777 0 0 0 2.906300+4 6.238940+1 0 0 41 12925 1451 1 0.000000+0 0.000000+0 0 0 0 62925 1451 2 1.000000+0 0.000000+0 0 0 10 22925 1451 3 0.000000+0 0.000000+0 0 0 135 32925 1451 4 29-Cu- 63 FEI EVAL-Nov01 K.I.Zolotarev 2925 1451 5 DIST-May12 Rev.3 May 2012 2925 1451 6 ----BROND-3 MATERIAL 2925 2925 1451 7 -----INCIDENT NEUTRON DATA 2925 1451 8 ------ENDF-6 FORMAT 2925 1451 9 ***************************************************************** 2925 1451 10 ------Russian Reactor Dosimetry File RRDF-2012 2925 1451 11 ***************************************************************** 2925 1451 12 Author of evaluation: K.I.Zolotarev 2925 1451 13 ***************************************************************** 2925 1451 14 2925 1451 15 ----- MF=3 MT=107 ----- 2925 1451 16 Evaluation of Cu-63(n,a)Co-60m+g- excitation function was car-2925 1451 17 ried out by means of statistical analysis of cross sections from 2925 1451 18 data base prepared in the energy range 2 - 20 Mev. In the energy 2925 1451 19 range 3.56 - 19.55 MeV input data base was formed with using of 2925 1451 20 experimental data from ref. [1-19]. Cross section data in the 2925 1451 21 interval 2.0 - 3.5 MeV were taken from theoretical model calcula- 2925 1451 22 tion. Experimental data included in the input data base were 2925 1451 23 renormalized using new cross sections standards for monitor reac- 2925 1451 24 tions and new standards for decay data. 2925 1451 25 The special correction was applied to the experimental data 2925 1451 26 [2,3,12,13,15,18]. Cross section data of A.Paulsen and H.Liskien 2925 1451 27 [2-3] measured in the energy region 12.09 - 19.55 MeV with using 2925 1451 28 T(d,n)He4 neutron source were multiplied to the factor 1.20805 . 2925 1451 29 Experimental data of Lu Hanlin et al. [12,18] , Wang Yongchag et 2925 1451 30 al. [13] and Konno et al. [15] were multiplied to the factors 2925 1451 31 0.88110, 0.86000, 0.84377 and 1.060, respectively. The correction 2925 1451 32 factors were derived from preliminary evaluated cross sections 2925 1451 33 integrals in the energy intervals 8.4 - 11.4 and 13 - 15 MeV . 2925 1451 34 Data of A.Paulsen and H.Liskien [2] in the energy range 2925 1451 35 5.76 - 11.48 MeV measured with using D(d,n)He3 , Be9(a,n)C12 , 2925 1451 36 C14(d,n)N15 , N15(d,n)O16 neutron sources were rejected due to 2925 1451 37 their inconsistency with precision measurements of G.Winkler et 2925 1451 38 al. [8] and integral experimental data for U-235 fission neutron 2925 1451 39 spectrum [20-23] and Cf-252 spontaneous fission neutron spectrum 2925 1451 40 [25-26]. Cross sections measured by J.Kantele and D.Gardner [27], 2925 1451 41 M.Bormann et al. [28], G.Maslov et al. [29] and K.Kayashima et al.2925 1451 42 [30] were also rejected due to the big discrepancy with the main 2925 1451 43 bulk experimental data. 2925 1451 44 The final procedure evaluation of (n,a) excitation function 2925 1451 45 was carried out by means of Pade-2 code [31]. 