IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 22046.0000 45.5579000 0 0 34 102225 1451 1 0.0 0.0 0 0 0 62225 1451 2 1.00000000 60000000.0 0 0 10 20022225 1451 3 300.000000 0.0 1 0 241 62225 1451 4 22-Ti- 46 FEI EVAL-Jan02 K.I.Zolotarev 2225 1451 5 DIST-Feb2004 2225 1451 6 ----IRDF-2002 MATERIAL 2225 2225 1451 7 -----INCIDENT NEUTRON DATA 2225 1451 8 ------ENDF-6 FORMAT 2225 1451 9 ******************************************************************2225 1451 10 IAEA, July 2011 (A. Trkov) 2225 1451 11 Extended cross sections and covariances from 20 to 60 MeV 2225 1451 12 by TENDL-2010, renormalised for continuity. 2225 1451 13 ******************************************************************2225 1451 14 ***************************************************************** 2225 1451 15 22-TI- 46 FEI EVAL-Jan02 K.I.Zolotarev 2225 1451 16 DIST-Feb02 20020203 2225 1451 17 ----BROND-2 MATERIAL 2225 2225 1451 18 -----INCIDENT NEUTRON DATA 2225 1451 19 ------ENDF-6 FORMAT 2225 1451 20 ------Russian Reactor Dosimetry File RRDF-2002 2225 1451 21 ***************************************************************** 2225 1451 22 Author of evaluation: K.I.Zolotarev 2225 1451 23 ***************************************************************** 2225 1451 24 MF=3 2225 1451 25 MT= 16 -(n,2n) cross section 2225 1451 26 ------------------------------------- 2225 1451 27 Excitation function for the Ti-46(n,2n)Ti-45 reaction in the 2225 1451 28 energy region from threshold to 20 MeV was evaluated by means of 2225 1451 29 statistical analysis of experimental cross section data [1-18]. 2225 1451 30 All experimental data were renormalized to the new standards 2225 1451 31 for monitor reactions cross sections and decay data. In the measu-2225 1451 32 rements [5,14-16] uncertainties were increased until the data had 2225 1451 33 become mutually consistent. 2225 1451 34 The final procedure of evaluation the Ti-46(n,2n)Ti-45 reac- 2225 1451 35 tion excitation function has been carried out within the frame- 2225 1451 36 work of generalized least squares method. Statistical analysis of 2225 1451 37 input cross section data was carried out by means of PADE-2 code 2225 1451 38 [19]. Rational function was used as the model function [20]. 2225 1451 39 The evaluated Ti-46(n,2n)Ti-45 excitation function averaged 2225 1451 40 on U-235 thermal neutron fission spectrum [21] and Cf-252 sponta- 2225 1451 41 neous fission neutron spectrum [22] gives the following values : 2225 1451 42 ---------------------------------------------------------------- 2225 1451 43 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 2225 1451 44 ---------------------------------------------------------------- 2225 1451 45 U-235 neutron fission I 0.0044686 I 2225 1451 46 ---------------------------------------------------------------- 2225 1451 47 CF-252 spont. fission I 0.011982 I 0.093 +- 0.031 [23] 2225 1451 48 ---------------------------------------------------------------- 2225 1451 49 2225 1451 50 MT=103 -(n,p) cross section 2225 1451 51 ------------------------------------- 2225 1451 52 Excitation function for the Ti-46(n,p)Sc-46m+g reaction in 2225 1451 53 the energy region from threshold to 20 MeV was evaluated by means 2225 1451 54 of statistical analysis of experimental cross section data [6,17, 2225 1451 55 24-38] and data from GNASH calculation [39]. 