ENTRY 21988 20170206 22592198800000001 SUBENT 21988001 20170206 22592198800100001 BIB 18 321 2198800100002 INSTITUTE (2GERJUL) 2198800100003 REFERENCE (J,NSE,91,162,1985) 2198800100004 AUTHOR (R.Woefle,S.Sudar,S.M.Qaim) 2198800100005 TITLE -Determination of excitation function of triton 2198800100006 emission reaction on aluminum from threshold up to 2198800100007 30 MeV via activation in diverse neutron fields and 2198800100008 unfolding code calculations 2198800100009 FACILITY (CYCLO,2GERJUL) Julich Isochronous Cyclotron(Julic) 2198800100010 INC-SOURCE (D-BE) A beryllium degrader of variable thickness used.2198800100011 Deutron energies 17.5, 20.0, 22.5, 27.5, 30.0 MeV. 2198800100012 Beam current 2-3 microA . 2198800100013 INC-SPECT The fluxes were normalized as SUM(F(Ei)*dE)=10**5 . 2198800100014 Flux distributions obtained with SAND-II code: 2198800100015 - 17.5 MeV deutrons - 20 MeV deutrons 2198800100016 En Flux Error Flux Error2198800100017 MeV n/cm2/sec/MeV % n/cm2/sec/MeV % 2198800100018 2. 20327. 16.4 14511. 18.8 2198800100019 3. 12859. 11.3 11077. 12.6 2198800100020 4. 7724. 10.0 7850. 9.5 2198800100021 5. 5262. 9.7 5816. 8.3 2198800100022 6. 5327. 10.2 5861. 8.5 2198800100023 7. 7194. 8.9 6823. 7.4 2198800100024 8. 7563. 10.3 7540. 8.5 2198800100025 9. 6977. 8.1 7443. 7.0 2198800100026 10. 6551. 6.4 6481. 6.8 2198800100027 11. 5609. 8.2 5478. 9.4 2198800100028 12. 3744. 9.0 4224. 10.2 2198800100029 13. 2026. 7.7 3378. 7.1 2198800100030 14. 1502. 5.7 2820. 4.5 2198800100031 15. 1437. 4.3 2370. 4.2 2198800100032 16. 1412. 4.5 1979. 5.0 2198800100033 17. 1324. 5.9 1609. 6.5 2198800100034 18. 1211. 6.1 1243. 6.9 2198800100035 19. 813. 5.9 925. 5.8 2198800100036 20. 500. 8.3 623. 5.6 2198800100037 21. 245. 13.0 580. 7.2 2198800100038 22. 133. 14.1 507. 9.1 2198800100039 23. 82. 10.0 326. 8.4 2198800100040 24. 58. 5.8 197. 5.9 2198800100041 25. 41. 4.0 113. 4.0 2198800100042 26. 27. 4.7 73. 4.0 2198800100043 27. 19. 5.9 51. 5.0 2198800100044 28. 13. 6.9 40. 5.8 2198800100045 29. 10. 7.3 35. 6.4 2198800100046 30. 8. 7.6 30. 6.7 2198800100047 - 22.5 MeV deutrons - 25 MeV deutrons 2198800100048 En Flux Error Flux Error2198800100049 MeV n/cm2/sec/MeV % n/cm2/sec/MeV % 2198800100050 2. 15771. 23.1 15752. 18.0 2198800100051 3. 10497. 10.3 8536. 11.4 2198800100052 4. 6737. 7.9 4947. 8.8 2198800100053 5. 4844. 11.1 3554. 9.4 2198800100054 6. 4837. 11.4 3812. 9.6 2198800100055 7. 5749. 7.9 4828. 9.4 2198800100056 8. 6586. 6.4 5872. 9.5 2198800100057 9. 6958. 6.3 6297. 6.7 2198800100058 10. 6735. 6.4 6246. 5.8 2198800100059 11. 5812. 7.5 6246. 8.3 2198800100060 12. 4561. 8.2 5495. 8.2 2198800100061 13. 3664. 6.1 4403. 6.3 2198800100062 14. 3108. 4.3 3678. 4.9 2198800100063 15. 2706. 