2925 1451 46 Evaluated excitation function for the reaction Cu63(n,a)Co60 2925 1451 47 was tested with using integral experimental data [20-24] for 2925 1451 48 U-235 thermal fission neutron spectrum and evaluated integral ex- 2925 1451 49 perimental data [32-33] for Cf-252 spontaneous fission neutron 2925 1451 50 spectrum. Calculated and measured average cross section values 2925 1451 51 for U-235 thermal fission neutron spectrum [34] and Cf-252 sponta-2925 1451 52 neous fission neutron spectrum [35] are given in the table 1. 2925 1451 53 Table 1 2925 1451 54 ----------------------+-----------------+----------------------- 2925 1451 55 Type of spectrum | ,mb (calc.) | , mb (measured) 2925 1451 56 ----------------------+-----------------+----------------------- 2925 1451 57 U-235 neutron fission | 0.53048 | 0.5255 +- 0.0316 [20] 2925 1451 58 | | 0.520 +- 0.040 [21] 2925 1451 59 | | 0.518 +- 0.035 [22] 2925 1451 60 | | 0.5255 +- 0.0156 [23] 2925 1451 61 | | 0.536 +- 0.015 [23] 2925 1451 62 | | 0.4935 +- 0.0242 [24] 2925 1451 63 | | 0.4918 +- 0.0241 [33] 2925 1451 64 ----------------------+-----------------+----------------------- 2925 1451 65 CF-252 spont. fission | 0.69351 | 0.709 +- 0.017 [25] 2925 1451 66 | | 0.675 +- 0.018 [26] 2925 1451 67 | | 0.6897 +- 0.0130 [32] 2925 1451 68 | | 0.6887 +- 0.0135 [33] 2925 1451 69 ----------------------+-----------------+----------------------- 2925 1451 70 2925 1451 71 ----- MF=33 MT=107 ----- 2925 1451 72 Uncertainties in the evaluated excitation function for the 2925 1451 73 reaction Cu-63(n,a)Co-60m+g are given in the form of relative co- 2925 1451 74 variance matrix for the 25-neutron energy groups (LB=5). Covari- 2925 1451 75 ance matrix of uncertainties was calculated simultaneously with 2925 1451 76 recommended cross section data by means of PADE-2 code. 2925 1451 77 Eigenvalues of the 6-th digits relative covariance matrix 2925 1451 78 given in the 33-file are the following: 2925 1451 79 2925 1451 80 6.72257E-07 6.90982E-07 7.26610E-07 7.80996E-07 2925 1451 81 8.73734E-07 1.00295E-06 1.14889E-06 1.39338E-06 2925 1451 82 1.71680E-06 1.98760E-06 2.46713E-06 3.21657E-06 2925 1451 83 4.04399E-06 4.67325E-06 6.03008E-06 8.12500E-06 2925 1451 84 2.08229E-05 2.99016E-04 1.40310E-03 1.73651E-03 2925 1451 85 2.36498E-03 2.92692E-03 6.39266E-03 1.70593E-02 2925 1451 86 8.28804E-02 2925 1451 87 2925 1451 88 References: 2925 1451 89 1. B.Czapp, H.Vonach, Oesterr. Akad. Wiss, Math, Naturw. 