JENDL-5 (Neutron sublibrary (activation cs)) B - 10 0 0 0 0 5.010000+3 9.926920+0 0 0 6 1 525 1451 1 0.000000+0 0.000000+0 0 0 0 6 525 1451 2 1.000000+0 2.000000+7 0 0 10 5 525 1451 3 2.936000+2 0.000000+0 4 0 367 16 525 1451 4 5-B - 10 JAERI EVAL-MAR87 S.CHIBA 525 1451 5 DIST-DEC21 20101004 525 1451 6 ----JENDL-5 MATERIAL 525 525 1451 7 -----INCIDENT NEUTRON DATA 525 1451 8 ------ENDF-6 FORMAT 525 1451 9 525 1451 10 HISTORY 525 1451 11 87-03 Newly evaluated by S.Chiba (jaeri) for JENDL-3. 525 1451 12 88-11 Data for mf=3(mt=1,2,3,4,51,103,107,113,800,801) were 525 1451 13 modified. data for mf=12(mt=102,801), mf=13(mt=4,103), 525 1451 14 mf=14(mt=4,102,103,801) were added. Comment was also 525 1451 15 modified. 525 1451 16 02-01 Compiled by K.Shibata for JENDL-3.3. 525 1451 17 09-02 (n,t) reaction was modified by S. Chiba. 525 1451 18 09-03 Compiled by S. Chiba for JENDL-4. 525 1451 19 525 1451 20 ******** modifications for JENDL-3.3 ********************* 525 1451 21 (1,451) Updated. 525 1451 22 (3,251) Deleted. 525 1451 23 (4,2) Transformation matrix deleted. 525 1451 24 (12,801) Eg and Es were corrected. 525 1451 25 (33,1-801) Taken from JENDL-3.2 covariance file. 525 1451 26 ************************************************************ 525 1451 27 525 1451 28 10-09 Re-compiled by S. Chiba 525 1451 29 Total, non-elastic and elastic cross sections were 525 1451 30 re-calculated in order to remove the strange oscillations 525 1451 31 which had been observed in the elastic cross sections 525 1451 32 contained in JENDL-4.0. 525 1451 33 21-11 revised by O.Iwamoto 525 1451 34 (MF8/MT16,102-105,107) JENDL/AD-2017 adopted 525 1451 35 (MF8/MT4,113) added 525 1451 36 21-12 (MF3,8/MT113) modified by O.Iwamoto 525 1451 37 MT113(n,t2a) -> MT105 (n,t) to avoid no residual 525 1451 38 525 1451 39 525 1451 40 mf=1 General information 525 1451 41 mt=451 Descriptive data and dictionary 525 1451 42 525 1451 43 mf=2 Resonance parameters 525 1451 44 mt=151 Scattering radius only. 525 1451 45 The 2200m/s and 14 MeV cross sections are in 525 1451 46 Table 1. 525 1451 47 525 1451 48 Thermal cross sections and resonance integrals at 300 K 525 1451 49 ---------------------------------------------------------- 525 1451 50 0.0253 eV res. integ. (*) 525 1451 51 (barns) (barns) 525 1451 52 ---------------------------------------------------------- 525 1451 53 Total 3.8408E+03 525 1451 54 Elastic 2.2543E+00 525 1451 55 n,gamma 5.0005E-01 2.2510E-01 525 1451 56 n,p 3.0003E-03 525 1451 57 n,alpha 3.8373E+03 525 1451 58 n,t2alpha 8.0298E-03 525 1451 59 ---------------------------------------------------------- 525 1451 60 (*) Integrated from 0.5 eV to 10 MeV. 525 1451 61 525 1451 62 mf=3 Neutron cross sections 525 1451 63 mt=1 Total 525 1451 64 Below 1.2 MeV, sum of the partial cross sections. 525 1451 65 1.2 to 17 MeV, based on the experimental data /1/-/9/. 