4.2 3154. 4.6 2198800100064 16. 2372. 5.6 2741. 5.7 2198800100065 17. 2052. 7.2 2378. 7.2 2198800100066 18. 1759. 7.3 2109. 8.0 2198800100067 19. 1482. 5.3 1908. 6.8 2198800100068 20. 1200. 6.8 1725. 6.3 2198800100069 21. 899. 11.1 1545. 9.6 2198800100070 22. 561. 14.3 1305. 14.2 2198800100071 23. 283. 13.2 988. 15.6 2198800100072 24. 210. 9.7 654. 12.8 2198800100073 25. 155. 5.8 382. 7.5 2198800100074 26. 120. 4.7 322. 4.3 2198800100075 27. 101. 5.7 300. 4.8 2198800100076 28. 87. 7.4 283. 7.3 2198800100077 29. 80. 8.4 274. 9.2 2198800100078 30. 74. 9.2 267. 10.5 2198800100079 - 27.5 MeV deutrons - 30 MeV deutrons 2198800100080 En Flux Error Flux Error2198800100081 MeV n/cm2/sec/MeV % n/cm2/sec/MeV % 2198800100082 2. 11305. 15.8 10010. 232198800100083 3. 8799. 10.6 7044. 122198800100084 4. 5872. 10.0 4482. 102198800100085 5. 4127. 11.6 3178. 122198800100086 6. 4116. 14.3 2711. 122198800100087 7. 4836. 10.7 3444. 112198800100088 8. 5177. 8.5 4191. 112198800100089 9. 5160. 9.4 4579. 82198800100090 10. 5171. 7.9 4867. 62198800100091 11. 5147. 7.8 5118. 82198800100092 12. 4951. 6.5 5141. 82198800100093 13. 4565. 5.9 5106. 52198800100094 14. 4041. 4.8 4825. 42198800100095 15. 3652. 5.3 4355. 42198800100096 16. 3346. 6.3 3978. 52198800100097 17. 3074. 7.3 3640. 62198800100098 18. 2794. 8.1 3334. 72198800100099 19. 2514. 6.9 3054. 72198800100100 20. 2238. 5.3 2790. 72198800100101 21. 1963. 7.3 2547. 62198800100102 22. 1682. 11.0 2303. 82198800100103 23. 1414. 13.0 2041. 102198800100104 24. 1141. 11.0 1780. 92198800100105 25. 887. 6.3 1521. 62198800100106 26. 651. 4.7 1264. 42198800100107 27. 441. 6.7 1021. 42198800100108 28. 330. 8.7 787. 72198800100109 29. 314. 10.0 556. 82198800100110 30. 312. 10.6 332. 102198800100111 SAMPLE The aluminum sample (99.999% purity ) consisted of 2198800100112 two parts, each 1 x 1 x 0.5 cm thick, between which 2198800100113 a set of 12 flux monitor foils was inserted. 2198800100114 METHOD (ACTIV) Irradiation were done for 5 to 20 hr. 2198800100115 Tritium activities induced in Al samples were separated2198800100116 after addition of H2 carrier by vacuum extraction at 2198800100117 900 degC and were counted in a proportional gas 2198800100118 counting tybe in an anticoincidence arrangement . 2198800100119 DETECTOR (PROPC,GELI) 2198800100120 ANALYSIS The shapes of the neutron spectra were determined by 2198800100121 spectrum unfolding, using the known excitation 2198800100122 functions of the monitor nuclides and their measured 2198800100123 activities. In a second calculational step, the 2198800100124 excitation function for the triton emission process 2198800100125 on Al-27 was obtained from the neutron flux 2198800100126 distributions and the measured tritium activities. 