ENTRY 21988 20170206 225921988 0 1 SUBENT 21988001 20170206 225921988 1 1 BIB 18 321 21988 1 2 INSTITUTE (2GERJUL) 21988 1 3 REFERENCE (J,NSE,91,162,1985) 21988 1 4 AUTHOR (R.Woefle,S.Sudar,S.M.Qaim) 21988 1 5 TITLE -Determination of excitation function of triton 21988 1 6 emission reaction on aluminum from threshold up to 21988 1 7 30 MeV via activation in diverse neutron fields and 21988 1 8 unfolding code calculations 21988 1 9 FACILITY (CYCLO,2GERJUL) Julich Isochronous Cyclotron(Julic) 21988 1 10 INC-SOURCE (D-BE) A beryllium degrader of variable thickness used.21988 1 11 Deutron energies 17.5, 20.0, 22.5, 27.5, 30.0 MeV. 21988 1 12 Beam current 2-3 microA . 21988 1 13 INC-SPECT The fluxes were normalized as SUM(F(Ei)*dE)=10**5 . 21988 1 14 Flux distributions obtained with SAND-II code: 21988 1 15 - 17.5 MeV deutrons - 20 MeV deutrons 21988 1 16 En Flux Error Flux Error21988 1 17 MeV n/cm2/sec/MeV % n/cm2/sec/MeV % 21988 1 18 2. 20327. 16.4 14511. 18.8 21988 1 19 3. 12859. 11.3 11077. 12.6 21988 1 20 4. 7724. 10.0 7850. 9.5 21988 1 21 5. 5262. 9.7 5816. 8.3 21988 1 22 6. 5327. 10.2 5861. 8.5 21988 1 23 7. 7194. 8.9 6823. 7.4 21988 1 24 8. 7563. 10.3 7540. 8.5 21988 1 25 9. 6977. 8.1 7443. 7.0 21988 1 26 10. 6551. 6.4 6481. 6.8 21988 1 27 11. 5609. 8.2 5478. 9.4 21988 1 28 12. 3744. 9.0 4224. 10.2 21988 1 29 13. 2026. 7.7 3378. 7.1 21988 1 30 14. 1502. 5.7 2820. 4.5 21988 1 31 15. 1437. 4.3 2370. 4.2 21988 1 32 16. 1412. 4.5 1979. 5.0 21988 1 33 17. 1324. 5.9 1609. 6.5 21988 1 34 18. 1211. 6.1 1243. 6.9 21988 1 35 19. 813. 5.9 925. 5.8 21988 1 36 20. 500. 8.3 623. 5.6 21988 1 37 21. 245. 13.0 580. 7.2 21988 1 38 22. 133. 14.1 507. 9.1 21988 1 39 23. 82. 10.0 326. 8.4 21988 1 40 24. 58. 5.8 197. 5.9 21988 1 41 25. 41. 4.0 113. 4.0 21988 1 42 26. 27. 4.7 73. 4.0 21988 1 43 27. 19. 5.9 51. 5.0 21988 1 44 28. 13. 6.9 40. 5.8 21988 1 45 29. 10. 7.3 35. 6.4 21988 1 46 30. 8. 7.6 30. 6.7 21988 1 47 - 22.5 MeV deutrons - 25 MeV deutrons 21988 1 48 En Flux Error Flux Error21988 1 49 MeV n/cm2/sec/MeV % n/cm2/sec/MeV % 21988 1 50 2. 15771. 23.1 15752. 18.0 21988 1 51 3. 10497. 10.3 8536. 11.4 21988 1 52 4. 6737. 7.9 4947. 8.8 21988 1 53 5. 4844. 11.1 3554. 9.4 21988 1 54 6. 4837. 11.4 3812. 9.6 21988 1 55 7. 5749. 7.9 4828. 9.4 21988 1 56 8. 6586. 6.4 5872. 9.5 21988 1 57 9. 6958. 6.3 6297. 6.7 21988 1 58 10. 6735. 6.4 6246. 5.8 21988 1 59 11. 5812. 7.5 6246. 8.3 21988 1 60 12. 4561. 8.2 5495. 8.2 21988 1 61 13. 3664. 6.1 4403. 6.3 21988 1 62 14. 3108. 4.3 3678. 4.9 21988 1 63 15. 2706. 4.2 3154. 4.6 21988 1 64 16. 2372. 5.6 2741. 