2925 1451 90 Anzeiger, v.97, p.13, January 1960 2925 1451 91 2. A.Paulsen, H.Liskien, Nukleonik, v.10, p.91, July 1967 2925 1451 92 3. A.Paulsen, Zeitschrift f. Phys., v.205, p.226, August 1967 2925 1451 93 4. R.C.Barrall et al., Report AFWL-TR-68-134, March 1969 2925 1451 94 6. G.Winkler, Nucl. Sci. Eng., v.67, n.2, p.260, August 1978 2925 1451 95 8. G.Winkler, D.L.Smith, J.W.Meadows, Nucl. Sci. Eng., v.76, 2925 1451 96 p.30, October 1980 2925 1451 97 9. U.Garuska et al., Prog. Report INDC(POL)-11, p.15, July 1980 2925 1451 98 10. O.I.Artem'ev et al., Atomnaja Energija (Sov.), v.49, n.3, 2925 1451 99 p.195, September 1980 2925 1451 100 11. L.R.Greenwood, Progress Report ASTM-STP-956, p.743, 1987 2925 1451 101 12. Lu Hanlin et al., China Journal of Nuclear Phys., v.12. n.4, 2925 1451 102 p. 373, 1990 2925 1451 103 13. Wang Yongchang et al., Chinese J. High Energy Phys. and Nucl. 2925 1451 104 Phys., v.14, p.919, October 1990 2925 1451 105 14. J.Csikai, C.M.Buczko, R.Pepelnik, H.M.Agrawal Annals of Nucl. 2925 1451 106 Energy, v.18, n.1, p.1, 1991 2925 1451 107 15. C.Konno et al., Report JAERI-1329, October 1993 2925 1451 108 16. J.W.Meadows et al., Annals of Nucl. Energy, v.23, p.877, 1996 2925 1451 109 17. A.A.Filatenkov et al., VANT, Ser.: Yadernye Konstanty, v.2, 2925 1451 110 p.8, Moscow, 1996 2925 1451 111 18. Lu Hanlin et al., Report INDC(CPR)-045, IAEA, October 1998 2925 1451 112 19. A.A.Filatenkov et al., Report RI-252, St.Petersburg, May 1999 2925 1451 113 20. R.Lloret, Progress Report EANDC(E)-57, p.172, February 1965 2925 1451 114 21. A.Fabry, J.P.Deworm, Progress Report EANDC(E)-66, p.125, 2925 1451 115 February 1966 2925 1451 116 22. K.Kobayashi et al., Nucl. Sci. Techn., v.13, p.531, Oct. 1976 2925 1451 117 23. L.P.Geraldo et al., Radiochimica Acta, v.57, pp.63-67, 1992 2925 1451 118 24. W.Mannhart, Progress Report INDC(Ger)-045, pp.40-43, 1999 2925 1451 119 25. G.Winkler et al., Nucl. Sci. Eng., v.78, p.415, August 1981 2925 1451 120 26. W.Mannhart, Proc. of Int. Conf. Nuclear Data for Science and 2925 1451 121 Technology, 6-10 September 1982, Antwerp, Holland, D.Reidel 2925 1451 122 Publishing Company, p.429 2925 1451 123 27. J.Kantele, D.Gardner, Nucl. Phys., v.35, p.353, 1962 2925 1451 124 28. M.Bormann et al., Nucl. Phys., v.A186, p.65, May 1972 2925 1451 125 29. G.N.Maslov, F.Nasyrov, N.F.Pashkin, Yadernye Konstanty, v.9, 2925 1451 126 p.50, Obninsk, 1972 2925 1451 127 30. K.Kayashima et al., Prog. Rep. NEANDC(J)-61U, p.94, Sep. 1979 2925 1451 128 31. