN EN-RSL-FW DATA ERR-T 2265500200015 MEV MEV MB MB 2265500200016 8.618 0.215 0.567 0.054 2265500200017 9.752 0.234 1.150 0.10 2265500200018 10.546 0.244 1.660 0.14 2265500200019 11.616 0.269 2.450 0.22 2265500200020 12.418 0.285 3.440 0.29 2265500200021 13.883 0.155 4.500 0.26 2265500200022 14.360 0.200 5.650 0.48 2265500200023 14.813 0.183 6.140 0.60 2265500200024 16.160 0.260 6.320 0.33 2265500200025 17.820 0.190 6.310 0.33 2265500200026 19.140 0.210 5.830 0.39 2265500200027 20.430 0.180 5.250 0.39 2265500200028 ENDDATA 14 0 2265500200029 ENDSUBENT 28 0 2265500299999 SUBENT 22655003 20090812 22142265500300001 BIB 4 9 2265500300002 REACTION (43-TC-99(N,P)42-MO-99,,SIG) 2265500300003 DECAY-DATA (42-MO-99,65.94HR,DG,739.5,0.1213) 2265500300004 SAMPLE The technetium samples were produced by pressing 2265500300005 about 0.5 g of metal into disks of 13-mm diameter. 2265500300006 Admixture of Tc-98 (HL-4.2E+6 YR) is negligible . 2265500300007 STATUS (APRVD) A.Plompen, 2002-07-13 2265500300008 (TABLE) Data provided in tabular form by an author. 2265500300009 From Table 5.14 of T,REIMER,2001, either. 2265500300010 (SPSDD,22655006) Superseded as newer publication. 2265500300011 ENDBIB 9 0 2265500300012 NOCOMMON 0 0 2265500300013 DATA 4 12 2265500300014 EN EN-RSL-FW DATA ERR-T 2265500300015 MEV MEV MB MB 2265500300016 8.618 0.215 1.116 0.234 2265500300017 9.752 0.234 2.55 0.150 2265500300018 10.546 0.244 4.17 0.250 2265500300019 11.616 0.269 5.87 0.460 2265500300020 12.418 0.285 9.00 0.850 2265500300021 13.883 0.155 11.27 0.600 2265500300022 14.360 0.200 13.55 1.210 2265500300023 14.813 0.183 14.57 1.120 2265500300024 16.160 0.260 14.29 0.930 2265500300025 17.820 0.190 14.96 0.810 2265500300026 19.140 0.210 14.34 0.910 2265500300027 20.430 0.180 16.10 1.290 2265500300028 ENDDATA 14 0 2265500300029 ENDSUBENT 28 0 2265500399999 SUBENT 22655004 20090812 22142265500400001 BIB 4 9 2265500400002 REACTION (43-TC-99(N,INL)43-TC-99-M,,SIG) 2265500400003 DECAY-DATA (43-TC-99-M,6.01HR,DG,140.5,0.8906) 2265500400004 SAMPLE The technetium samples were produced by pressing 2265500400005 about 0.5 g of metal into disks of 13-mm diameter. 2265500400006 Admixture of Tc-98 (HL-4.2E+6 YR) is negligible . 2265500400007 STATUS (APRVD) A.Plompen, 2002-07-13 2265500400008 (TABLE) Data provided in tabular form by an author. 2265500400009 From Table 5.12 of T,REIMER,2001, either. 2265500400010 (SPSDD,22655007) Superseded as newer publication. 2265500400011 ENDBIB 9 0 2265500400012 NOCOMMON 0 0 2265500400013 DATA 4 20 2265500400014 EN EN-RSL-FW DATA ERR-T 2265500400015 MEV MEV MB MB 2265500400016 0.4822 0.0760 6.27 3.94 2265500400017 0.9777 0.0585 78.53 11.72 2265500400018 2.0227 0.0422 211.03 17.01 2265500400019 2.9774 0.0343 222.82 18.93 2265500400020 3.9734 0.0290 239.09 20.10 2265500400021 4.9285 0.0252 323.16 30.40 2265500400022 5.4270 0.0237 318.23 39.02 2265500400023 5.9130 0.0805 310.01 41.00 2265500400024 7.4720 0.2020 309.07 19.20 2265500400025 8.6150 0.2200 297.45 16.20 