IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 25055.0000 54.4661000 0 0 0 12525 1451 1 0.0 0.0 0 0 0 62525 1451 2 1.00000000 60000000.0 0 5 10 72525 1451 3 300.000000 0.0 1 0 299 72525 1451 4 25-Mn- 55 JAERI,ORNL EVAL-MAR88 K.Shibata 2525 1451 5 DIST-DEC06 2525 1451 6 ----ENDF/B-VII MATERIAL 2525 2525 1451 7 -----INCIDENT NEUTRON DATA 2525 1451 8 ------ENDF-6 FORMAT 2525 1451 9 ******************************************************************2525 1451 10 IAEA, July 2011 (A. Trkov) 2525 1451 11 - The capture cross section was taken from the ENDF/B-VII.1 2525 1451 12 library, including the covariance data. The source data are 2525 1451 13 essentially the same as in the Zolotarev original evaluation, 2525 1451 14 except for some small changes in the resonance parameters 2525 1451 15 (see original evaluation for details). 2525 1451 16 - The total cross section is also taken from the ENDF/B-VII.1 2525 1451 17 library for consistency. 2525 1451 18 - The Zolotarev (n,2n) evaluation was extended from 40 to 2525 1451 19 60 MeV using TENDL-2010 data, renormalised for continuity. 2525 1451 20 The covariances above 20 MeV were taken from the same library. 2525 1451 21 ******************************************************************2525 1451 22 2525 1451 23 **************************************************************** 2525 1451 24 * Extension to the International Reactor Dosimetry Library * 2525 1451 25 * supported partially by the International Atomic Energy Agency * 2525 1451 26 * through IAEA research contract 13335. * 2525 1451 27 * Unpublished, received on December 2008. * 2525 1451 28 ***************************************************************** 2525 1451 29 ------Russian Reactor Dosimetry File BEST-17 25138-10 c=0.82 2525 1451 30 ***************************************************************** 2525 1451 31 Authors of evaluation: K.I.Zolotarev and R.Capote 2525 1451 32 ***************************************************************** 2525 1451 33 MF=3 2525 1451 34 MT= 16 - (n,2n) cross section 2525 1451 35 ----------------------------- 2525 1451 36 Microscopic experimental data [1-33] were analyzed in the 2525 1451 37 process of preparation of input data base for the evaluation of 2525 1451 38 cross sections and their uncertainty for the Mn-55(n,2n)Mn-54 2525 1451 39 reaction. During this procedure experimental data of works [1-4],2525 1451 40 [6], [8-12], [14-16], [18-19], [22-24], [29], [32] were corrected 2525 1451 41 to the new standars. 2525 1451 42 Cross sections measured by Filatenkov and Chuvaev in the neut- 2525 1451 43 ron energies interval 14.42-14.78 MeV [24] were used as a referen-2525 1451 44 ce data for correction experimental data from works [3] and [17]. 2525 1451 45 After corrections to the new standards experimental data of Paul- 2525 1451 46 sen and Liskien [3] and Zhao Wenrong et al.[17] were renormalized 2525 1451 47 to a factors of Fc= 0.81319 and Fc= 0.95100, respectively. 2525 1451 48 Neutron energies of 11.14, 11.97 and 12.85 MeV asreported by 2525 1451 49 Bostan and Qaim [22] were shifted by +0.45 MeV. 2525 1451 50 Cross sections measured by Soewarsono et al. over a wide neut- 2525 1451 51 ron energies range 17.55 - 38.50 MeV [20] were renormalized to a 2525 1451 52 value of 820 mb at 17.55 MeV obtained from experimental data of 2525 1451 53 Uwamino et al. [21]. 