525 1451 66 Above 17MeV, optical model calculation was normalized at 525 1451 67 17 MeV. The spherical optical potential parameters/10/ 525 1451 68 are listed in Table 2. 525 1451 69 mt=2 Elastic scattering 525 1451 70 Below 10 keV, based on the R-matrix calculation. The 525 1451 71 R-matrix parameters are mainly based on ref./11/. 525 1451 72 10 keV to 1.2 MeV, based on the experimental data /12/- 525 1451 73 /14/. 525 1451 74 Above 1.2 MeV, calculated by subtracting all the other 525 1451 75 partial cross sections from the total cross section. 525 1451 76 mt=3 Non-elastic 525 1451 77 Sum of mt=4, 16, 102, 103, 104, 107 and 105. 525 1451 78 mt=4 Total inelastic 525 1451 79 Sum of mt=51 to 89. 525 1451 80 mt=16 (n,2n) 525 1451 81 Based on the experimental data /15/. Cross section was 525 1451 82 extrapolated as 0.0120*sqrt(E-Eth), where E is incident 525 1451 83 neutron energy and Eth threshold energy in MeV. Note 525 1451 84 that this reaction produces 1 proton and 2 alpha 525 1451 85 particles, i.e. (n,2np)2alpha. 525 1451 86 mt=51-59, 61, 62, 64-66. Inelastic scattering to real levels 525 1451 87 Cross sections were calculated by the collective model 525 1451 88 DWBA and normalized to the experimental data/16/ at 14 525 1451 89 MeV. Calculated levels and assumed orbital angular 525 1451 90 momentum transfers (l) are summarized in table 3. 525 1451 91 data for mt=51 was normalized to the experimental 525 1451 92 data/17/ below 6MeV. Above 6MeV, the deformation 525 1451 93 parameter deduced from (p,p') reaction/18/ was used. 525 1451 94 mt=60,63,67-89 (n,n'd)2alpha continuum. 525 1451 95 Represented by pseudo-levels, binned in 0.5 MeV intervals. 525 1451 96 The (n,n'd)2alpha cross section was based on the 525 1451 97 measurement of Frye+ /19/. The cross section for each 525 1451 98 level was calculated by the 3-body phase space 525 1451 99 distribution, assuming isotropic center-of-mass 525 1451 100 angular distributions. 525 1451 101 mt=102 Capture 525 1451 102 1/v shape was normalized to the experimental data /20/. 525 1451 103 mt=103 (n,p) 525 1451 104 Sum of mt = 700 to 705. 525 1451 105 mt=104 (n,d) 525 1451 106 Sum of mt = 720 and 721. 525 1451 107 mt=107 (n,alpha) 525 1451 108 Sum of mt = 800 and 801. The thermal cross section of 525 1451 109 3837 barns was adopted/21/. 525 1451 110 mt=105 (n,t)2alpha 525 1451 111 Based on the experimental data /19/,/22/-/29/. 525 1451 112 Feb. 2009 525 1451 113 Modified by taking account of the resonant structure at 525 1451 114 the threshold region. The trion widths were calculated 525 1451 115 by the analytical continuation method (N. Itagaki), which 525 1451 116 yielded Gamma_t = 22 keV for 370 keV and 30 keV for 525 1451 117 1890 keV resonance (L=2). The WKB penetration factor 525 1451 118 was applied to hinder the cross section for the first 525 1451 119 resonance. The thermal cross section was also slightly 525 1451 120 modified to take account of the recent experimental data 525 1451 121 (Kornilov et al., YK,(1),11,9004, EXFOR41053002 and 5). 