5.7 21988 1 65 17. 2052. 7.2 2378. 7.2 21988 1 66 18. 1759. 7.3 2109. 8.0 21988 1 67 19. 1482. 5.3 1908. 6.8 21988 1 68 20. 1200. 6.8 1725. 6.3 21988 1 69 21. 899. 11.1 1545. 9.6 21988 1 70 22. 561. 14.3 1305. 14.2 21988 1 71 23. 283. 13.2 988. 15.6 21988 1 72 24. 210. 9.7 654. 12.8 21988 1 73 25. 155. 5.8 382. 7.5 21988 1 74 26. 120. 4.7 322. 4.3 21988 1 75 27. 101. 5.7 300. 4.8 21988 1 76 28. 87. 7.4 283. 7.3 21988 1 77 29. 80. 8.4 274. 9.2 21988 1 78 30. 74. 9.2 267. 10.5 21988 1 79 - 27.5 MeV deutrons - 30 MeV deutrons 21988 1 80 En Flux Error Flux Error21988 1 81 MeV n/cm2/sec/MeV % n/cm2/sec/MeV % 21988 1 82 2. 11305. 15.8 10010. 2321988 1 83 3. 8799. 10.6 7044. 1221988 1 84 4. 5872. 10.0 4482. 1021988 1 85 5. 4127. 11.6 3178. 1221988 1 86 6. 4116. 14.3 2711. 1221988 1 87 7. 4836. 10.7 3444. 1121988 1 88 8. 5177. 8.5 4191. 1121988 1 89 9. 5160. 9.4 4579. 821988 1 90 10. 5171. 7.9 4867. 621988 1 91 11. 5147. 7.8 5118. 821988 1 92 12. 4951. 6.5 5141. 821988 1 93 13. 4565. 5.9 5106. 521988 1 94 14. 4041. 4.8 4825. 421988 1 95 15. 3652. 5.3 4355. 421988 1 96 16. 3346. 6.3 3978. 521988 1 97 17. 3074. 7.3 3640. 621988 1 98 18. 2794. 8.1 3334. 721988 1 99 19. 2514. 6.9 3054. 721988 1 100 20. 2238. 5.3 2790. 721988 1 101 21. 1963. 7.3 2547. 621988 1 102 22. 1682. 11.0 2303. 821988 1 103 23. 1414. 13.0 2041. 1021988 1 104 24. 1141. 11.0 1780. 921988 1 105 25. 887. 6.3 1521. 621988 1 106 26. 651. 4.7 1264. 421988 1 107 27. 441. 6.7 1021. 421988 1 108 28. 330. 8.7 787. 721988 1 109 29. 314. 10.0 556. 821988 1 110 30. 312. 10.6 332. 1021988 1 111 SAMPLE The aluminum sample (99.999% purity ) consisted of 21988 1 112 two parts, each 1 x 1 x 0.5 cm thick, between which 21988 1 113 a set of 12 flux monitor foils was inserted. 21988 1 114 METHOD (ACTIV) Irradiation were done for 5 to 20 hr. 21988 1 115 Tritium activities induced in Al samples were separated21988 1 116 after addition of H2 carrier by vacuum extraction at 21988 1 117 900 degC and were counted in a proportional gas 21988 1 118 counting tybe in an anticoincidence arrangement . 21988 1 119 DETECTOR (PROPC,GELI) 21988 1 120 ANALYSIS The shapes of the neutron spectra were determined by 21988 1 121 spectrum unfolding, using the known excitation 21988 1 122 functions of the monitor nuclides and their measured 21988 1 123 activities. In a second calculational step, the 21988 1 124 excitation function for the triton emission process 21988 1 125 on Al-27 was obtained from the neutron flux 21988 1 126 distributions and the measured tritium activities. 