2225 1451 56 Analyzed microscopic experimental data were renormalized to 2225 1451 57 the new recommended standards for monitor reaction cross sections 2225 1451 58 and decay data. All experiments performed with Ti-natural samples 2225 1451 59 were corrected for the contribution of the Ti-47(n,np+pn)Sc-46m+g 2225 1451 60 and Ti-47(n,d)Sc-46m+g reactions. Total cross section for these 2225 1451 61 reactions were taken from ref.[40]. Experimental data from ref. 2225 1451 62 [6,27] were used partially. Data of Bormann et al. [6] were taken 2225 1451 63 only for 14.1 MeV point. In the work of Lukic and Carroll [27] it 2225 1451 64 were used data measured relative Fe56(n,p)Mn56 and Al27(n,a)Na24 2225 1451 65 monitor reactions. These data were renormalized to the cross sec- 2225 1451 66 sections obtained in the ref.[28]. Data of Smith and Meadows [28] 2225 1451 67 measured with using D(d,n)He3 neutron source were renormalized 2225 1451 68 in the energy range 6.996-9.950 MeV to the preliminary evaluated 2225 1451 69 integral of cross section from new experimental data [34,37,38]. 2225 1451 70 Experimental cross section data [8] , [41-46] were rejected 2225 1451 71 due to their discrepancy with the main bulk of experimental data 2225 1451 72 [6,17,24-38] and data from theoretical model calculation. 2225 1451 73 Statistical analysis of input cross section data was carried 2225 1451 74 out by means of PADE-2 code [19]. Rational function was used as 2225 1451 75 the model function [20]. 2225 1451 76 U-235 thermal fission [21] and Cf-252 spontaneous fission 2225 1451 77 neutron spectra [22] averaged cross sections calculated from the 2225 1451 78 evaluated Ti-46(n,p)Sc-46m+g reaction excitation function are 2225 1451 79 the following: 2225 1451 80 ---------------------------------------------------------------- 2225 1451 81 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 2225 1451 82 ---------------------------------------------------------------- 2225 1451 83 U-235 neutron fission I 11.447 I 11.57 +- 0.37 [47] 2225 1451 84 I I 11.51 +- 0.40 [48] 2225 1451 85 I I 11.55 +- 0.20 [49] 2225 1451 86 ---------------------------------------------------------------- 2225 1451 87 CF-252 spont. fission I 13.818 I 14.20 +- 0.24 [50] 2225 1451 88 I I 14.07 +- 0.25 [51] 2225 1451 89 ---------------------------------------------------------------- 2225 1451 90 2225 1451 91 MF=33 2225 1451 92 MT= 16 -(n,2n) cross section cov. matrix 2225 1451 93 ---------------------------------------- 2225 1451 94 Uncertainties in the evaluated excitation function for the 2225 1451 95 reaction Ti-46(n,2n)Ti-45 are given in the form of relative cova- 2225 1451 96 riance matrix for the 17-neutron energy groups (LB=5). Covariance 2225 1451 97 matrix of uncertainties was calculated simultaneously with 2225 1451 98 recommended cross section data by means of PADE-2 code. 2225 1451 99 Eigenvalues of the 6-th digits relative covariance matrix 2225 1451 100 given in the 33-file are the following: 2225 1451 101 2225 1451 102 2.26418E-07 2.55017E-07 2.97541E-07 3.62667E-07 2225 1451 103 4.74369E-07 6.90723E-07 1.00928E-06 1.38635E-06 2225 1451 104 2.05902E-06 3.42154E-06 6.73918E-06 1.77794E-05 2225 1451 105 1.16721E-04 5.82882E-03 7.49965E-03 2.28734E-02 2225 1451 106 4.20028E-02 2225 1451 107 2225 1451 108 MT=103 -(n,p) cross section cov. matrix 2225 1451 109 ---------------------------------------- 2225 1451 110 Uncertainties in the evaluated excitation function for the 2225 1451 111 reaction Ti-46(n,p)Sc-45m+g are given in the form of