2198800100127 At both calculational stages of iterative code 2198800100128 SAND-II and the generalized least-squares (LSQ) 2198800100129 unfolding code were applied, the latter yielding 2198800100130 additionally the error covariance matrix. 2198800100131 For input and output unfolding codes scheme see 2198800100132 Table VII of NSE,91,162,1985 . 2198800100133 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 11 2198800100134 Max.response region 1.5 - 11.5 MeV 2198800100135 (28-NI-58(N,P)27-CO-58-G,,SIG) 12 2198800100136 Max.response region 3.7 - 15.3 MeV 2198800100137 (26-FE-54(N,P)25-MN-54,,SIG) 13 2198800100138 Max.response region 3.7 - 15.9 MeV 2198800100139 (13-AL-27(N,A)11-NA-24-G,,SIG) 14 2198800100140 Max.response region 8.9 - 17.8 MeV 2198800100141 (29-CU-65(N,P)28-NI-65,,SIG) 15 2198800100142 Max.response region 8.4 - 25.2 MeV 2198800100143 (79-AU-197(N,2N)79-AU-196-G,,SIG) 16 2198800100144 Max.response region 10.1 - 20.0 MeV 2198800100145 (22-TI-48(N,P)21-SC-48,,SIG) 17 2198800100146 Max.response region 10.3 - 23.0 MeV 2198800100147 (27-CO-59(N,2N)27-CO-58-G,,SIG) 18 2198800100148 Max.response region 12.6 - 27.4 MeV 2198800100149 (39-Y-89(N,2N)39-Y-88-G,,SIG) 19 2198800100150 Max.response region 13.6 - 27.5 MeV 2198800100151 (40-ZR-90(N,2N)40-ZR-89-G,,SIG) 20 2198800100152 Max.response region 14.2 - 29.3 MeV 2198800100153 (47-AG-107(N,3N)47-AG-105-G,,SIG) 21 2198800100154 Max.response region >22.5 - >30.0 MeV 2198800100155 (39-Y-89(N,3N)39-Y-87-G,,SIG) 22 2198800100156 Max.response region >27.0 - >30.0 MeV . 2198800100157 Max.response region - region where 2198800100158 SIG(E) > or = 0.5*SIGmaximal . 2198800100159 Threshold monitor reactions were used for neutron 2198800100160 spectrum unfolding. 2198800100161 DECAY-MON (49-IN-115-M,,DG,336.,0.459) 11 2198800100162 (27-CO-58-G,,DG,811.,0.9945) 12 2198800100163 (25-MN-54,,DG,835.,0.9998) 13 2198800100164 (11-NA-24-G,,DG,1369.,0.9999) 14 2198800100165 (28-NI-65,,DG,1482.,0.235) 15 2198800100166 (79-AU-196-G,,DG,356.,0.8761) 16 2198800100167 (21-SC-48,,DG,1312.,1.00) 17 2198800100168 (27-CO-58-G,,DG,811.,0.9945) 18 2198800100169 (39-Y-88-G,,DG,898.,0.937) 19 2198800100170 (40-ZR-89-G,,DG,909.,0.9901) 20 2198800100171 (47-AG-105-G,,DG,345.,0.425) 21 2198800100172 (39-Y-87-G,,DG,485.,0.921) 22 2198800100173 MONIT-REF (,B.P.Bayhurst+,J,PR/C,12,451,1975) 2198800100174 for MONITOR 14,16,19,20,21,22 2198800100175 (,,3,ENDF/B-V,,1979) Dosimetry file . 2198800100176 for MONITOR 11,12,13,17,18 2198800100177 (,S.Tagesen+,B,PH-DAT,13-1,1981) 2198800100178 Physics Data 13-1, Fachinformation zentrum Karlsruhe, 2198800100179 also 2198800100180 (,H.Vonach+,R,IAEA-227,59,1983) Techn.Rep.Ser. 2198800100181 for MONITOR 14 2198800100182 (,D.C.Santry+,J,CJP,44,1183,1966) 2198800100183 for MONITOR 15 2198800100184 CORRECTION .For monitor foils corrections for pile-up effects, 2198800100185 coincidence losses, self-absorption, etc., were 2198800100186 applied. 