21988 1 127 At both calculational stages of iterative code 21988 1 128 SAND-II and the generalized least-squares (LSQ) 21988 1 129 unfolding code were applied, the latter yielding 21988 1 130 additionally the error covariance matrix. 21988 1 131 For input and output unfolding codes scheme see 21988 1 132 Table VII of NSE,91,162,1985 . 21988 1 133 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 11 21988 1 134 Max.response region 1.5 - 11.5 MeV 21988 1 135 (28-NI-58(N,P)27-CO-58-G,,SIG) 12 21988 1 136 Max.response region 3.7 - 15.3 MeV 21988 1 137 (26-FE-54(N,P)25-MN-54,,SIG) 13 21988 1 138 Max.response region 3.7 - 15.9 MeV 21988 1 139 (13-AL-27(N,A)11-NA-24-G,,SIG) 14 21988 1 140 Max.response region 8.9 - 17.8 MeV 21988 1 141 (29-CU-65(N,P)28-NI-65,,SIG) 15 21988 1 142 Max.response region 8.4 - 25.2 MeV 21988 1 143 (79-AU-197(N,2N)79-AU-196-G,,SIG) 16 21988 1 144 Max.response region 10.1 - 20.0 MeV 21988 1 145 (22-TI-48(N,P)21-SC-48,,SIG) 17 21988 1 146 Max.response region 10.3 - 23.0 MeV 21988 1 147 (27-CO-59(N,2N)27-CO-58-G,,SIG) 18 21988 1 148 Max.response region 12.6 - 27.4 MeV 21988 1 149 (39-Y-89(N,2N)39-Y-88-G,,SIG) 19 21988 1 150 Max.response region 13.6 - 27.5 MeV 21988 1 151 (40-ZR-90(N,2N)40-ZR-89-G,,SIG) 20 21988 1 152 Max.response region 14.2 - 29.3 MeV 21988 1 153 (47-AG-107(N,3N)47-AG-105-G,,SIG) 21 21988 1 154 Max.response region >22.5 - >30.0 MeV 21988 1 155 (39-Y-89(N,3N)39-Y-87-G,,SIG) 22 21988 1 156 Max.response region >27.0 - >30.0 MeV . 21988 1 157 Max.response region - region where 21988 1 158 SIG(E) > or = 0.5*SIGmaximal . 21988 1 159 Threshold monitor reactions were used for neutron 21988 1 160 spectrum unfolding. 21988 1 161 DECAY-MON (49-IN-115-M,,DG,336.,0.459) 11 21988 1 162 (27-CO-58-G,,DG,811.,0.9945) 12 21988 1 163 (25-MN-54,,DG,835.,0.9998) 13 21988 1 164 (11-NA-24-G,,DG,1369.,0.9999) 14 21988 1 165 (28-NI-65,,DG,1482.,0.235) 15 21988 1 166 (79-AU-196-G,,DG,356.,0.8761) 16 21988 1 167 (21-SC-48,,DG,1312.,1.00) 17 21988 1 168 (27-CO-58-G,,DG,811.,0.9945) 18 21988 1 169 (39-Y-88-G,,DG,898.,0.937) 19 21988 1 170 (40-ZR-89-G,,DG,909.,0.9901) 20 21988 1 171 (47-AG-105-G,,DG,345.,0.425) 21 21988 1 172 (39-Y-87-G,,DG,485.,0.921) 22 21988 1 173 MONIT-REF (,B.P.Bayhurst+,J,PR/C,12,451,1975) 21988 1 174 for MONITOR 14,16,19,20,21,22 21988 1 175 (,,3,ENDF/B-V,,1979) Dosimetry file . 21988 1 176 for MONITOR 11,12,13,17,18 21988 1 177 (,S.Tagesen+,B,PH-DAT,13-1,1981) 21988 1 178 Physics Data 13-1, Fachinformation zentrum Karlsruhe, 21988 1 179 also 21988 1 180 (,H.Vonach+,R,IAEA-227,59,1983) Techn.Rep.Ser. 21988 1 181 for MONITOR 14 21988 1 182 (,D.C.Santry+,J,CJP,44,1183,1966) 21988 1 183 for MONITOR 15 21988 1 184 CORRECTION .For monitor foils corrections for pile-up effects, 21988 1 185 coincidence losses, self-absorption, etc., were 21988 1 186 applied. 