2525 1451 54 Cross sections that had been determined in Refs. [25-33] were 2525 1451 55 rejected due to their significant discrepancy with the representa-2525 1451 56 tive experimental data. In all of the rejected works only one ex- 2525 1451 57 perimenlal value is given in the energy range of 14 - 15 MeV. 2525 1451 58 Excitation function for the Mn-55(n,2n)Mn-54 reaction in the 2525 1451 59 energy region from threshold to 40 MeV was evaluated by means of 2525 1451 60 statistical analysis of experimental cross section data [1-24] 2525 1451 61 and data obtained from theoretical model calculation carried out 2525 1451 62 by means of modified GNASH code [34]. 2525 1451 63 Statistical analysis of input cross section data was carried 2525 1451 64 out by means of PADE-2 code [35]. Rational function was used as 2525 1451 65 the model function [36]. 2525 1451 66 Evaluated excitation function of the Mn-55(n,2n)Mn-54 reaction 2525 1451 67 was tested by comparison with integral experimental data [37-38] 2525 1451 68 for U-235 thermal fission neutron spectrum and recommended integ- 2525 1451 69 ral experimental data [39] for Cf-252 spontaneous fission neutron 2525 1451 70 spectrum. Calculated and measured average cross section values 2525 1451 71 for U-235 thermal fission neutron spectrum [40] and Cf-252 sponta-2525 1451 72 neous fission neutron spectrum [41] are given in the Table 1. 2525 1451 73 Table 1 2525 1451 74 ----------------------+-----------------+----------------------- 2525 1451 75 Type of spectrum | ,mb (calc.) | , mb (measured) 2525 1451 76 ----------------------+-----------------+----------------------- 2525 1451 77 U-235 neutron fission | 0.20410 | 0.2043 +- 0.0074 [ *] 2525 1451 78 ----------------------+-----------------+----------------------- 2525 1451 79 CF-252 spont. fission | 0.41615 | 0.4075 +- 0.0095 [39] 2525 1451 80 ----------------------+-----------------+----------------------- 2525 1451 81 * -average-weighted value obtained from experimental data [37-38].2525 1451 82 2525 1451 83 MF=33 2525 1451 84 MT= 16 - (n,2n) cross section cov. matrix 2525 1451 85 ----------------------------------------- 2525 1451 86 Uncertainties in the evaluated excitation function for the 2525 1451 87 reaction Mn-55(n,2n)Mn-54 are given in the form of relative cova- 2525 1451 88 riance matrix for the 39-neutron energy groups (LB=5). Covariance 2525 1451 89 matrix of uncertainties was calculated simultaneously with 2525 1451 90 recommended cross section data by means of PADE-2 code [35]. 2525 1451 91 Eigenvalues of the 6-th digits relative covariance matrix 2525 1451 92 given in the 33-file are the following: 2525 1451 93 2525 1451 94 9.60189E-06 9.64312E-06 9.73051E-06 9.85035E-06 2525 1451 95 1.00065E-05 1.02262E-05 1.04988E-05 1.07979E-05 2525 1451 96 1.11916E-05 1.18366E-05 1.26678E-05 1.36336E-05 2525 1451 97 1.58284E-05 1.75566E-05 2.24423E-05 2.62145E-05 2525 1451 98 3.37354E-05 4.71224E-05 6.03072E-05 7.19641E-05 2525 1451 99 9.68428E-05 1.30367E-04 1.71642E-04 2.20387E-04 2525 1451 100 2.75154E-04 3.25769E-04 3.63859E-04 4.27408E-04 2525 1451 101 4.37291E-04 5.07300E-04 5.98776E-04 1.01930E-03 2525 1451 102 2.45165E-03 3.58243E-03 6.03353E-03 6.07530E-02 2525 1451 103 8.38378E-02 2.25620E-01 3.56662E-01 2525 1451 104 2525 1451 105 References: 2525 1451 106 1. E.Weigold Australian J. Phys., v. 13, p. 186, 1960 2525 1451 107 2. R.Wenusch, H.Vonach Oesterr. Akad. Wiss., Math. and Naturw. 