525 1451 122 mt=600 (n,p) to the ground state of Be-10. 525 1451 123 Below 100 keV, assumed to be 1/v. the thermal cross 525 1451 124 section was assumed to be 3mb/30/. 525 1451 125 From 100 keV to 500 keV, assumed to be constant. 525 1451 126 From 500 keV to 1 MeV, linearly interpolated. 525 1451 127 Above 1 MeV, the statistical model calculation was 525 1451 128 normalized by a factor of 0.704. The optical potential, 525 1451 129 level schemes and level density parameters used in the 525 1451 130 calculation are summarized in Tables 2, 3 and 4. 525 1451 131 mt=601-605 (n,p) to the low lying excited states of Be-10. 525 1451 132 The statistical model calculation was normalized to the 525 1451 133 experimental data/26/ at 14 MeV. 525 1451 134 mt=650 (n,d0) 525 1451 135 Below 7.6 MeV, the inverse reaction cross sections/31/- 525 1451 136 /32/ were converted by the principle of detailed 525 1451 137 balance. 525 1451 138 From 7.6 to 14 MeV, interpolated linearly. 525 1451 139 Above 14 MeV, DWBA calculation with the proton pickup 525 1451 140 mechanism was normalized to the experimental data, 525 1451 141 /33/-/34/ at 14 MeV. The d + Be-9 and bound proton 525 1451 142 potentials of Valkovic+/34/ were used. Depth of the 525 1451 143 proton potential was searched by the separation energy 525 1451 144 method. the potential parameters are listed in Table 2. 525 1451 145 mt=651 (n,d2) 525 1451 146 DWBA calculation with the proton pickup mechanism was 525 1451 147 normalized to the experimental data/26/,/33/-/34/ at 14 525 1451 148 MeV. This is really the (n,d) reaction to the second 525 1451 149 level of Be-9. 525 1451 150 mt=800, (n,alpha0) 525 1451 151 Below 10 keV, R-matrix calculation. 525 1451 152 From 10 keV to 800 keV, based on the experimental data 525 1451 153 /35/-/36/. 525 1451 154 From 800 keV to 7.5 MeV, the experimental data/37/ were 525 1451 155 normalized by a factor of 1.38 and fitted by the spline 525 1451 156 function. 525 1451 157 Above 7 MeV, the experimental data/26/ were adopted. 525 1451 158 mt=801 (n,alpha1) 525 1451 159 Below 10 keV, the R-matrix calculation. 525 1451 160 From 10 keV to 100 keV, based on the experimental data/36/ 525 1451 161 /38/. 525 1451 162 From 100 keV to 2 MeV, recommendation by Liskien and 525 1451 163 Wattecamps/39/ was adopted. 525 1451 164 From 2 to 7.5 MeV, the experimental data/37-40/ were 525 1451 165 normalized by a factor of 1.38 and fitted by the spline 525 1451 166 function. 525 1451 167 Above 7 MeV, the experimental data/40/ was adopted. 525 1451 168 525 1451 169 mf=4 angular distributions of secondary neutrons 525 1451 170 mt=2 525 1451 171 Below 100 keV, the R-matrix calculation. 525 1451 172 From 100 keV to 6 MeV, ENDF/B-V was adopted. 525 1451 173 Above 6 MeV, based on the optical model calculation. 525 1451 174 mt=16 525 1451 175 Calculated by the method of Nakagawa/41/. 