21988 1 187 ERR-ANALYS Error component of measured tritium activities : 21988 1 188 ------------------------------------------------------21988 1 189 Origin of error component Partial error,% Correlation21988 1 190 ------------------------------------------------------21988 1 191 -Statistics of sample counting 0.26 - 3.62 21988 1 192 -Statistics of calibration 1. + 21988 1 193 standard counting 21988 1 194 -Plateau uncertainty of 1.5 21988 1 195 sample counting 21988 1 196 -Plateau uncertainty of 1.5 + 21988 1 197 calibration standard counting 21988 1 198 -Uncertainty of chemical 1.5 21988 1 199 yield of sample 21988 1 200 -Disintegration rate uncertainty 3. + 21988 1 201 of calibration standard 21988 1 202 -Irradiation geometry 2.5 21988 1 203 uncertainty, ect. 21988 1 204 Typical Error components of 12 measured Monitor 21988 1 205 activities : 21988 1 206 ------------------------------------------------------21988 1 207 Origin of error component Partial error,% Correlation21988 1 208 ------------------------------------------------------21988 1 209 -Statistics of monitor counting 0.58-2.37 21988 1 210 -Statistics of calibration 1. 21988 1 211 standard counting 21988 1 212 -Pile-up correction uncertainty 0-0.37 21988 1 213 for monitor 21988 1 214 -Pile-up correction uncertainty 0.28-2.17 + 21988 1 215 for calibration standard 21988 1 216 -Coincidence losses correction 0-4.45 + 21988 1 217 uncertainty for monitor 21988 1 218 -Coincidence losses correction 0-3.51 + 21988 1 219 uncertainty for calibr.standard 21988 1 220 -Gamma-abundance uncertainty 0-1.7 21988 1 221 for monitor 21988 1 222 -Gamma-abundance uncertainty 0-1.1 + 21988 1 223 for calibration standard 21988 1 224 -Half-life uncertainty 0-1.34 21988 1 225 for monitor 21988 1 226 -Half-life uncertainty 0-2.24 + 21988 1 227 for calibration standard 21988 1 228 -Disintegration rate uncertainty 0.5-2.5 + 21988 1 229 for calibration standard 21988 1 230 -Irradiation geometry 2. 21988 1 231 deviation etc. 21988 1 232 -------------------------------------------------------21988 1 233 Scale error of the neutron energy was estimated 2-5 % 21988 1 234 and not included in error calculations. 21988 1 235 (DATA-ERR) Uncertainties given by a code used for 21988 1 236 unfolding. 