relative co- 2225 1451 112 variance matrix for the 31-neutron energy groups (LB=5). Covari- 2225 1451 113 ance matrix of uncertainties was calculated simultaneously with 2225 1451 114 recommended cross section data by means of PADE-2 code. 2225 1451 115 Eigenvalues of the 6-th digits relative covariance matrix 2225 1451 116 given in the 33-file are the following: 2225 1451 117 2225 1451 118 3.10934E-07 3.16123E-07 3.24666E-07 3.37022E-07 2225 1451 119 3.51765E-07 3.72727E-07 3.91781E-07 4.23365E-07 2225 1451 120 4.47112E-07 4.91264E-07 5.29779E-07 6.15458E-07 2225 1451 121 6.75168E-07 7.93660E-07 9.79888E-07 1.29384E-06 2225 1451 122 1.98373E-06 3.65835E-06 2.36258E-04 5.76816E-04 2225 1451 123 7.66259E-04 1.00346E-03 1.10942E-03 1.43365E-03 2225 1451 124 2.89439E-03 3.32523E-03 4.20534E-03 7.47772E-03 2225 1451 125 1.06722E-02 1.67016E-02 7.87709E-02 2225 1451 126 2225 1451 127 References : 2225 1451 128 1. A.Poularikas, R.W.Fink Physical Review, v.115, p.989, 1959 2225 1451 129 2. R.J.Prestwood,B.P.Bayhurst Phys. Rev, v.121, p.1438,Mar.1961 2225 1451 130 3. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 2225 1451 131 3. M.Cevolani, S.Petralia Nuovo Cimento, v.26, p.1328, Dec. 1962 2225 1451 132 5. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 2225 1451 133 6. M.Bormann et al. Nuclear Physics, v.63, p.438, March 1965 2225 1451 134 7. J.Csikai Progress Report EANDC-50S, v.2, p.102, July 1965 2225 1451 135 8. H.L.Pai Canadian J. of Physics, v.44, p.2337, 1966 2225 1451 136 9. G.N.Maslov et al. Yadernye Konstanty, No.9, p.50, 1972 2225 1451 137 10. J.Araminowicz, J.Dresler Report INR-1464, p.14, May 1973 2225 1451 138 11. A.Paulsen et al. Atomkernenergie , v.26, p.34, August 1975 2225 1451 139 12. S.M.Qaim, N.I.Molla Proc of 9th Symposium on Fusion Technolo-2225 1451 140 gy, Garmisch, Germany, 14-18 June 1976, p.589 2225 1451 141 13. R.A.Sigg J. Diss. Abst., v.B37, p.2237, November 1976 2225 1451 142 14. J.Csikai Proc. of Int. Conf. on Nuclear Data for Science and 2225 1451 143 Technology, Antwerp, 6-10 September 1982, p.414, Reidel Publ. 2225 1451 144 Company, 1983 2225 1451 145 15. N.T.Molla et al. Progress Report INDC(BAN)-002, p.1, Feb.1983 2225 1451 146 16. Zhou Muyao et al. Chinese J. of Nucl. Phys., v.9, p.34, 1987 2225 1451 147 17. Y.Ikeda et al. Report JAERI-1312, March 1988 2225 1451 148 18. P.M.Dighe e.a. Indian J. of Pure and Applied Physics, v.29, 2225 1451 149 p.665, October 1991 2225 1451 150 19. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 2225 1451 151 20. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2225 1451 152 st's Meeting on Evaluation and Processing of Covariance Data, 2225 1451 153 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 2225 1451 154 21. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2225 1451 155 Library, MAT=9228, MF=5, MT=18, eval. April 1989 2225 1451 156 22. W.Mannhart IAEA-TECDOC-410, p.158, 1987 2225 1451 157 23. J.Csikai, Z.Dezso Proc. of 4th All Union Conf. on Neutron 2225 1451 158 Physics, Kiev, 18-22 April 1977, v.3, p.32 2225 1451 159 24. H.Liskien, A.Paulsen Nucl. Phys., v.63, p.393, March 1965 2225 1451 160 25. V.N.Levkovskij et al. Yadernaja Fizika (Sov.), v.10, n.1, 2225 1451 161 p.44, July 1969 2225 1451 162 26. S.K.Ghorai et al. J. Nucl. Energ., v.25, p.319, August 1971 2225 1451 163 27. Y.Lukic, E.E.Carroll Nucl. Sci. Eng., v.43, p.233, 1971 2225 1451 164 28. D.L.Smith, J.W.Meadows Nucl. Sci. Eng., v.58, p.314, 