525 1451 176 Angular distributions are given in the laboratory system. 525 1451 177 mt=51-59, 61, 62, 64-66. 525 1451 178 DWBA calculation. 525 1451 179 mt=60, 63, 67-89 525 1451 180 Assumed to be isotropic in cm. 525 1451 181 525 1451 182 mf=5 Energy distribution of secondary neutrons 525 1451 183 mt=16 525 1451 184 The evaporation model was assumed. the evaporation 525 1451 185 temperature was assumed to be 1 MeV at 14 MeV. it was 525 1451 186 extrapolated as 525 1451 187 t = 0.2673*sqrt(En) MeV, 525 1451 188 where En means the incident neutron energy in the 525 1451 189 laboratory system in MeV. 525 1451 190 525 1451 191 mf=12 Photon multiplicities 525 1451 192 mt=102 525 1451 193 Multiplicities were given according to a compilation of 525 1451 194 Ajzenberg et al./43/. However, they were normalized 525 1451 195 for the total secondary gamma-ray energy to match the 525 1451 196 available energy in the final state. 525 1451 197 mt=801 525 1451 198 Multiplicity for the 0.479-MeV gamma-ray was given as 525 1451 199 1.0. 525 1451 200 525 1451 201 mf=13 Photon production cross sections 525 1451 202 mt=4 525 1451 203 Experimental data/41,44/ were adopted for 0.4138-, 525 1451 204 0.7183- and 1.0219-MeV gamma-rays. For 1.44- and 525 1451 205 2.15-MeV gamma-rays, excitation function of the 525 1451 206 0.4138-MeV gamma-ray production was normalized to the 525 1451 207 data/41/ at 14.8MeV. For 2.87-, 3.01-, 4.44- and 525 1451 208 6.03-MeV gamma-rays, shapes of the corresponding (n,n') 525 1451 209 excitation functions in mf=3 were normalized to the 525 1451 210 data/41/ at 14.8MeV. 525 1451 211 mt=103 525 1451 212 For 3.368- and 2.592-MeV gamma-rays, shapes of the 525 1451 213 corresponding (n,p) excitation functions in mf=3 525 1451 214 were normalized to the experimental data/41/ at 525 1451 215 14.8MeV. 525 1451 216 525 1451 217 mf=14 Angular distribution of secondary photons 525 1451 218 mt=4,102,103,113, 801 525 1451 219 Assumed to be isotropic. 525 1451 220 525 1451 221 mf=33 Covariances of cross sections (ref. 46) 525 1451 222 mt=1 525 1451 223 Below 1.2 MeV, constructed from mt=2, 102, 800 and 801. 525 1451 224 Above 1.2 MeV, based on experimaental data. a chi-value 525 1451 225 was 2.186. 525 1451 226 mt=2 525 1451 227 Below 1.2 MeV, based on experimental data. 525 1451 228 Above 1.2 MeV, constructed from mt=1, 102, 800 and 801. 525 1451 229 525 1451 230 mt=102 525 1451 231 Based on experimental data. 525 1451 232 525 1451 233 mt=107 525 1451 234 Constructed from mt=800 and 801. 525 1451 235 525 1451 236 mt=800 525 1451 237 Based on experimental data. A chi-value was 1.203. 525 1451 238 525 1451 239 mt=801 525 1451 240 Based on experimental data. A chi-value was 1.913. 525 1451 241 525 1451 242 References 525 1451 243 1) Auchampaugh,G.F. et al.: Nucl. Sci. Eng. 69,30(1979). 525 1451 244 2) Cook,C.E. et al.: Phys. Rev. 94, 651(1954). 525 1451 245 3) Tsukada,K.: EXFOR 20324,003(1963). 