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 2925 1451 129 32. W.Mannhart, Handbook on Nuclear Activation Cross Sections, 2925 1451 130 IAEA Technical Report series No.273, p.413, 1987 2925 1451 131 33. W.Mannhart, Validation of Differential Cross Sections with 2925 1451 132 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2925 1451 133 September 2002 2925 1451 134 34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2925 1451 135 Library, MAT=9228, MF=5, MT=18, eval. April 1989 2925 1451 136 35. W.Mannhart, Report INDC(NDS)-220/L, p.158, IAEA, Vienna, 1989 2925 1451 137 ***************************************************************** 2925 1451 138 2925 1451 139 1 451 142 12925 1451 140 3 107 63 12925 1451 141 33 107 66 12925 1451 142 2925 1 0 143 2925 0 0 144 2.90630+ 4 6.23890+ 1 0 0 0 02925 3107 145 1.71440+ 6 1.71440+ 6 0 0 1 1792925 3107 146 179 2 2925 3107 147 1.00000- 5 0.00000+ 0 2.53000- 2 0.00000+ 0 2.25000+ 6 0.00000+ 02925 3107 148 2.50000+ 6 1.11931- 6 2.60000+ 6 1.25919- 6 2.70000+ 6 1.77646- 62925 3107 149 2.80000+ 6 2.91589- 6 2.90000+ 6 4.96923- 6 3.00000+ 6 8.28312- 62925 3107 150 3.10000+ 6 1.32654- 5 3.20000+ 6 2.03923- 5 3.30000+ 6 3.02176- 52925 3107 151 3.40000+ 6 4.33838- 5 3.50000+ 6 6.06300- 5 3.60000+ 6 8.28008- 52925 3107 152 3.70000+ 6 1.10857- 4 3.80000+ 6 1.45884- 4 3.90000+ 6 1.89104- 42925 3107 153 4.00000+ 6 2.41873- 4 4.10000+ 6 3.05691- 4 4.20000+ 6 3.82201- 42925 3107 154 4.30000+ 6 4.73183- 4 4.40000+ 6 5.80541- 4 4.50000+ 6 7.06288- 42925 3107 155 4.60000+ 6 8.52512- 4 4.70000+ 6 1.02135- 3 4.80000+ 6 1.21494- 32925 3107 156 4.90000+ 6 1.43535- 3 5.00000+ 6 1.68454- 3 5.10000+ 6 1.96425- 32925 3107 157 5.20000+ 6 2.27598- 3 5.30000+ 6 2.62085- 3 5.40000+ 6 2.99958- 32925 3107 158 5.50000+ 6 3.41239- 3 5.60000+ 6 3.85896- 3 5.70000+ 6 4.33845- 32925 3107 159 5.80000+ 6 4.84943- 3 5.90000+ 6 5.38994- 3 6.00000+ 6 5.95755- 32925 3107 160 6.10000+ 6 6.54944- 3 6.20000+ 6 7.16246- 3 6.30000+ 6 7.79330- 32925 3107 161 6.40000+ 6 8.43854- 3 6.50000+ 6 9.09484- 3 6.60000+ 6 9.75896- 32925 3107 162 6.70000+ 6 1.04279- 2 6.80000+ 6 1.10990- 2 6.90000+ 6 1.17699- 22925 3107 163 7.00000+ 6 1.24387- 2 7.10000+ 6 1.31038- 2 7.20000+ 6 1.37641- 22925 3107 164 7.30000+ 6 1.44187- 2 7.40000+ 6 1.50671- 2 7.50000+ 6 1.57093- 22925 3107 165 7.60000+ 6 1.63453- 2 7.70000+ 6 1.69754- 2 7.80000+ 6 1.76001- 22925 3107 166 7.90000+ 6 1.82201- 2 8.00000+ 6 1.88361- 2 8.10000+ 6 1.94488- 22925 3107 167 8.20000+ 6 2.00593- 2 8.30000+ 6 2.06683- 2 8.40000+ 6 2.12767- 22925 3107 168 8.50000+ 6 2.18854- 2 8.60000+ 6 2.24953- 2 8.70000+ 6 2.31071- 22925 3107 169 8.80000+ 6 2.37216- 2 8.90000+ 6 2.43394- 2 9.00000+ 6 2.49612- 22925 3107 170 9.10000+ 6 2.55876- 2 9.20000+ 