21988 1 237 COVARIANCE Activities errors relative covariance matrix in 21988 1 238 percent squared after irradiations in six different 21988 1 239 neutron fields ( see six spectra in INC-SOURCE) 21988 1 240 ------------------------------------------------------21988 1 241 1 25.4 21988 1 242 2 12.3 36.1 21988 1 243 3 12.3 12.3 25.2 21988 1 244 4 12.3 12.3 12.3 23.1 (symmetric) 21988 1 245 5 12.3 12.3 12.3 12.3 23.4 21988 1 246 6 12.3 12.3 12.3 12.3 12.3 23.0 21988 1 247 1 2 3 4 5 6 21988 1 248 ------------------------------------------------------21988 1 249 .Relative error correlation matrix for the Al-27((n,t) 21988 1 250 +(n,t+n)) excitation function results(LSQ-2) 21988 1 251 ------------------------------------------------------21988 1 252 EN(MeV) 11 12 13 14 15 16 17 18 21988 1 253 11 1 21988 1 254 12 0.50 1 21988 1 255 13 0. 0.49 1 (Symmetric) 21988 1 256 14 -0.01 -0.02 0.49 1 21988 1 257 15 -0.01 -0.02 -0.04 0.48 1 21988 1 258 16 -0.01 -0.02 -0.04 -0.05 0.47 1 21988 1 259 17 -0.01 -0.03 -0.04 -0.05 -0.06 0.49 1 21988 1 260 18 -0.01 -0.02 -0.04 -0.05 -0.06 -0.06 0.45 1 21988 1 261 19 -0.01 -0.02 -0.03 -0.04 -0.04 -0.05 -0.05 0.4921988 1 262 20 0 -0.01 -0.03 -0.03 -0.04 -0.04 -0.04 -0.0421988 1 263 21 0 -0.01 -0.02 -0.03 -0.04 -0.04 -0.04 -0.0421988 1 264 22 0 -0.01 -0.02 -0.03 -0.03 -0.04 -0.04 -0.0421988 1 265 23 0 -0.01 -0.02 -0.02 -0.03 -0.03 -0.03 -0.0321988 1 266 24 0 0 -0.01 -0.02 -0.02 -0.02 -0.02 -0.0221988 1 267 25 0 0 -0.01 -0.01 -0.01 -0.02 -0.02 -0.0221988 1 268 26 0 0 0 -0.01 -0.01 -0.01 -0.01 -0.0221988 1 269 27 0 0 0 -0.01 -0.01 -0.01 -0.01 -0.0121988 1 270 28 0 0 0 0 -0.01 -0.01 -0.01 -0.0121988 1 271 29 0 0 0 0 0 0 0 -0.0121988 1 272 30 0 0 0 0 0 0 0 0 21988 1 273 EN(MeV) 19 20 21 22 23 24 25 26 21988 1 274 19 1 21988 1 275 20 0.48 1 21988 1 276 21 -0.04 0.48 1 21988 1 277 22 -0.04 -0.05 0.47 1 21988 1 278 23 -0.03 -0.04 -0.06 0.46 1 21988 1 279 24 -0.03 -0.04 -0.06 -0.08 0.45 1 21988 1 280 25 -0.03 -0.04 -0.06 -0.08 -0.09 0.44 1 21988 1 281 26 -0.02 -0.03 -0.05 -0.07 -0.08 -0.09 0.46 1 21988 1 282 27 -0.02 -0.03 -0.04 -0.05 -0.06 -0.07 -0.07 0.4721988 1 283 28 -0.01 -0.02 -0.03 -0.03 -0.04 -0.04 -0.05 -0.0421988 1 284 29 -0.01 -0.01 -0.02 -0.02 -0.02 -0.03 -0.03 -0.0221988 1 285 30 0 -0.01 -0.01 -0.01 -0.01 -0.01 -0.01 -0.0121988 1 286 EN(MeV) 27 28 29 30 21988 1 287 27 1 21988 1 288 28 0.48 1 21988 1 289 29 -0.02 0.49 1 21988 1 290 30 -0.01 -0.01 0.50 1 21988 1 291 ------------------------------------------------------21988 1 292 Relative covariance matrix(symmetric, in percent 21988 1 293 squared) of 12 measured Monitor activities for 21988 1 294 irradiation with 20-MeV neutrons - Table II of 21988 1 295 NSE,91,162,1985 : 21988 1 296 1 2 3 4 5 6 7 8 9 10 21988 1 297 1 18.4 21988 1 298 2 0. 