525 1451 246 4) Coon,J.H. et al.: Phys.Rev. 88, 562(1952). 525 1451 247 5) Fossan,D.B. et al.: Phys.Rev. 123, 209(1961). 525 1451 248 6) Cookson,J.A. et al.: Nucl. Phys. A146, 417(1970). 525 1451 249 7) Nereson,N.G. et al.: LA-1655(1954). 525 1451 250 8) Becker,R.L. et al.: Phys.Rev. 102, 1384(1956). 525 1451 251 9) Bockelman,C.K. et al.: Phys. Rev. 84, 69(1951). 525 1451 252 10) Dave,J.H. et al.: Phys.Rev. C28,2112(1983). 525 1451 253 11) Hausladen,S.L. et al.: Nucl.Phys. A217,563(1973). 525 1451 254 12) Asami,A. et al.: J.Nucl.Energ. 24, 85(1970). 525 1451 255 13) Lane,R.O. et al.: Phys. Rev. C4, 380(1971). 525 1451 256 14) Willard,H.B. et al.: Phys. Rev. 98,669(1958). 525 1451 257 15) Mather,D.S.: AWRE-O-47/69(1969). 525 1451 258 16) Vaucher,B. et al.: Helv. Phys. Acta 43, 237(1970). 525 1451 259 17) Porter D.: AWRE-O-45/70(1970) 525 1451 260 18) Swiniarski, R.D. et al.: Helv. Phys. Acta 49, 227(1976). 525 1451 261 19) Frye,G.M. et al.: Phys.Rev. 103, 328(1956). 525 1451 262 20) Batholomew,G.A. et al.: Can.J.Phys. 35, 1347(1957). 525 1451 263 21) Mughabghab,S.F. et al.: 'Neutron Cross Sections', Vol.1 Part 525 1451 264 A (Academic Press 1981, New York) 525 1451 265 22) Wyman,M.E. et al.: Phys.Rev. 112, 1264(1958). 525 1451 266 23) Klein,P.D. et al.: EXFOR 12654,002(1966). 525 1451 267 24) Antolkovic,B. et al.: Nucl.Phys. A139, 10(1969). 525 1451 268 25) Valkovic,V. et al: Nucl.Phys. A98, 305(1967). 525 1451 269 26) Sellem,C. et al.: Nucl.Instrum.Meth. 128, 495(1975). 525 1451 270 27) Cserpak,F. et al.: EXFOR 30474,003(1978). 525 1451 271 28) Suhaimi,A. et al.: Radiochimica Acta 40, 113(1986). 525 1451 272 29) Qaim,S.M. et al.: Proc. Int. Conf. Nucl. Data for Sci. and 525 1451 273 Technol., Mito, May 30 - June 3, 1988. 525 1451 274 30) Eggler,et al. : In CINDA-A (1935-1976) Vol.1 (1979) 525 1451 275 31) Bardes,R. et al.: Phys.Rev. 120, 1369(1960). 525 1451 276 32) Siemssen,R.H. et al.: Nucl.Phys. 69, 209(1965). 525 1451 277 33) Ribe,F.L. et al.: Phys.Rev. 94, 934(1954). 525 1451 278 34) Valkovic,V. et al.: Phys.Rev. 139, B331(1965). 525 1451 279 35) Olson,M.D. et al.: Phys.Rev. C30, 1375(1984). 525 1451 280 36) Sealock,R.M. et al.: Phys.Rev. C13, 2149(1976). 525 1451 281 37) Davis,E.A. et al.: Nucl.Phys. 27, 448(1961). 525 1451 282 38) Schrack,R.A. et al.: Nucl.Sci.Eng. 68, 189(1978). 525 1451 283 39) Liskien,H. and Wattecamps, E.: Nucl.Sci.Eng. 68, 132(1978). 525 1451 284 40) Viesti,G. et al.: Annals Nucl. Energ. 6, 13(1979). 525 1451 285 41) Nellis R.O.: Phys.Rev. C1, 847(1970). 525 1451 286 42) Nakagawa,T.: JAERI-M 84-103(1984) 525 1451 287 43) Ajzenberg S.: Nucl.Phys. A248, 1(1975). 525 1451 288 44) Dickens et al. : Proc. Int. Conf. Nucl. Data for Sci. 525 1451 289 & Technol., May 30- June 3, 1988, Mito, Japan. 525 1451 290 45) Watson,B.A. et al: Phys. Rev. 182, 977(1969) 525 1451 291 46) Shibata, K, et al.: JAERI-Research 98-045 (1998). 