2265500400026 9.5550 0.2330 269.02 21.68 2265500400027 10.7180 0.2410 204.81 22.62 2265500400028 12.4180 0.2850 110.12 19.89 2265500400029 13.8800 0.1500 77.39 4.83 2265500400030 14.3600 0.2000 77.12 6.75 2265500400031 14.8100 0.1900 64.80 4.00 2265500400032 16.2600 0.2600 60.82 5.43 2265500400033 17.9900 0.1280 56.24 6.18 2265500400034 19.3400 0.1030 63.81 10.20 2265500400035 20.5900 0.0940 71.16 22.46 2265500400036 ENDDATA 22 0 2265500400037 ENDSUBENT 36 0 2265500499999 SUBENT 22655005 20090812 22142265500500001 BIB 4 18 2265500500002 REACTION (43-TC-99(N,A)41-NB-96,,SIG) 2265500500003 DECAY-DATA (41-NB-96,23.35HR,DG,778.2,0.9645, 2265500500004 DG,568.9,0.580, 2265500500005 DG,1091.4,0.585, 2265500500006 DG,460.0,0.2662) 2265500500007 Error of Nb-96 half-life 0.05 hr, 2265500500008 Errors of intensities: 0.0022, 0.003, 0.015, 0.0019, 2265500500009 respectively. 2265500500010 Decay data from NuDat-2 data base, 2008. 2265500500011 Measurement of Nb-96 yield via 569.9 keV gamma-ray was2265500500012 possible by inserting 2mm Pb sheet between the sample 2265500500013 and detector. 2265500500014 Strongest gamma-ray 778.2 keV was not used because of 2265500500015 it's overlap with 777.9 keV gamma-ray of Mo-99. 2265500500016 ADD-RES (COMP) Data compared with calculations by TALYS and 2265500500017 STAPRE codes. 2265500500018 STATUS (TABLE) Table 5 of J,NP/A,815 . 2265500500019 (DEP,22655002) 2265500500020 ENDBIB 18 0 2265500500021 NOCOMMON 0 0 2265500500022 DATA 4 12 2265500500023 EN EN-RSL-FW DATA ERR-T 2265500500024 MEV MEV MB MB 2265500500025 8.6 0.2 0.6 0.1 2265500500026 9.8 0.2 1.1 0.1 2265500500027 10.6 0.2 1.7 0.1 2265500500028 11.6 0.3 2.5 0.2 2265500500029 12.4 0.3 3.4 0.3 2265500500030 13.9 0.3 4.5 0.3 2265500500031 14.4 0.2 5.7 0.5 2265500500032 14.8 0.2 6.1 0.6 2265500500033 16.2 0.3 6.3 0.3 2265500500034 17.8 0.2 6.3 0.3 2265500500035 19.1 0.2 5.8 0.4 2265500500036 20.4 0.2 5.3 0.4 2265500500037 ENDDATA 14 0 2265500500038 ENDSUBENT 37 0 2265500599999 SUBENT 22655006 20090812 22142265500600001 BIB 4 15 2265500600002 REACTION (43-TC-99(N,P)42-MO-99,,SIG) 2265500600003 DECAY-DATA (42-MO-99,65.94HR,DG,739.5,0.1213, 2265500600004 DG,181.1,0.0599, 2265500600005 DG,777.9,0.0426) 2265500600006 Error of Mo-99 half-life 0.01 hr, 2265500600007 Errors of intensities: 0.0022, 0.0011,0.0008, 2265500600008 respectively. 2265500600009 Decay data from NuDat-2 data base, 2008. 2265500600010 Measurement of Mo-99 yield via 739.5 keV gamma-ray was2265500600011 possible by inserting 2mm Pb sheet between the sample 2265500600012 and detector. 2265500600013 ADD-RES (COMP) Data compared with calculations by TALYS and 2265500600014 STAPRE codes. 2265500600015 STATUS (TABLE) Table 5 of J,NP/A,815 . 