2525 1451 108 Anzeiger, v. 99, p. 1, January 1962 2525 1451 109 3. A.Paulsen, H.Liskien J. of Nucl. Energy, v. AB19, p. 907, 2525 1451 110 November 1965 2525 1451 111 4. H.O.Menlove et al., Phys. Rev., v. 163, p. 1308, 1967 2525 1451 112 5. H.Vonach EXFOR 21533.002, 1968 2525 1451 113 6. R.C.Barrall, J.A.Holmes, M.Silbergeld Report AFWL-TR-68-134, 2525 1451 114 Kirtland, New Mexico, March 1969 2525 1451 115 7. R.C.Barrall, M.Silbergeld, D.G.Gardner, Nucl. Phys. A, v.138, 2525 1451 116 p.387, December 1969 2525 1451 117 8. M.Bormann, B.Lammers, Progress Report, EANDC(E)-115U, 2525 1451 118 March 1969 2525 1451 119 9. G.N.Maslov, F.Nasyrov, N.F.Pashkin Yadernye Konstanty , v. 9,2525 1451 120 pp. 50-56, Atomizdat-1972 2525 1451 121 10. O.Schwerer, M.Winkler-Rohatsch, G.Winkler Oesterr. Akad. 2525 1451 122 Wiss., Math. and Naturw. Anzeiger, v. 113, p. 153, June 1976 2525 1451 123 11. G.F.Auchampaugh, D.M.Drake, L.R.Veeser, Neutron cross section 2525 1451 124 programs in the energy region from 1 to 24 MeV at the LASL 2525 1451 125 Van De Graaff facilities. C,77BNL,, p. 231, July 1977 2525 1451 126 12. B.M.Bahal, R.Pepelnik Report GKSS-84-E-, 1984 2525 1451 127 B.M.Bahal, R.Pepelnik Progress Report NEANDC(E)-252/U,(5), 2525 1451 128 p.28, June 1984 2525 1451 129 13. M.Berrada Measurement and Analysis of 14 MeV Neutron Nuclear 2525 1451 130 Reaction Cross-Sections by X and Gamma Spectroscopy. Progress 2525 1451 131 on Research Contract-3311.R1/RB, IAEA NDS, Vienna, April 1984 2525 1451 132 14. J.W.Meadows, D.L.Smith, M.M.Bretscher, S.A.Cox, Annals of 2525 1451 133 Nuclear Energy, v. 14, p. 489, September 1987 2525 1451 134 15. L.R.Greenwood Report, ASTM-STP-956, p. 743, 1987 2525 1451 135 16. Y.Ikeda et al., Report, JAERI-1312, March 1988 2525 1451 136 17. Zhao Wenrong, Lu Hanlin, Yu Weixiang, Yuan Xialin Compilation 2525 1451 137 of measurements and evaluations of nuclear activation cross 2525 1451 138 sections for nuclear data applications. Report, INDC(CPR)-16, 2525 1451 139 IAEA, Vienna, August 1989 2525 1451 140 18. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v. 106, p. 332, 1990 2525 1451 141 19. M.Sakuma et al., Report, JAERI-M-92-027, 1992 2525 1451 142 20. T.S.Soewarsono, Y.Uwamino, T.Nakamura Progress Report, 2525 1451 143 JAERI-M-92-027, p. 354, March 1992 2525 1451 144 21. Y.Uwamino, H.Sugita, Y.Kondo, T.Nakamura Nucl. Sci. Eng., 2525 1451 145 v. 111, p. 391, 1992 2525 1451 146 22. M.Bostan, S.M.Qaim Phys. Rev. C, v. 49, pp. 266-271, 1994 2525 1451 147 23. S.Iwasaki et al., Proc of The 1996 Symposium on Nuclear Data. 2525 1451 148 November 21-22, 1996, JAERI, Tokai, Ibaraki, Japan, Report 2525 1451 149 INDC(JPN)-179/U, pp. 169-175, March 1997 2525 1451 150 24. A.A.Filatenkov, S.V.Chuvaev, " Systematic activation cross 2525 1451 151 sections measurement at neutron energies around 14 MeV MeV", 2525 1451 152 Preprit RI-252, M.: Atominform, 1999 2525 1451 153 25. V.J.Ashby et al. Second UN Conf. on the Peaceful Uses of 2525 1451 154 Atomic Energy, Geneva, 1-13 September 1958, v. 15, p.3 (2494) 2525 1451 155 26. J.Nix, D.Chittenden, D.G.Gardner, Progress Report, A-ARK-61, 2525 1451 156 p.6, January 1961 2525 1451 157 27. B.Granger, M.Longueve Report EANDC(E)-49L, p.83, October 1963 2525 1451 158 28 O.A.Salnikov et al., Proc. 1st All Union Conf. on Neutron Phy-2525 1451 159 sics, 24-28 May 1971, Kiev, USSR, "Naukova Dumka", Kiev 1972, 2525 1451 160 Vol. 1, pp. 214-218 2525 1451 161 29. J.Araminowicz, J.Dresler "Investigation of the (n,2n) reac- 2525 1451 162 tions with 14.6 MeV neutrons", Progress Report INR-1464, 2525 1451 163 pp. 14-18, May 1973 2525 1451 164 30. F.Deak et al. Acta Phys. Hung., v. 38, p. 209, 1975 2525 1451 165 31. K.Kayashima et al. Progress Report NEANDC(J)-61U, p.94, 2525 1451 166 September 1979 2525 1451 167 32. A.Ercan et al., Proc. of an Int. Conf. on Nuclear Data for 2525 1451 168 Science and Technology, 13-17 May 1991, Julich, FRG, Springer-2525 1451 169 Verlag, 1992, p. 376 2525 1451 170 33. M.Matuzda et al., "Measurement of (n,2n) reaction cross sec- 2525 1451 171 tion using a 14MeV pencil beam source", S, JAERI-C-02-006, 2525 1451 172 p. 144, November 2002 2525 1451 173 34. G.Y.Tertychnyj, E.L.Trykov, Modified version of GNASH code. 2525 1451 174 Private communication, IPPE, Obninsk, May 1999 2525 1451 175 35. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 2525 1451 176 36. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2525 1451 177 st's Meeting on Evaluation and Processing of Covariance Data, 2525 1451 178 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 2525 1451 179 37. A.Fabry, J.P.Deworm, Progress Report EANDC(E)-57, p. 69, 1965 2525 1451 180 38. K.Kobayashi, I.Kimura, Progress Report NEANDC(J)-67U, p. 42, 2525 1451 181 September 1980 2525 1451 182 39. W.Mannhart Validation of Differential Cross Sections with 2525 1451 183 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2525 1451 184 September 2002 2525 1451 185 40. L.W.Weston et al., Evaluated Neutron Data for Uranium-235, 2525 1451 186 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 2525 1451 187 41. W.Mannhart Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 2525 1451 188 2525 1451 189 ***************************************************************** 2525 1451 190 2525 1451 191 EVALUATION of the RESONANCE PARAMETERS of Mn-55 in the ENERGY 2525 1451 192 RANGE 0 to 122 keV- H. Derrien, L.C. Leal, N.M.Larson, D. Wiarda 2525 1451 193 K. Guber, and G. Arbanas. 2525 1451 194 2525 1451 195 The resonance parameters were obtained from a sequential Bayes 2525 1451 196 SAMMY analysis of the most recent experimental neutron 2525 1451 197 transmissions and capture cross sections in the resolved energy 2525 1451 198 range: Harvey et al. transmissions measured at ORELA in 1980, 2525 1451 199 Aerts et al. Capture cross sections measured at GELINA in 2006, 2525 1451 200 and Guber et al. Capture cross section measured at ORELA in 2007. 2525 1451 201 For the evaluation in the thermal energy range Widder et al. 2525 1451 202 (1975) capture cross section, Cote et al. (1964) total cross 2525 1451 203 sections, and Rainwater et al. (1964) total cross sections were 2525 1451 204 considered. The thermal capture cross sections were normalized at 2525 1451 205 the 0.0253 eV value of 13.27 b which is an average of the 2525 1451 206 available experimental values, consistent with the recent 2525 1451 207 evaluation of Trkov et al.(2007). The thermal cross sections 2525 1451 208 calculated by the resonance parameters are the following: 2525 1451 209 Res. Int. 2525 1451 210 Capture 13.274 b 13.514 2525 1451 211 Total 15.390 b - 2525 1451 212 Scattering 2.116 b - 2525 1451 213 2525 1451 214 The capture resonance integral is 13.516 b in the energy range 2525 1451 215 0.5 eV to 120 keV. 2525 1451 216 2525 1451 217 Most of the p-wave resonances are not observed in the experimental2525 1451 218 transmission data. For those resonances only the capture area 2525 1451 219 could be obtained with good accuracy. The capture area is 2525 1451 220 proportional to gamman*gammag / gammatot and only the product 2525 1451 221 gamman*gammag could be defined. A solution is to assign to all 2525 1451 222 this resonances a constant capture width value equal to an 2525 1451 223 estimated averaged value. In this case the SAMMY fit to the 2525 1451 224 capture data is generally poor. The solution of varying both the 2525 1451 225 capture width and the neutron width in the SAMMY fit has been 2525 1451 226 chosen is the evaluation. The resulting capture widths do not 2525 1451 227 deviate too much from an average value. The fit is obviously not 2525 1451 228 unique but give a good description of the experimental data. The 2525 1451 229 study of the statistical properties of the neutron widths has 2525 1451 230 shown that the obtained set of parameters is reasonable. 