2198800100187 ERR-ANALYS Error component of measured tritium activities : 2198800100188 ------------------------------------------------------2198800100189 Origin of error component Partial error,% Correlation2198800100190 ------------------------------------------------------2198800100191 -Statistics of sample counting 0.26 - 3.62 2198800100192 -Statistics of calibration 1. + 2198800100193 standard counting 2198800100194 -Plateau uncertainty of 1.5 2198800100195 sample counting 2198800100196 -Plateau uncertainty of 1.5 + 2198800100197 calibration standard counting 2198800100198 -Uncertainty of chemical 1.5 2198800100199 yield of sample 2198800100200 -Disintegration rate uncertainty 3. + 2198800100201 of calibration standard 2198800100202 -Irradiation geometry 2.5 2198800100203 uncertainty, ect. 2198800100204 Typical Error components of 12 measured Monitor 2198800100205 activities : 2198800100206 ------------------------------------------------------2198800100207 Origin of error component Partial error,% Correlation2198800100208 ------------------------------------------------------2198800100209 -Statistics of monitor counting 0.58-2.37 2198800100210 -Statistics of calibration 1. 2198800100211 standard counting 2198800100212 -Pile-up correction uncertainty 0-0.37 2198800100213 for monitor 2198800100214 -Pile-up correction uncertainty 0.28-2.17 + 2198800100215 for calibration standard 2198800100216 -Coincidence losses correction 0-4.45 + 2198800100217 uncertainty for monitor 2198800100218 -Coincidence losses correction 0-3.51 + 2198800100219 uncertainty for calibr.standard 2198800100220 -Gamma-abundance uncertainty 0-1.7 2198800100221 for monitor 2198800100222 -Gamma-abundance uncertainty 0-1.1 + 2198800100223 for calibration standard 2198800100224 -Half-life uncertainty 0-1.34 2198800100225 for monitor 2198800100226 -Half-life uncertainty 0-2.24 + 2198800100227 for calibration standard 2198800100228 -Disintegration rate uncertainty 0.5-2.5 + 2198800100229 for calibration standard 2198800100230 -Irradiation geometry 2. 2198800100231 deviation etc. 2198800100232 -------------------------------------------------------2198800100233 Scale error of the neutron energy was estimated 2-5 % 2198800100234 and not included in error calculations. 2198800100235 (DATA-ERR) Uncertainties given by a code used for 2198800100236 unfolding. 