2265500600016 (DEP,22655003) 2265500600017 ENDBIB 15 0 2265500600018 NOCOMMON 0 0 2265500600019 DATA 4 12 2265500600020 EN EN-RSL-FW DATA ERR-T 2265500600021 MEV MEV MB MB 2265500600022 8.6 0.2 1.1 0.2 2265500600023 9.8 0.2 2.5 0.1 2265500600024 10.6 0.2 4.2 0.3 2265500600025 11.6 0.3 5.9 0.5 2265500600026 12.4 0.3 9.0 0.8 2265500600027 13.9 0.3 11.3 0.6 2265500600028 14.4 0.2 13.6 1.2 2265500600029 14.8 0.2 14.6 1.1 2265500600030 16.2 0.3 14.3 0.9 2265500600031 17.8 0.2 15.0 0.8 2265500600032 19.1 0.2 14.3 0.9 2265500600033 20.4 0.2 16.1 1.3 2265500600034 ENDDATA 14 0 2265500600035 ENDSUBENT 34 0 2265500699999 SUBENT 22655007 20120120 Y0082265500700001 BIB 8 21 2265500700002 REACTION (43-TC-99(N,INL)43-TC-99-M,,SIG) 2265500700003 DECAY-DATA (43-TC-99-M,6.015HR,DG,140.5,0.8903) 2265500700004 Error of Tc-99m half life 0.009 hr. 2265500700005 Intensity error 0.0048 . 2265500700006 The yield of Tc-99m measured via 140.5 gamma-ray was 2265500700007 obtained at 20 or 30 cm distance without lead absorber2265500700008 (Juelich) or at 7.5 cm with 1 mm of lead to shield 2265500700009 the detector (Geel). 2265500700010 REL-REF (R,,J.K.Tuli+,J,NDS,93,1,2001) Reference for decay 2265500700011 data. 2265500700012 ANALYSIS Reaction rates per atom are multiplied with the 2265500700013 correction factors to obtain the peak rates at the 2265500700014 primary neutron energy. 2265500700015 MISC-COL (MISC1) Factor of correction for low energy neutrons. 2265500700016 (MISC2) Factor of correction for scattering . 2265500700017 (MISC3) Factor of correction for breakup. 2265500700018 ADD-RES (COMP) Data compared with calculations by TALYS and 2265500700019 STAPRE codes. 2265500700020 STATUS (TABLE) Table 4 of J,NP/A,815 . 2265500700021 (DEP,22655004) 2265500700022 HISTORY (20120120A) NDS(VZ): REL-REF: ND/B->NDS 2265500700023 ENDBIB 21 0 2265500700024 NOCOMMON 0 0 2265500700025 DATA 10 20 2265500700026 EN EN-RSL-FW DATA ERR-T MISC1 MISC1-ERR 2265500700027 MISC2 MISC1-ERR MISC3 MISC1-ERR 2265500700028 MEV MEV MB MB NO-DIM NO-DIM 2265500700029 NO-DIM NO-DIM NO-DIM NO-DIM 2265500700030 0.48 0.08 6. 4. 2265500700031 2265500700032 0.98 0.06 79. 12. 2265500700033 2265500700034 2.02 0.04 211. 17. 2265500700035 2265500700036 2.98 0.03 223. 19. 2265500700037 2265500700038 3.97 0.03 239. 20. 2265500700039 2265500700040 4.93 0.03 323. 30. 2265500700041 2265500700042 5.43 0.02 318. 39. 2265500700043 2265500700044 5.91 0.01 310. 41. 2265500700045 2265500700046 7.5 0.2 309. 19. 0.92 0.01 2265500700047 1. 2265500700048 8.6 0.2 297. 16. 0.87 0.01 2265500700049 0.97 0.01 2265500700050 9.6 0.2 269. 22. 0.71 0.02 2265500700051 0.76 0.04 2265500700052 10.7 0.2 205. 23. 0.73 0.02 2265500700053 0.54 0.05 2265500700054 12.4 0.3 110. 20. 0.47 0.03 2265500700055 0.26 0.04 2265500700056 13.9 0.2 77.4 4.8 2265500700057 2265500700058 14.4 0.2 77.1 6.8 2265500700059 2265500700060 14.8 0.2 64.8 4.0 2265500700061 2265500700062 16.3 0.3 60.8 5.4 1. 2265500700063 0.88 0.01 2265500700064 18.0 0.1 56.2 6.2 0.84 0.05 2265500700065 0.88 0.01 2265500700066 19.3 0.1 63.8 10.2 0.36 0.04 2265500700067 0.89 0.01 2265500700068 20.6 0.1 71.2 22.5 0.14 0.04 2265500700069 0.90 0.01 2265500700070 ENDDATA 44 0 2265500700071 ENDSUBENT 70 0 2265500799999 ENDENTRY 7 0 2265599999999