6 2.62189- 2 9.30000+ 6 2.68556- 22925 3107 171 9.40000+ 6 2.74980- 2 9.50000+ 6 2.81462- 2 9.60000+ 6 2.88004- 22925 3107 172 9.70000+ 6 2.94606- 2 9.80000+ 6 3.01266- 2 9.90000+ 6 3.07983- 22925 3107 173 1.00000+ 7 3.14753- 2 1.01000+ 7 3.21572- 2 1.02000+ 7 3.28433- 22925 3107 174 1.03000+ 7 3.35331- 2 1.04000+ 7 3.42257- 2 1.05000+ 7 3.49200- 22925 3107 175 1.06000+ 7 3.56151- 2 1.07000+ 7 3.63096- 2 1.08000+ 7 3.70022- 22925 3107 176 1.09000+ 7 3.76914- 2 1.10000+ 7 3.83754- 2 1.11000+ 7 3.90525- 22925 3107 177 1.12000+ 7 3.97207- 2 1.13000+ 7 4.03780- 2 1.14000+ 7 4.10221- 22925 3107 178 1.15000+ 7 4.16507- 2 1.16000+ 7 4.22616- 2 1.17000+ 7 4.28521- 22925 3107 179 1.18000+ 7 4.34198- 2 1.19000+ 7 4.39620- 2 1.20000+ 7 4.44763- 22925 3107 180 1.21000+ 7 4.49599- 2 1.22000+ 7 4.54103- 2 1.23000+ 7 4.58251- 22925 3107 181 1.24000+ 7 4.62018- 2 1.25000+ 7 4.65382- 2 1.26000+ 7 4.68322- 22925 3107 182 1.27000+ 7 4.70818- 2 1.28000+ 7 4.72852- 2 1.29000+ 7 4.74411- 22925 3107 183 1.30000+ 7 4.75482- 2 1.31000+ 7 4.76055- 2 1.32000+ 7 4.76124- 22925 3107 184 1.33000+ 7 4.75686- 2 1.34000+ 7 4.74740- 2 1.35000+ 7 4.73290- 22925 3107 185 1.36000+ 7 4.71342- 2 1.37000+ 7 4.68904- 2 1.38000+ 7 4.65990- 22925 3107 186 1.39000+ 7 4.62614- 2 1.40000+ 7 4.58794- 2 1.41000+ 7 4.54549- 22925 3107 187 1.42000+ 7 4.49902- 2 1.43000+ 7 4.44876- 2 1.44000+ 7 4.39496- 22925 3107 188 1.45000+ 7 4.33788- 2 1.46000+ 7 4.27780- 2 1.47000+ 7 4.21499- 22925 3107 189 1.48000+ 7 4.14972- 2 1.49000+ 7 4.08229- 2 1.50000+ 7 4.01296- 22925 3107 190 1.51000+ 7 3.94199- 2 1.52000+ 7 3.86966- 2 1.53000+ 7 3.79622- 22925 3107 191 1.54000+ 7 3.72191- 2 1.55000+ 7 3.64696- 2 1.56000+ 7 3.57159- 22925 3107 192 1.57000+ 7 3.49600- 2 1.58000+ 7 3.42039- 2 1.59000+ 7 3.34493- 22925 3107 193 1.60000+ 7 3.26979- 2 1.61000+ 7 3.19512- 2 1.62000+ 7 3.12105- 22925 3107 194 1.63000+ 7 3.04770- 2 1.64000+ 7 2.97519- 2 1.65000+ 7 2.90361- 22925 3107 195 1.66000+ 7 2.83304- 2 1.67000+ 7 2.76357- 2 1.68000+ 7 2.69525- 22925 3107 196 1.69000+ 7 2.62813- 2 1.70000+ 7 2.56227- 2 1.71000+ 7 2.49769- 22925 3107 197 1.72000+ 7 2.43443- 2 1.73000+ 7 2.37251- 2 1.74000+ 7 2.31195- 22925 3107 198 1.75000+ 7 2.25275- 2 1.76000+ 7 2.19492- 2 1.77000+ 7 2.13845- 22925 3107 199 1.78000+ 7 2.08335- 2 1.79000+ 7 2.02960- 2 1.80000+ 7 1.97720- 22925 3107 200 1.81000+ 7 1.92612- 2 1.82000+ 7 1.87636- 2 1.83000+ 7 1.82789- 22925 3107 201 1.84000+ 7 1.78069- 2 1.85000+ 7 1.73474- 2 1.86000+ 7 1.69002- 22925 3107 202 1.87000+ 7 1.64649- 2 1.88000+ 7 1.60415- 2 1.89000+ 7 1.56295- 22925 3107 203 1.90000+ 7 1.52288- 2 1.91000+ 7 1.48391- 2 1.92000+ 7 1.44601- 22925 3107 204 1.93000+ 7 1.40914- 