2198800100237 COVARIANCE Activities errors relative covariance matrix in 2198800100238 percent squared after irradiations in six different 2198800100239 neutron fields ( see six spectra in INC-SOURCE) 2198800100240 ------------------------------------------------------2198800100241 1 25.4 2198800100242 2 12.3 36.1 2198800100243 3 12.3 12.3 25.2 2198800100244 4 12.3 12.3 12.3 23.1 (symmetric) 2198800100245 5 12.3 12.3 12.3 12.3 23.4 2198800100246 6 12.3 12.3 12.3 12.3 12.3 23.0 2198800100247 1 2 3 4 5 6 2198800100248 ------------------------------------------------------2198800100249 .Relative error correlation matrix for the Al-27((n,t) 2198800100250 +(n,t+n)) excitation function results(LSQ-2) 2198800100251 ------------------------------------------------------2198800100252 EN(MeV) 11 12 13 14 15 16 17 18 2198800100253 11 1 2198800100254 12 0.50 1 2198800100255 13 0. 0.49 1 (Symmetric) 2198800100256 14 -0.01 -0.02 0.49 1 2198800100257 15 -0.01 -0.02 -0.04 0.48 1 2198800100258 16 -0.01 -0.02 -0.04 -0.05 0.47 1 2198800100259 17 -0.01 -0.03 -0.04 -0.05 -0.06 0.49 1 2198800100260 18 -0.01 -0.02 -0.04 -0.05 -0.06 -0.06 0.45 1 2198800100261 19 -0.01 -0.02 -0.03 -0.04 -0.04 -0.05 -0.05 0.492198800100262 20 0 -0.01 -0.03 -0.03 -0.04 -0.04 -0.04 -0.042198800100263 21 0 -0.01 -0.02 -0.03 -0.04 -0.04 -0.04 -0.042198800100264 22 0 -0.01 -0.02 -0.03 -0.03 -0.04 -0.04 -0.042198800100265 23 0 -0.01 -0.02 -0.02 -0.03 -0.03 -0.03 -0.032198800100266 24 0 0 -0.01 -0.02 -0.02 -0.02 -0.02 -0.022198800100267 25 0 0 -0.01 -0.01 -0.01 -0.02 -0.02 -0.022198800100268 26 0 0 0 -0.01 -0.01 -0.01 -0.01 -0.022198800100269 27 0 0 0 -0.01 -0.01 -0.01 -0.01 -0.012198800100270 28 0 0 0 0 -0.01 -0.01 -0.01 -0.012198800100271 29 0 0 0 0 0 0 0 -0.012198800100272 30 0 0 0 0 0 0 0 0 2198800100273 EN(MeV) 19 20 21 22 23 24 25 26 2198800100274 19 1 2198800100275 20 0.48 1 2198800100276 21 -0.04 0.48 1 2198800100277 22 -0.04 -0.05 0.47 1 2198800100278 23 -0.03 -0.04 -0.06 0.46 1 2198800100279 24 -0.03 -0.04 -0.06 -0.08 0.45 1 2198800100280 25 -0.03 -0.04 -0.06 -0.08 -0.09 0.44 1 2198800100281 26 -0.02 -0.03 -0.05 -0.07 -0.08 -0.09 0.46 1 2198800100282 27 -0.02 -0.03 -0.04 -0.05 -0.06 -0.07 -0.07 0.472198800100283 28 -0.01 -0.02 -0.03 -0.03 -0.04 -0.04 -0.05 -0.042198800100284 29 -0.01 -0.01 -0.02 -0.02 -0.02 -0.03 -0.03 -0.022198800100285 30 0 -0.01 -0.01 -0.01 -0.01 -0.01 -0.01 -0.012198800100286 EN(MeV) 27 28 29 30 2198800100287 27 1 2198800100288 28 0.48 1 2198800100289 29 -0.02 0.49 1 2198800100290 30 -0.01 -0.01 0.50 1 2198800100291 ------------------------------------------------------2198800100292 Relative covariance matrix(symmetric, in percent 2198800100293 squared) of 12 measured Monitor activities for 2198800100294 irradiation with 20-MeV neutrons - Table II of 2198800100295 NSE,91,162,1985 : 2198800100296 1 2 3 4 5 6 7 8 9 10 2198800100297 1 18.4 2198800100298 2 0. 