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