2525 1451 231 2525 1451 232 Only s-wave and p-wave resonances are given in the evaluation. 2525 1451 233 However the study of the statistical properties of the p-wave 2525 1451 234 resonance parameters has shown that 25% of them(the very small 2525 1451 235 one) could be d-wave resonances. Including these possible d-wave 2525 1451 236 resonances in the p-wave resonances has a negligible effect on 2525 1451 237 the calculated capture cross section. 2525 1451 238 2525 1451 239 Two components of the capture cross section are given is the 2525 1451 240 evaluation: the first component is calculated by the observed 2525 1451 241 resonance parameters; the second component is given as a File 3 2525 1451 242 background. This background stands for the contribution of the 2525 1451 243 the contribution of the direct capture, for the contribution of 2525 1451 244 non observed d-wave resonances, and for possible errors in the 2525 1451 245 errors in the calculation of the multiple scattering effect by 2525 1451 246 SAMMY in the experimental capture cross sections. The estimation 2525 1451 247 of the average d-wave contribution below 122 keV was obtained from2525 1451 248 SAMMY/URR. The error on the background file is important (20% to 2525 1451 249 30%), contributing to the most part of the uncertainty on the 2525 1451 250 average captur cross section 2525 1451 251 2525 1451 252 The following Table compares the average capture cross section to 2525 1451 253 the experimental values of Lerigoleur , and of Garg and Macklin. 2525 1451 254 The present evaluation is systematically lower than Lerigoleur 2525 1451 255 (absolute measurement) by 12% on average; part of the discrepancy 2525 1451 256 could be due to the inaccuracy of the calculation of the d-wave 2525 1451 257 component in the background file. 2525 1451 258 2525 1451 259 2525 1451 260 ___________________________________________________________ 2525 1451 261 Energy Range Present Results Lerigoleur Garg-Macklin 2525 1451 262 keV mb mb Mb 2525 1451 263 ___________________________________________________________ 2525 1451 264 15 - 20 47.98+/-2.05 57.05+/-4.56 48.6 2525 1451 265 20 - 30 35.79+/-1.79 40.97+/-3.28 44.6 2525 1451 266 30 - 40 25.24+/-1.20 27.43+/-2.19 44.7 2525 1451 267 40 - 50 25.24+/-1.20 19.58+/-1.57 28.2 2525 1451 268 50 - 60 20.40+/-1.20 20.41+/-1.63 26.0 2525 1451 269 60 - 80 16.69+/-1.30 20.19+/-1.61 21.5 2525 1451 270 80 -100 15.00+/-1.10 17.65+/-1.41 16.3 2525 1451 271 100 -120 11.63+/-1.10 12.65+/-1.41 14.3 2525 1451 272 ___________________________________________________________ 2525 1451 273 2525 1451 274 Resonance parameter covariance was generated in the resolved 2525 1451 275 energy region (1.0-5 eV to 125 keV) with the computer code SAMMY 2525 1451 276 at ORNL. Experimental data and uncertainties were used to generate2525 1451 277 covariance data. SAMMY covariance information was converted in 2525 1451 278 the ENDF FILE32 representation. The covariance information was 2525 1451 279 processed with the PUFF-IV code. 2525 1451 280 2525 1451 281 The details of the evaluation are in progress of publication in 2525 1451 282 an ORNL/TM report. 