9.60 2198800100299 3 0. 3.84 12.2 2198800100300 4 0. 0. 0. 12.8 2198800100301 5 0. 0. 0. 0. 28.0 2198800100302 6 12.1 0. 0. 0. 0. 21.5 2198800100303 7 0. 0. 0. 4.03 0. 0. 30.3 2198800100304 8 0. 4.22 3.84 0. 0. 0. 0. 9.76 2198800100305 9 0. 0. 0. 0. 0. 0. 0. 0. 20.0 2198800100306 10 0. 0. 0. 0. 0. 0. 0. 0. 12.7 19.1 2198800100307 11 12.1 0. 0. 0. 0. 12.1 0. 0. 0. 0. 2198800100308 12 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 2198800100309 continued: 2198800100310 11 12 2198800100311 11 26.7 2198800100312 12 0. 17.3 2198800100313 HISTORY (19860127C) 2198800100314 (19860210E) 2198800100315 (19860417A) 2198800100316 (19860703E) 2198800100317 (20170206A) M.M. INC-SPECT,DECAY-MON,MONIT-REF were 2198800100318 added. 2198800100319 Article was checked, BIB information was updated in 2198800100320 TITLE, STATUS, MONITOR, ERR-ANALYS, COVARIANCE. 2198800100321 Upper -> lower case correction. 2198800100322 Dates were corrected for 4-digits year. 2198800100323 ENDBIB 321 0 2198800100324 NOCOMMON 0 0 2198800100325 ENDSUBENT 324 0 2198800199999 SUBENT 21988002 20170206 22592198800200001 BIB 3 8 2198800200002 REACTION 1(13-AL-27(N,X)1-H-3,,SIG,,,DERIV) SAND-II 2198800200003 2(13-AL-27(N,X)1-H-3,,SIG,,,DERIV) LSQ-1 2198800200004 3(13-AL-27(N,X)1-H-3,,SIG,,,DERIV) LSQ-2 2198800200005 STATUS (TABLE) Table V of NSE,91,162,1985 2198800200006 HISTORY (19860127C) 2198800200007 (19860210E) 2198800200008 (19860417A) 2198800200009 (19860703E) 2198800200010 ENDBIB 8 0 2198800200011 NOCOMMON 0 0 2198800200012 DATA 7 39 2198800200013 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 32198800200014 DATA-ERR 3 2198800200015 MEV MB PER-CENT MB PER-CENT MB 2198800200016 PER-CENT 2198800200017 1.1000E+01 0.0000E+00 1.0000E+01 0.0000E+00 1.9900E+01 1.0000E-022198800200018 1.0300E+01 2198800200019 1.1500E+01 1.9000E-01 9.5000E+00 1.9000E-01 1.9900E+01 2198800200020 2198800200021 1.2000E+01 4.1000E-01 8.0000E+00 4.1000E-01 1.9900E+01 3.1000E-012198800200022 8.1000E+00 2198800200023 1.2500E+01 6.4000E-01 6.8000E+00 6.4000E-01 1.9900E+01 2198800200024 2198800200025 1.3000E+01 8.8000E-01 6.8000E+00 8.8000E-01 1.9900E+01 9.0000E-012198800200026 6.9000E+00 2198800200027 1.3500E+01 1.1300E+00 7.0000E+00 1.1300E+00 1.9900E+01 2198800200028 2198800200029 1.4000E+01 1.3900E+00 6.2000E+00 1.3900E+00 1.9800E+01 1.4100E+002198800200030 6.4000E+00 2198800200031 1.4500E+01 1.6400E+00 6.0000E+00 1.6400E+00 1.9800E+01 2198800200032 2198800200033 1.5000E+01 1.9000E+00 5.3000E+00 1.9000E+00 1.9700E+01 1.9300E+002198800200034 5.5000E+00 2198800200035 1.5500E+01 2.1700E+00 5.2000E+00 2.1700E+00 1.9700E+01 2198800200036 2198800200037 1.6000E+01 2.4600E+00 5.3000E+00 2.4700E+00 1.9600E+01 2.5100E+002198800200038 