2 1.94000+ 7 1.37330- 2 1.95000+ 7 1.33844- 22925 3107 205 1.96000+ 7 1.30454- 2 1.97000+ 7 1.27158- 2 1.98000+ 7 1.23953- 22925 3107 206 1.99000+ 7 1.20837- 2 2.00000+ 7 1.17806- 2 2925 3107 207 2925 3 0 208 2925 0 0 209 2.90630+ 4 6.23890+ 1 0 0 0 1292533107 210 0.00000+ 0 0.00000+ 0 0 107 0 1292533107 211 0.00000+ 0 0.00000+ 0 1 5 378 27292533107 212 1.00000- 5 2.25000+ 6 4.50000+ 6 5.00000+ 6 6.00000+ 6 7.00000+ 6292533107 213 8.00000+ 6 9.00000+ 6 1.00000+ 7 1.10000+ 7 1.20000+ 7 1.25000+ 7292533107 214 1.30000+ 7 1.35000+ 7 1.40000+ 7 1.45000+ 7 1.50000+ 7 1.55000+ 7292533107 215 1.60000+ 7 1.65000+ 7 1.70000+ 7 1.75000+ 7 1.80000+ 7 1.85000+ 7292533107 216 1.90000+ 7 1.95000+ 7 2.00000+ 7 0.00000+ 0 0.00000+ 0 0.00000+ 0292533107 217 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0292533107 218 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0292533107 219 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0292533107 220 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 8.28557- 2292533107 221 9.04974- 4 5.02511- 4 1.06958- 4 1.33609- 4 3.17206- 4 3.98727- 4292533107 222 3.31873- 4 1.70444- 4 4.22976- 5-2.26335- 5-5.89429- 5-6.36951- 5292533107 223 -4.10693- 5-8.82886- 7 4.44575- 5 8.30490- 5 1.05461- 4 1.05331- 4292533107 224 7.90017- 5 2.47578- 5-5.79594- 5-1.69173- 4-3.08809- 4-4.76976- 4292533107 225 2.67865- 3 1.12800- 3 5.07805- 4 3.22865- 4 4.28195- 4 5.10888- 4292533107 226 4.61371- 4 2.99521- 4 1.52733- 4 6.61877- 5 4.50111- 6-2.57750- 5292533107 227 -2.51840- 5-7.47354- 7 3.66022- 5 7.51389- 5 1.04680- 4 1.17645- 4292533107 228 1.09062- 4 7.60339- 5 1.70458- 5-6.86391- 5-1.81440- 4-3.21777- 4292533107 229 1.46034- 3 1.12763- 3 7.61250- 4 5.30922- 4 4.36235- 4 3.93687- 4292533107 230 3.40975- 4 2.77803- 4 2.21846- 4 1.60592- 4 1.00416- 4 4.80669- 5292533107 231 8.97773- 6-1.37736- 5-1.95445- 5-9.51298- 6 1.41699- 5 4.90940- 5292533107 232 9.30422- 5 1.44205- 4 2.01231- 4 2.63203- 4 3.29572- 4 1.43769- 3292533107 233 1.16835- 3 7.97367- 4 5.52208- 4 4.34811- 4 3.75885- 4 3.28899- 4292533107 234 2.82612- 4 2.23456- 4 1.55326- 4 8.56283- 5 2.31289- 5-2.43031- 5292533107 235 -5.11235- 5-5.44322- 5-3.34869- 5 1.10838- 5 7.80106- 5 1.65914- 4292533107 236 2.73622- 4 4.00332- 4 5.45685- 4 1.23342- 3 1.06581- 3 8.60394- 4292533107 237 6.65868- 4 4.80776- 4 3.46347- 4 2.59929- 4 1.80956- 4 1.13517- 4292533107 238 6.09945- 5 2.51603- 5 5.92182- 6 1.70762- 6 1.01560- 5 2.87600- 5292533107 239 5.52892- 5 8.79772- 5 1.25551- 4 1.67178- 4 2.12385- 4 2.60982- 4292533107 240 1.16964- 3 1.09769- 3 9.06241- 4 6.36939- 4 4.20119- 4 2.84899- 4292533107 241 1.71627- 4 8.82182- 5 3.76525- 5 1.75452- 5 2.14491- 5 