2525 1451 283 2525 1451 284 References: 2525 1451 285 2525 1451 286 HA 90 Harvey, private communication, 2007 2525 1451 287 AE 06, private communication 2006 2525 1451 288 GU 07 Guber, to be published, 2007 2525 1451 289 WI 75, Wilder, R_EIR-217, 1975 2525 1451 290 CO 64, Cote, PR/B, 134, 1047, 1964 2525 1451 291 RA 64, Rainwater, RSI, 35, 263, 1964 2525 1451 292 TR 07, private communication 2007 2525 1451 293 LE 76, Lerigoleur CEA-R-4888, 1976 2525 1451 294 GA 78, Garg-Madelin, PR/C, 18, 2079, 1978 2525 1451 295 2525 1451 296 ***************************************************************** 2525 1451 297 ***************** Program LINEAR (VERSION 2012-1) ***************2525 1451 298 For All Data Greater than 1.0000D-10 barns in Absolute Value 2525 1451 299 Data Linearized to Within an Accuracy of .100000000 per-cent 2525 1451 300 ***************** Program GROUPIE (VERSION 2012-1) **************2525 1451 301 Unshielded Group Averages Using 640 Groups 2525 1451 302 Weighting Spectrum: Flat (Constant) Spectrum 2525 1451 303 1 451 291 02525 1451 304 2 151 4 02525 1451 305 3 1 9576 12525 1451 306 3 16 52 12525 1451 307 3 102 20552 12525 1451 308 33 16 151 12525 1451 309 33 102 251 12525 1451 310 2525 1 0 311 2525 0 0 312 25055.0000 54.4661000 0 0 1 02525 2151 313 2.505500+4 1.000000+0 0 0 1 02525 2151 314 1.000000-5 1.000000+5 0 0 0 02525 2151 315 2.500000+0 5.150000-1 0 0 0 02525 2151 316 2525 2 0 317 2525 0 0 318 25055.0000 54.4661000 0 0 0 02525 3 1 319 0.0 0.0 0 0 1 6412525 3 1 320 641 1 2525 3 1 321 1.00000E-4 214.088843 1.05000E-4 209.068326 1.10000E-4 204.3828732525 3 1 322 1.15000E-4 200.001780 1.20000E-4 194.917111 1.27500E-4 189.2866792525 3 1 323 1.35000E-4 184.120284 1.42500E-4 179.354613 1.50000E-4 174.2518872525 3 1 324 1.60000E-4 168.912535 1.70000E-4 164.039052 1.80000E-4 159.5679772525 3 1 325 1.90000E-4 155.443521 2.00000E-4 151.627880 2.10000E-4 148.0808902525 3 1 326 2.20000E-4 144.774880 2.30000E-4 141.679990 2.40000E-4 138.0911862525 3 1 327 2.55000E-4 134.116805 2.70000E-4 131.048400 2.80000E-4 127.6568842525 3 1 328 3.00000E-4 123.504727 3.20000E-4 119.736906 3.40000E-4 116.2983832525 3 1 329 3.60000E-4 113.142844 3.80000E-4 110.233232 4.00000E-4 107.2231632525 3 1 330 4.25000E-4 104.150299 4.50000E-4 101.330805 4.75000E-4 98.73076202525 3 1 331 5.00000E-4 96.3261104 5.25000E-4 94.0895259 5.50000E-4 92.00669422525 3 1 332 5.75000E-4 90.0562146 6.00000E-4 88.0545367 6.30000E-4 86.01487762525 3 1 333 6.60000E-4 84.1147700 6.90000E-4 82.3372204 7.20000E-4 80.40460972525 3 1 334 7.60000E-4 78.3545570 8.00000E-4 76.4579811 8.40000E-4 74.69396802525 3 1 335 8.80000E-4 73.0513271 9.20000E-4 71.5139624 9.60000E-4 70.07163942525 3 1 336 .001000000 68.5550262 .001050000 66.9791449 .001100000 65.51184312525 3 1 337 .001150000 64.1383435 .001200000 62.5448361 .001275000 60.78054342525 3 1 338 .001350000 59.1617864 .001425000 57.6704334 .001500000 56.07213142525 3 1 339 .001600000 54.4008983 .001700000 52.8754168 .001800000 51.47564452525 3 1 340 .001900000 50.1858871 .002000000 48.9920070 .002100000 47.88226982525 3 1 341 .002200000 46.8481230 .002300000 45.8809777 .002400000 44.75798492525 3 1 342 .002550000 43.5148931 .002700000 42.5561822 .002800000 41.49547492525 3 1 343 .003000000 40.1971979 .003200000 39.0192820 .003400000 37.94406552525 3 1 344 .003600000 36.9575270 .003800000 36.0485739 .004000000 35.10712512525 3 1 345 .004250000 34.1462472 .004500000 33.2645649 .004750000 32.45221232525 3 1 346 .005000000 31.6996809 .005250000 31.0008195 .005500000 30.34880882525 3 1 347 .005750000 29.7395532 .006000000 29.1127345 .006300000 28.47557872525 3 1 348 .006600000 27.8807948 .006900000 27.3243139 .007200000 26.72018312525 3 1 349 .007600000 26.0782182 .008000000 25.4847218 .008400000 24.93242942525 3 1 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