525 1451 292 525 1451 293 Table 1 The 2200-m/s and 14 mev cross sections 525 1451 294 ---------------------------------------------------- 525 1451 295 2200-m/s (b) 14 MeV (b) 525 1451 296 ---------------------------------------------------- 525 1451 297 elastic 2.144 0.943 525 1451 298 (n,n') ----- 0.269 525 1451 299 (n,p) 0.003 0.038 525 1451 300 (n,d) ----- 0.047 525 1451 301 (n,t) 0.012 0.095 525 1451 302 (n,alpha) 3837.0 0.049 525 1451 303 (n,2n) ----- 0.027 525 1451 304 capture 0.50 0.000 525 1451 305 total 3839.7 1.467 525 1451 306 ---------------------------------------------------- 525 1451 307 525 1451 308 Table 2 Optical potential parameters 525 1451 309 ------------------------------------------------------------- 525 1451 310 B-10 + n /10/ 525 1451 311 V= 47.91 - 0.346En, Ws= 0.657 + 0.810En, Vso=5.5 (MeV) 525 1451 312 r= 1.387 , rs= 1.336 , rso=1.15 (fm) 525 1451 313 a= 0.464 , as= 0.278 , aso=0.5 (fm) 525 1451 314 525 1451 315 Be-10 + p /45/ 525 1451 316 V = 60.0 + 27.0(N-Z)/A -0.3Ecm (MeV) 525 1451 317 Ws = 0.64Ecm + 10.0(N-Z)/A ,(Ecm < 13.8 MeV) (MeV) 525 1451 318 = 9.60-0.06Ecm + 10.0(N-Z)/A ,(Ecm > 13.8 MeV) (MeV) 525 1451 319 Vso= 5.5 (MeV) 525 1451 320 r = rs = rso = 1.15 (fm) 525 1451 321 a = aso = 0.57, as= 0.5 (fm) 525 1451 322 525 1451 323 Be-9 + d /34/ 525 1451 324 V= 80.0 , Wv= 30.0 , Vso=6.0 (MeV) 525 1451 325 r= 1.0 , rv= 1.0 , rso=1.0 ,rc= 1.3 (fm) 525 1451 326 a= 1.0 , av= 0.8 , aso=1.0 (fm) 525 1451 327 ------------------------------------------------------------- 525 1451 328 525 1451 329 Table 3 Level schemes used in the DWBA or statistical 525 1451 330 model calculation 525 1451 331 --------------------------------------------------- 525 1451 332 B-10 Be-10 525 1451 333 --------------------------------------------------- 525 1451 334 mt energy Jp L mt energy Jp 525 1451 335 ( MeV ) ( MeV ) 525 1451 336 2 0.0 3+ 700 0.0 0+ 525 1451 337 51 0.7183 1+ 2 701 3.368 2+ 525 1451 338 52 1.7402 0+ 4 702 5.958 2+ 525 1451 339 53 2.154 1+ 2 703 5.960 1- 525 1451 340 54 3.587 2+ 2 704 6.179 0+ 525 1451 341 55 4.774 3+ 2 705 6.263 2- 525 1451 342 56 5.110 2- 3 525 1451 343 57 5.163 2+ 2 525 1451 344 58 5.18 1+ 2 525 1451 345 59 5.920 2+ 2 525 1451 346 61 6.025 4+ 2 525 1451 347 62 6.127 3- 3 525 1451 348 64 6.561 3+ 2 525 1451 349 65 6.881 1- 3 525 1451 350 66 7.00 1+ 2 525 1451 351 7.430 1- 525 1451 352 7.470 1+ 525 1451 353 7.477 2- 525 1451 354 7.560 0+ 525 1451 355 7.670 1+ 525 1451 356 7.840 1- 525 1451 357 8.070 2- 525 1451 358 8.650 1+ 525 1451 359 8.890 3- 525 1451 360 8.894 2+ 525 1451 361 --------------------------------------------------- 525 1451 362 525 1451 363 Table 4 Level density parameters used in the statistical 525 1451 364 model calculation 525 1451 365 ---------------------------------------------------------------- 525 1451 366 a(1/MeV) t(MeV) c(1/MeV) pair.