1975 2225 1451 165 29. Lu Hamlin et al. Chinese J. of Atomic Energy Sci. Technology,2225 1451 166 v.9, no.2, p.113, May 1975 2225 1451 167 30. K.Kayashima et al. Prog. Report NEANDC(J)-61U, p.94, Sep.1979 2225 1451 168 31. M.Viennot et al. Proc of Int. Conference on Nuclear Data for 2225 1451 169 Science and Technology, Antwerp, 6-10 September 1982, p.406 2225 1451 170 32. N.I.Molla et al. Progress Report INDC(BAN)-003, Sept. 1986 2225 1451 171 33. Lu Hanlin et al. Report INDC(CPR)-16, IAEA, August 1989 2225 1451 172 34. N.I.Molla, S.M.Qaim, M.Uhl Phys. Rev. C, v.42, n.4, p.1540, 2225 1451 173 October 1990 2225 1451 174 35. M.Viennot et al. Nucl. Sci. Eng., v.108, p.289, July 1991 2225 1451 175 36. Yuan Junqian e.a. High Energy Physics and Nucl.Phys.(China), 2225 1451 176 v.16, n.1, p.57, January 1992 2225 1451 177 37. J.W.Meadows, D.L.Smith, L.R.Greenwood, R.C.Haight, Y.Ikeda, 2225 1451 178 C.Konno Annals of Nuclear Energy, v.23, p.877, July 1996 2225 1451 179 38. Lu Hanlin et al. Report INDC(CPR)-045, IAEA, October 1998 2225 1451 180 39. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 2225 1451 181 Model Code for Calculation of Cross Section and Emission 2225 1451 182 Spectra. Report LA-6947, Los Alamos, 1977 ; 2225 1451 183 E.L.Trykiv, G.Ya.Tertychnyi Private communication, IPPE, 2225 1451 184 Obninsk, May 1999 2225 1451 185 40. K.I.Zolotrarev RRDF-2002, MAT=2222, eval. January 2002 2225 1451 186 41. D.L.Allan Nucl. Phys., v.24, p.274, April 1961 2225 1451 187 42. W.G.Cross, H.L.Pai Prog. Report EANDC(CAN)-16, p.1, Jan. 1963 2225 1451 188 43. S.M.Qaim, N.I.Molla Nucl. Phys., v.A283, p.269, June 1977 2225 1451 189 44. I.Ribansky, S.Gmuca J. Phys. G, v.9, p.1537, December 1983 2225 1451 190 45. R.Pepelnik et al. Progress Report, NEANDC(E)-262U,(5), p.32, 2225 1451 191 June 1985 2225 1451 192 46. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v.106, p.332, 1990 2225 1451 193 47. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2225 1451 194 Washington D.C., 25-28 April 1989, v.2, p.923 2225 1451 195 48. W.Mannhart Proc. 5-th ASTM-EUR. Symp. on Reactor Dosimetry, 2225 1451 196 Geesthacht, FRG, September 24-28, 1984, Vol.2, p.813, 1985 2225 1451 197 49. W.Mannhart Progress Report INDC(Ger)-045, pp.40-43, 1999 2225 1451 198 50. W.Mannhart Handbook on Nuclear Activation Data . IAEA Tech- 2225 1451 199 nical Report series No.273, p.413, 1987 2225 1451 200 51. W.Mannhart Validation of Differential Cross Sections with 2225 1451 201 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2225 1451 202 September 2002 2225 1451 203 ***************************************************************** 2225 1451 204 The Q values and threshold energies were updated prior to pro- 2225 1451 205 cessing through the codes to comply with the values obtained 2225 1451 206 using the NNDC calculation program which is based on the 1995 2225 1451 207 Update to the Atomic mass Evaluation. 2225 1451 208 2225 1451 209 File 2 added to the pointwise file containing only the effective 2225 1451 210 scattering radius with no resonance parameters given. 