9.60 21988 1 299 3 0. 3.84 12.2 21988 1 300 4 0. 0. 0. 12.8 21988 1 301 5 0. 0. 0. 0. 28.0 21988 1 302 6 12.1 0. 0. 0. 0. 21.5 21988 1 303 7 0. 0. 0. 4.03 0. 0. 30.3 21988 1 304 8 0. 4.22 3.84 0. 0. 0. 0. 9.76 21988 1 305 9 0. 0. 0. 0. 0. 0. 0. 0. 20.0 21988 1 306 10 0. 0. 0. 0. 0. 0. 0. 0. 12.7 19.1 21988 1 307 11 12.1 0. 0. 0. 0. 12.1 0. 0. 0. 0. 21988 1 308 12 0. 0. 0. 0. 0. 0. 0. 0. 0. 0. 21988 1 309 continued: 21988 1 310 11 12 21988 1 311 11 26.7 21988 1 312 12 0. 17.3 21988 1 313 HISTORY (19860127C) 21988 1 314 (19860210E) 21988 1 315 (19860417A) 21988 1 316 (19860703E) 21988 1 317 (20170206A) M.M. INC-SPECT,DECAY-MON,MONIT-REF were 21988 1 318 added. 21988 1 319 Article was checked, BIB information was updated in 21988 1 320 TITLE, STATUS, MONITOR, ERR-ANALYS, COVARIANCE. 21988 1 321 Upper -> lower case correction. 21988 1 322 Dates were corrected for 4-digits year. 21988 1 323 ENDBIB 321 0 21988 1 324 NOCOMMON 0 0 21988 1 325 ENDSUBENT 324 0 21988 199999 SUBENT 21988002 20170206 225921988 2 1 BIB 3 8 21988 2 2 REACTION 1(13-AL-27(N,X)1-H-3,,SIG,,,DERIV) SAND-II 21988 2 3 2(13-AL-27(N,X)1-H-3,,SIG,,,DERIV) LSQ-1 21988 2 4 3(13-AL-27(N,X)1-H-3,,SIG,,,DERIV) LSQ-2 21988 2 5 STATUS (TABLE) Table V of NSE,91,162,1985 21988 2 6 HISTORY (19860127C) 21988 2 7 (19860210E) 21988 2 8 (19860417A) 21988 2 9 (19860703E) 21988 2 10 ENDBIB 8 0 21988 2 11 NOCOMMON 0 0 21988 2 12 DATA 7 39 21988 2 13 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 321988 2 14 DATA-ERR 3 21988 2 15 MEV MB PER-CENT MB PER-CENT MB 21988 2 16 PER-CENT 21988 2 17 1.1000E+01 0.0000E+00 1.0000E+01 0.0000E+00 1.9900E+01 1.0000E-0221988 2 18 1.0300E+01 21988 2 19 1.1500E+01 1.9000E-01 9.5000E+00 1.9000E-01 1.9900E+01 21988 2 20 21988 2 21 1.2000E+01 4.1000E-01 8.0000E+00 4.1000E-01 1.9900E+01 3.1000E-0121988 2 22 8.1000E+00 21988 2 23 1.2500E+01 6.4000E-01 6.8000E+00 6.4000E-01 1.9900E+01 21988 2 24 21988 2 25 1.3000E+01 8.8000E-01 6.8000E+00 8.8000E-01 1.9900E+01 9.0000E-0121988 2 26 6.9000E+00 21988 2 27 1.3500E+01 1.1300E+00 7.0000E+00 1.1300E+00 1.9900E+01 21988 2 28 21988 2 29 1.4000E+01 1.3900E+00 6.2000E+00 1.3900E+00 1.9800E+01 1.4100E+0021988 2 30 6.4000E+00 21988 2 31 1.4500E+01 1.6400E+00 6.0000E+00 1.6400E+00 1.9800E+01 21988 2 32 21988 2 33 1.5000E+01 1.9000E+00 5.3000E+00 1.9000E+00 1.9700E+01 1.9300E+0021988 2 34 5.5000E+00 21988 2 35 1.5500E+01 2.1700E+00 5.2000E+00 2.1700E+00 1.9700E+01 21988 2 36 21988 2 37 1.6000E+01 2.4600E+00 5.3000E+00 2.4700E+00 