(MeV) Ex(MeV) 525 1451 367 ---------------------------------------------------------------- 525 1451 368 B-10 1.196 5.581 0.066 0.0 16.17 525 1451 369 Be-10 1.088 5.866 0.021 5.13 19.63 525 1451 370 ----------------------------------------------------------------- 525 1451 371 1 451 387 1 525 1451 372 2 151 4 1 525 1451 373 3 4 35 1 525 1451 374 3 16 10 1 525 1451 375 3 102 119 1 525 1451 376 3 103 151 1 525 1451 377 3 104 10 1 525 1451 378 3 105 136 1 525 1451 379 3 107 140 1 525 1451 380 8 4 2 1 525 1451 381 8 16 2 1 525 1451 382 8 102 2 1 525 1451 383 8 103 2 1 525 1451 384 8 104 2 1 525 1451 385 8 105 2 1 525 1451 386 8 107 2 1 525 1451 387 525 1 099999 525 0 0 0 5.010000+3 9.926920+0 0 0 1 0 525 2151 1 5.010000+3 1.000000+0 0 0 1 0 525 2151 2 1.000000-5 1.000000+4 0 0 0 0 525 2151 3 3.000000+0 4.100000-1 0 0 0 0 525 2151 4 525 2 099999 525 0 0 0 5.010000+3 9.926920+0 0 0 0 0 525 3 4 1 0.000000+0-7.182990+5 0 0 1 96 525 3 4 2 96 2 525 3 4 3 7.906600+5 0.000000+0 8.000000+5 1.298900-2 1.000000+6 2.911200-2 525 3 4 4 1.200000+6 5.692500-2 1.400000+6 8.473800-2 1.600000+6 8.548100-2 525 3 4 5 1.800000+6 8.466800-2 1.915500+6 7.989210-2 2.000000+6 7.646470-2 525 3 4 6 2.200000+6 6.639180-2 2.371000+6 6.174260-2 2.400000+6 6.402130-2 525 3 4 7 2.600000+6 8.775700-2 2.800000+6 1.171270-1 3.000000+6 1.211770-1 525 3 4 8 3.200000+6 1.255340-1 3.400000+6 1.257690-1 3.600000+6 1.207700-1 525 3 4 9 3.800000+6 1.133760-1 3.948300+6 1.079540-1 4.000000+6 1.117750-1 525 3 4 10 4.200000+6 1.275120-1 4.400000+6 1.442700-1 4.600000+6 1.618700-1 525 3 4 11 4.800000+6 1.632570-1 4.900000+6 1.632240-1 5.000000+6 1.631900-1 525 3 4 12 5.200000+6 1.577120-1 5.254900+6 1.552320-1 5.600000+6 1.650000-1 525 3 4 13 5.624800+6 1.637470-1 5.683100+6 1.612130-1 5.701800+6 1.619060-1 525 3 4 14 6.000000+6 1.990230-1 6.200000+6 1.840330-1 6.400000+6 1.772420-1 525 3 4 15 6.516400+6 1.748520-1 6.600000+6 1.881260-1 6.604400+6 1.887910-1 525 3 4 16 6.631900+6 1.933420-1 6.744200+6 2.226100-1 6.800000+6 2.415580-1 525 3 4 17 7.000000+6 3.071260-1 7.154800+6 3.175470-1 7.221900+6 3.220650-1 525 3 4 18 7.500000+6 3.504980-1 7.574200+6 3.494470-1 7.705200+6 3.491540-1 525 3 4 19 8.000000+6 3.575970-1 8.255500+6 3.411930-1 8.500000+6 3.254970-1 525 3 4 20 8.805900+6 3.072190-1 9.000000+6 2.956230-1 9.356300+6 2.837030-1 525 3 4 21 9.500000+6 2.788970-1 9.906600+6 2.652960-1 1.000000+7 2.621710-1 525 3 4 22 1.045700+7 2.578110-1 1.050000+7 2.574010-1 1.100000+7 2.526290-1 525 3 4 23 1.100700+7 2.525870-1 1.150000+7 2.493020-1 1.155800+7 2.489130-1 525 3 4 24 1.200000+7 2.459760-1 1.210800+7 2.452700-1 1.250000+7 2.483680-1 525 3 4 25 1.265800+7 2.503320-1 1.300000+7 2.545380-1 1.320900+7 2.574610-1 525 3 4 26 1.350000+7 2.615430-1 1.375900+7 2.651780-1 1.400000+7 2.685480-1 525 3 4 27 1.415000+7 2.663440-1 1.431000+7 2.642780-1 1.450000+7 2.590540-1 525 3 4 28 1.486000+7 2.491660-1 1.500000+7 2.453190-1 1.541000+7 2.353040-1 525 3 4 29 1.550000+7 2.331120-1 1.596100+7 2.218600-1 1.600000+7 2.209040-1 525 3 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