4.10650- 5292533107 242 6.82635- 5 9.63105- 5 1.20268- 4 1.36850- 4 1.44054- 4 1.40750- 4292533107 243 1.26343- 4 1.00516- 4 1.15465- 3 1.03430- 3 7.80883- 4 5.43998- 4292533107 244 3.82808- 4 2.39315- 4 1.26280- 4 5.10223- 5 1.41159- 5 1.03206- 5292533107 245 3.10137- 5 6.67630- 5 1.09135- 4 1.51513- 4 1.89184- 4 2.19034- 4292533107 246 2.39135- 4 2.48349- 4 2.46020- 4 1.02032- 3 8.58365- 4 6.62486- 4292533107 247 5.06542- 4 3.50682- 4 2.10962- 4 1.00700- 4 2.76501- 5-6.76559- 6292533107 248 -6.19977- 6 2.28447- 5 7.31134- 5 1.37980- 4 2.12086- 4 2.91456- 4292533107 249 3.73342- 4 4.55982- 4 5.38345- 4 8.22344- 4 7.07312- 4 5.87317- 4292533107 250 4.47339- 4 3.03203- 4 1.71938- 4 6.78651- 5-4.62615- 8-2.86379- 5292533107 251 -1.93223- 5 2.38352- 5 9.58196- 5 1.91808- 4 3.07758- 4 4.40608- 4292533107 252 5.88259- 4 7.49480- 4 6.63137- 4 5.84025- 4 4.75880- 4 3.50856- 4292533107 253 2.25451- 4 1.15820- 4 3.43588- 5-1.18206- 5-2.05203- 5 7.00539- 6292533107 254 6.76700- 5 1.57829- 4 2.74083- 4 4.13667- 4 5.74605- 4 7.55714- 4292533107 255 5.38125- 4 4.59912- 4 3.60965- 4 2.54551- 4 1.55575- 4 7.65416- 5292533107 256 2.56785- 5 6.79273- 6 2.02888- 5 6.45209- 5 1.36963- 4 2.35009- 4292533107 257 3.56424- 4 4.99550- 4 6.63372- 4 4.17168- 4 3.51295- 4 2.74271- 4292533107 258 1.97205- 4 1.30849- 4 8.30638- 5 5.83109- 5 5.81836- 5 8.23610- 5292533107 259 1.29526- 4 1.98053- 4 2.86421- 4 3.93446- 4 5.18382- 4 3.24264- 4292533107 260 2.82983- 4 2.36778- 4 1.92390- 4 1.55926- 4 1.31485- 4 1.21237- 4292533107 261 1.25897- 4 1.45289- 4 1.78813- 4 2.25766- 4 2.85534- 4 3.57705- 4292533107 262 2.81789- 4 2.70558- 4 2.54726- 4 2.36886- 4 2.19908- 4 2.05895- 4292533107 263 1.96189- 4 1.91530- 4 1.92250- 4 1.98440- 4 2.10078- 4 2.27115- 4292533107 264 2.96715- 4 3.11447- 4 3.17485- 4 3.15037- 4 3.05588- 4 2.90648- 4292533107 265 2.71535- 4 2.49287- 4 2.24659- 4 1.98157- 4 1.70087- 4 3.58599- 4292533107 266 3.90205- 4 4.08411- 4 4.12666- 4 4.04216- 4 3.84563- 4 3.55140- 4292533107 267 3.17152- 4 2.71508- 4 2.18822- 4 4.51009- 4 4.93329- 4 5.20214- 4292533107 268 5.31019- 4 5.27039- 4 5.09756- 4 4.80563- 4 4.40608- 4 3.90744- 4292533107 269 5.67134- 4 6.23120- 4 6.65753- 4 6.94176- 4 7.09582- 4 7.13277- 4292533107 270 7.06470- 4 6.90175- 4 7.20328- 4 8.04419- 4 8.81314- 4 9.49578- 4292533107 271 1.01017- 3 1.06419- 3 1.11272- 3 9.47090- 4 1.08470- 3 1.22477- 3292533107 272 1.36506- 3 1.50640- 3 1.64988- 3 1.30515- 3 1.53111- 3 1.77231- 3292533107 273 2.02575- 3 2.29246- 3 1.87027- 3 2.22768- 3 2.61632- 3 3.03273- 3292533107 274 2.73431- 3 3.27428- 3 3.86539- 3 4.00534- 3 4.78790- 3 5.81005- 3292533107 275 292533 0 276 2925 0 0 277 0 0 0 278 -1 0 0 0