5.3000E+00 2198800200039 1.6500E+01 2.7700E+00 5.3000E+00 2.7800E+00 1.9600E+01 2198800200040 2198800200041 1.7000E+01 3.1200E+00 5.2000E+00 3.1300E+00 1.9600E+01 3.1900E+002198800200042 5.0000E+00 2198800200043 1.7500E+01 3.5100E+00 4.5000E+00 3.5200E+00 1.9500E+01 2198800200044 2198800200045 1.8000E+01 3.9400E+00 5.5000E+00 3.9600E+00 1.9400E+01 4.0300E+002198800200046 4.8000E+00 2198800200047 1.8500E+01 4.4600E+00 4.3000E+00 4.4800E+00 1.9400E+01 2198800200048 2198800200049 1.9000E+01 4.8100E+00 3.5000E+00 4.8200E+00 1.9500E+01 4.9000E+002198800200050 3.5000E+00 2198800200051 1.9500E+01 5.2600E+00 2.7000E+00 5.2700E+00 1.9500E+01 2198800200052 2198800200053 2.0000E+01 5.6600E+00 4.3000E+00 5.6800E+00 1.9500E+01 5.7500E+002198800200054 3.8000E+00 2198800200055 2.0500E+01 5.8100E+00 4.5000E+00 5.8100E+00 1.9600E+00 2198800200056 2198800200057 2.1000E+01 5.9800E+00 5.5000E+00 5.9800E+00 1.9700E+01 6.0300E+002198800200058 5.5000E+00 2198800200059 2.1500E+01 6.1800E+00 6.6000E+00 6.1700E+00 1.9700E+01 2198800200060 2198800200061 2.2000E+01 6.4300E+00 5.9000E+00 6.4200E+00 1.9800E+01 6.4500E+002198800200062 7.1000E+00 2198800200063 2.2500E+01 6.8300E+00 8.7000E+00 6.8300E+00 1.9800E+01 2198800200064 2198800200065 2.3000E+01 7.0600E+00 7.2000E+00 7.0600E+00 1.9800E+01 7.0800E+002198800200066 7.9000E+00 2198800200067 2.3500E+01 7.2800E+00 7.8000E+00 7.2800E+00 1.9800E+01 2198800200068 2198800200069 2.4000E+01 7.7900E+00 8.5000E+00 7.8100E+00 1.9800E+01 7.8100E+002198800200070 9.1000E+00 2198800200071 2.4500E+01 7.9800E+00 1.1000E+01 8.0000E+00 1.9800E+00 2198800200072 2198800200073 2.5000E+01 8.1500E+00 1.2000E+01 8.1700E+00 1.9900E+01 8.1200E+002198800200074 1.1700E+01 2198800200075 2.5500E+01 8.2700E+00 1.2100E+01 8.3000E+00 1.9900E+01 2198800200076 2198800200077 2.6000E+01 8.2800E+00 1.2600E+01 8.3000E+00 1.9900E+01 8.3000E+002198800200078 1.2400E+01 2198800200079 2.6500E+01 8.1300E+00 1.2500E+01 8.1600E+00 1.9900E+01 2198800200080 2198800200081 2.7000E+01 7.8500E+00 1.2000E+01 7.8800E+00 1.9900E+01 7.9400E+002198800200082 1.2200E+01 2198800200083 2.7500E+01 7.3200E+00 1.2000E+01 7.3500E+00 1.9900E+01 2198800200084 2198800200085 2.8000E+01 6.8000E+00 1.1900E+01 6.8300E+00 1.9900E+01 6.9000E+002198800200086 1.1500E+01 2198800200087 2.8500E+01 6.0200E+00 1.0600E+01 6.0400E+00 1.9900E+01 2198800200088 2198800200089 2.9000E+01 5.2200E+00 1.0400E+01 5.2400E+00 1.9900E+01 5.3000E+002198800200090 1.0500E+01 2198800200091 2.9500E+01 4.5300E+00 1.0500E+01 4.5500E+00 1.9900E+01 2198800200092 2198800200093 3.0000E+01 3.7600E+00 1.2900E+01 3.7800E+00 1.9900E+01 3.8200E+002198800200094 1.2100E+01 2198800200095 ENDDATA 82 0 2198800200096 ENDSUBENT 95 0 2198800299999 ENDENTRY 2 0 2198899999999