1.9600E+01 2.5100E+0021988 2 38 5.3000E+00 21988 2 39 1.6500E+01 2.7700E+00 5.3000E+00 2.7800E+00 1.9600E+01 21988 2 40 21988 2 41 1.7000E+01 3.1200E+00 5.2000E+00 3.1300E+00 1.9600E+01 3.1900E+0021988 2 42 5.0000E+00 21988 2 43 1.7500E+01 3.5100E+00 4.5000E+00 3.5200E+00 1.9500E+01 21988 2 44 21988 2 45 1.8000E+01 3.9400E+00 5.5000E+00 3.9600E+00 1.9400E+01 4.0300E+0021988 2 46 4.8000E+00 21988 2 47 1.8500E+01 4.4600E+00 4.3000E+00 4.4800E+00 1.9400E+01 21988 2 48 21988 2 49 1.9000E+01 4.8100E+00 3.5000E+00 4.8200E+00 1.9500E+01 4.9000E+0021988 2 50 3.5000E+00 21988 2 51 1.9500E+01 5.2600E+00 2.7000E+00 5.2700E+00 1.9500E+01 21988 2 52 21988 2 53 2.0000E+01 5.6600E+00 4.3000E+00 5.6800E+00 1.9500E+01 5.7500E+0021988 2 54 3.8000E+00 21988 2 55 2.0500E+01 5.8100E+00 4.5000E+00 5.8100E+00 1.9600E+00 21988 2 56 21988 2 57 2.1000E+01 5.9800E+00 5.5000E+00 5.9800E+00 1.9700E+01 6.0300E+0021988 2 58 5.5000E+00 21988 2 59 2.1500E+01 6.1800E+00 6.6000E+00 6.1700E+00 1.9700E+01 21988 2 60 21988 2 61 2.2000E+01 6.4300E+00 5.9000E+00 6.4200E+00 1.9800E+01 6.4500E+0021988 2 62 7.1000E+00 21988 2 63 2.2500E+01 6.8300E+00 8.7000E+00 6.8300E+00 1.9800E+01 21988 2 64 21988 2 65 2.3000E+01 7.0600E+00 7.2000E+00 7.0600E+00 1.9800E+01 7.0800E+0021988 2 66 7.9000E+00 21988 2 67 2.3500E+01 7.2800E+00 7.8000E+00 7.2800E+00 1.9800E+01 21988 2 68 21988 2 69 2.4000E+01 7.7900E+00 8.5000E+00 7.8100E+00 1.9800E+01 7.8100E+0021988 2 70 9.1000E+00 21988 2 71 2.4500E+01 7.9800E+00 1.1000E+01 8.0000E+00 1.9800E+00 21988 2 72 21988 2 73 2.5000E+01 8.1500E+00 1.2000E+01 8.1700E+00 1.9900E+01 8.1200E+0021988 2 74 1.1700E+01 21988 2 75 2.5500E+01 8.2700E+00 1.2100E+01 8.3000E+00 1.9900E+01 21988 2 76 21988 2 77 2.6000E+01 8.2800E+00 1.2600E+01 8.3000E+00 1.9900E+01 8.3000E+0021988 2 78 1.2400E+01 21988 2 79 2.6500E+01 8.1300E+00 1.2500E+01 8.1600E+00 1.9900E+01 21988 2 80 21988 2 81 2.7000E+01 7.8500E+00 1.2000E+01 7.8800E+00 1.9900E+01 7.9400E+0021988 2 82 1.2200E+01 21988 2 83 2.7500E+01 7.3200E+00 1.2000E+01 7.3500E+00 1.9900E+01 21988 2 84 21988 2 85 2.8000E+01 6.8000E+00 1.1900E+01 6.8300E+00 1.9900E+01 6.9000E+0021988 2 86 1.1500E+01 21988 2 87 2.8500E+01 6.0200E+00 1.0600E+01 6.0400E+00 1.9900E+01 21988 2 88 21988 2 89 2.9000E+01 5.2200E+00 1.0400E+01 5.2400E+00 1.9900E+01 5.3000E+0021988 2 90 1.0500E+01 21988 2 91 2.9500E+01 4.5300E+00 1.0500E+01 4.5500E+00 1.9900E+01 21988 2 92 21988 2 93 3.0000E+01 3.7600E+00 1.2900E+01 3.7800E+00 1.9900E+01 3.8200E+0021988 2 94 1.2100E+01 21988 2 95 ENDDATA 82 0 21988 2 96 ENDSUBENT 95 0 21988 299999 ENDENTRY 2 0 2198899999999