2225 1451 211 Taken from ENDF/B-VI 2225 1451 212 2225 1451 213 Psuedo Threshold of 0.0 added at 2.1E+6 ev to MF/MT=3/103 2225 1451 214 in original evaluation 2225 1451 215 2225 1451 216 ***************************************************************** 2225 1451 217 ***************** Program LINEAR (VERSION 2002-1) ***************2225 1451 218 For All Data Greater than 1.0000E-10 barns in Absolute Value 2225 1451 219 Data Linearized to Within an Accuracy of .100000000 per-cent 2225 1451 220 ***************** Program SIGMA1 (VERSION 2002-1) ***************2225 1451 221 Data Doppler Broadened to 300.000000 Kelvin 2225 1451 222 for All Data Greater than 1.0000E-10 barns in Absolute Value 2225 1451 223 Data Linearized to Within an Accuracy pf .100000000 per-cent 2225 1451 224 ***************** Program FIXUP (Version 2002-1) ****************2225 1451 225 Corrected ZA/AWR in All Sections-----------------------------Yes 2225 1451 226 Corrected Thresholds-----------------------------------------Yes 2225 1451 227 Extended Cross Sections to 20 MeV----------------------------No 2225 1451 228 Allow Cross Section Deletion---------------------------------No 2225 1451 229 Allow Cross Section Reconstruction---------------------------No 2225 1451 230 Make All Cross Sections Non-Negative-------------------------Yes 2225 1451 231 Delete Energies Not in Ascending Order-----------------------Yes 2225 1451 232 Deleted Duplicate Points-------------------------------------Yes 2225 1451 233 Check for Ascending MAT/MF/MT Order--------------------------Yes 2225 1451 234 Check for Legal MF/MT Numbers--------------------------------Yes 2225 1451 235 Allow Creation of Missing Sections---------------------------No 2225 1451 236 Allow Insertion of Energy Points-----------------------------No 2225 1451 237 Create Uniform Energy Grid-----------------------------------No 2225 1451 238 Delete Section if Cross Section =0 at All Energies-----------Yes 2225 1451 239 ***************** Program LINEAR (VERSION 2012-1) ***************2225 1451 240 For All Data Greater than 1.0000D-10 barns in Absolute Value 2225 1451 241 Data Linearized to Within an Accuracy of .100000000 per-cent 2225 1451 242 ***************** Program GROUPIE (VERSION 2012-1) **************2225 1451 243 Unshielded Group Averages Using 640 Groups 2225 1451 244 Weighting Spectrum: Flat (Constant) Spectrum 2225 1451 245 1 451 245 12225 1451 246 2 151 4 12225 1451 247 3 16 27 12225 1451 248 3 103 42 12225 1451 249 33 16 44 12225 1451 250 33 103 106 12225 1451 251 2225 1 0 252 2225 0 0 253 22046.0000 45.5578000 0 0 1 02225 2151 254 2.204600+4 1.000000+0 0 0 1 02225 2151 255 1.000000-5 1.000000+5 0 0 0 02225 2151 256 0.000000+0 5.733000-1 0 0 0 02225 2151 257 2225 2 0 258 2225 0 0 259 22046.0000 45.5579000 0 0 0 02225 3 16 260 -13189800.0-13189800.0 0 0 1 672225 3 16 261 67 1 2225 3 16 262 13400000.0 5.45500E-6 13500000.0 2.69062E-4 13600000.0 .0013538942225 3 16 263 13700000.0 .003167185 13800000.0 .005539635 13900000.0 .0084628702225 3 16 264 14000000.0 .011885800 14100000.0 .015756100 14200000.0 .0200212002225 3 16 265 14300000.0 .024629400 14400000.0 .029530600 14500000.0 .0346768502225 3 16 266 14600000.0 .040022950 14700000.0 .045526750 14800000.0 .0511660252225 3 16 267 14900000.0 .056872075 15000000.0 .062608313 15100000.0 .0683747382225 3 16 268 15200000.0 .074141163 15300000.0 .079907588 15400000.0 .0855952332225 3 16 269 15500000.0 .091204100 15600000.0 .096812967 15700000.0 .1022853332225 3 16 270 15800000.0 .107621200 15900000.0 .112957067 16000000.0 .1181235002225 3 16 271 16100000.0 .123120500 16200000.0 .128117500 16300000.0 .1329310002225 3 16 272 16400000.0 .137561000 16500000.0 .142191000 16600000.0 .1466356672225 3 16 273 16700000.0 .150895000 16800000.0 .155154333 16900000.0 .1592341672225 3 16 274 17000000.0 .163134500 17100000.0 .167034833 17200000.0 .1707660002225 3 16 275 17300000.0 .174328000 17400000.0 .177890000 17500000.0 .1812951672225 3 16 276 17600000.0 .184543500 17700000.0 .187791833 17800000.0 .1908743752225 3 16 277 17900000.0 .193791125 18000000.0 .196707875 18100000.0 .1996246252225 3 16 278 18200000.0 .202373250 18300000.0 .204953750 18400000.0 .2075342502225 3 16 279 18500000.0 .210114750 18600000.0 .212532000 18700000.0 .2147860002225 3 16 280 18800000.0 .217040000 18900000.0 .219294000 19000000.0 .2215480002225 3 16 281 19100000.0 .223648400 19200000.0 .225595200 19300000.0 .2275420002225 3 16 282 19400000.0 .229488800 19500000.0 .231435600 19600000.0 .2332651252225 3 16 283 19700000.0 .234977375 19800000.0 .236689625 19900000.0 .2381165002225 3 16 284 20000000.0 0.0 2225 3 16 285 2225 3 0 286 22046.0000 45.5579000 0 0 0 02225 3103 287 -1584300.00-1584300.00 0 0 1 1802225 3103 288 180 1 2225 3103 289 2100000.00 3.42206E-6 2200000.00 1.02662E-5 2300000.00 1.71103E-52225 3103 290 2400000.00 2.39544E-5 2500000.00 3.98904E-5 2600000.00 9.93846E-52225 3103 291 2700000.00 2.37889E-4 2800000.00 4.78634E-4 2900000.00 8.52157E-42225 3103 292 3000000.00 .001398970 3100000.00 .002172540 3200000.00 .0032406352225 3103 293 3300000.00 .004678875 3400000.00 .006545195 3500000.00 .0088332052225 3103 294 3600000.00 .011449050 3700000.00 .014282900 3800000.00 .0173307502225 3103 295 3900000.00 .020716350 4000000.00 .024597800 4100000.00 .0290779002225 3103 296 4200000.00 .034170000 4300000.00 .039792900 4400000.00 .0457663252225 3103 297 4500000.00 .051856975 4600000.00 .057775050 4700000.00 .0632341002225 3103 298 4800000.00 .068060950 4900000.00 .072219050 5000000.00 .0757965502225 3103 299 5100000.00 .079116450 5200000.00 .082497900 5300000.00 .0861876502225 3103 300 5400000.00 .090482100 5500000.00 .095555300 5600000.00 .1014841502225 3103 301 5700000.00 .108255000 5800000.00 .115777000 5900000.00 .1239030002225 3103 302 6000000.00 .132481167 6100000.00 .141251500 6200000.00 .1500218332225 3103 303 6300000.00 .158677500 6400000.00 .167038500 6500000.00 .1749920002225 3103 304 6600000.00 .182459000 6700000.00 .189393500 6800000.00 .1957795002225 3103 305 6900000.00 .201623000 7000000.00 .206947500 7100000.00 .2116860002225 3103 306 7200000.00 .216090000 7300000.00 .220127250 7400000.00 .2237977502225 3103 307 7500000.00 .227143500 7600000.00 .230164500 7700000.00 .2331855002225 3103 308 7800000.00 .235943125 7900000.00 .238437375 8000000.00 .2409316252225 3103 309 8100000.00 .243425875 8200000.00 .245762125 8300000.00 .2479403752225 3103 310 8400000.00 .250118625 8500000.00 .252296875 8600000.00 .2544751252225 3103 311 8700000.00 .256653375 8800000.00 .258831625 8900000.00 .2610098752225 3103 312 9000000.00 .263188125 9100000.00 .265366375 9200000.00 .2675446252225 3103 313 9300000.00 .269722875 9400000.00 .271901125 9500000.00 .2740793752225 3103 314 9600000.00 .276257625 9700000.00 .278435875 9800000.00 .2804955832225 3103 315 9900000.00 .282436750 10000000.0 .284377917 10100000.0 .2863190832225 3103 316 10200000.0 .288260250 10300000.0 .290201417 10400000.0 .2919556252225 3103 317 10500000.0 .293522875 10600000.0 .295090125 10700000.0 .2966573752225 3103 318 10800000.0 .297992875 10900000.0 .299096625 11000000.0 .3002003752225 3103 319 11100000.0 .301304125 11200000.0 .302152667 11300000.0 .3027460002225 3103 320 11400000.0 .303339333 11500000.0 .303725000 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