IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 29065.0000 64.3700000 0 0 41 12931 1451 1 0.0 0.0 0 0 0 62931 1451 2 1.00000000 60000000.0 0 0 10 22931 1451 3 300.000000 0.0 1 0 233 42931 1451 4 29-Cu- 65 FEI EVAL-Jun06 K.I.Zolotarev 2931 1451 5 DIST-Sep06 2931 1451 6 ----BROND-2 MATERIAL 2931 2931 1451 7 -----INCIDENT NEUTRON DATA 2931 1451 8 ------ENDF-6 FORMAT 2931 1451 9 ******************************************************************2931 1451 10 IAEA, June 2012 (A. Trkov) 2931 1451 11 Extended cross sections and covariances from 20 to 60 MeV 2931 1451 12 by TENDL-2011, renormalised for continuity. 2931 1451 13 ******************************************************************2931 1451 14 *** MF2 added *************************************************** 2931 1451 15 * Extension to the International Reactor Dosimetry Library * 2931 1451 16 * supported partially by the International Atomic Energy Agency * 2931 1451 17 * through IAEA research contract 13335. * 2931 1451 18 * Published as a technical report INDC(NDS)-0526 (2008). * 2931 1451 19 * Available online at * 2931 1451 20 * http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/ * 2931 1451 21 * indc-nds-0526.pdf * 2931 1451 22 ***************************************************************** 2931 1451 23 ------Russian Reactor Dosimetry File RRDF-2006 2931 1451 24 ***************************************************************** 2931 1451 25 Author of evaluation: K.I.Zolotarev 2931 1451 26 ***************************************************************** 2931 1451 27 MF=3 2931 1451 28 MT= 16 - (n,2n) cross section 2931 1451 29 ------------------------------------- 2931 1451 30 Microscopic experimental data [1-46] were analyzed in the 2931 1451 31 process of preparation of input data base for the evaluation of 2931 1451 32 cross sections and their uncertainty for the Cu-65(n,2n)Cu-64 2931 1451 33 reaction. During this procedure all experimental data if it was 2931 1451 34 possible were corrected to the new recommended cross section data 2931 1451 35 for monitor reactions used in the measurements and to the new re- 2931 1451 36 commended decay data from ref. [47] and [48]. 2931 1451 37 Excitation function for the Cu-65(n,2n)Cu-64 reaction in the 2931 1451 38 energy region from threshold to 20 MeV was evaluated by means of 2931 1451 39 statistical analysis of experimental cross section data [1-38]. 2931 1451 40 Carefully analysis of experimental cross section data for the 2931 1451 41 reaction Cu-65(n,2n)Cu-64 between 13 - 15 MeV show that the more 2931 1451 42 representative in this energy range are data measured by Mannhart 2931 1451 43 and Vonach [25], Ryves et al. [27], Ghanbary and Robertson [31], 2931 1451 44 Meadows et al. [32], Filatenkov and Chuvaev [37], Mannhart and 2931 1451 45 Schmidt [38]. Data of Prestwood and Bayhurst [4] measured relative2931 1451 46 Al-27(n,a)Na-24 reaction cross sections and experimental data [7],2931 1451 47 [10], [21], [22], [24], [30] corrected to the new standards are 2931 1451 48 agree well with these data. 2931 1451 49 The results of precise relative measurements of Vonach et al. 2931 1451 50 for the incident neutron energies 13.6-14.7 MeV [15] were norma- 2931 1451 51 lized to the absolute cross section value 955 mb at 14.70 MeV. 2931 1451 52 Cross section data of Cuzzocrea et al. obtained in the energy 2931 1451 53 interval 13.70 - 14.67 MeV relative absolute cross section of 2931 1451 54 919 mb at 14.11 MeV [16] were renormalized to a value 900.8 mb. 2931 1451 55 The Cu-65(n,2n)Cu-64 reaction cross sections at 14.11 MeV and 2931 1451 56 14.70 MeV were determined from preliminary evaluation carried out 2931 1451 57 on the basis of precise experimental data [25], [27], [31], [32], 2931 1451 58 [37] and [38]. 2931 1451 59 Special corrections was applied to the experimental data [2], 2931 1451 60 [4], [11], [12], [28], [29], [33] and [36]. 2931 1451 61 Experimental data of Mc Crary and Morgan [2], Paulsen and Lis-2931 1451 62 kien [11], Santry and Butler [12], Csikai [28], Winkler and Ryves 2931 1451 63 [29], Ikeda et al. [33] and Molla et al.[36] were renormalized to 2931 1451 64 the integral of cross section calculated from experimental data 2931 1451 65 of Filatenkov and Chuvaev [37] in the overlapping energy ranges. 2931 1451 66 Experimental data [2] were corrected to the factor Fc= 0.61795 . 2931 1451 67 After corrections to the new recommended cross sections for moni- 2931 1451 68 tor reactions and decay data for Cu-64 experimental data [11-12],2931 1451 69 [28], [29], [33] and [36] were multiplied to the factors 0.89950, 2931 1451 70 0.95979, 0.93453, 1.02965, 0.96037 and 0.94159, respectively. 2931 1451 71 Total uncertainty of 8.3 % was assigned to the cross section 2931 1451 72 data of Rayburn [6] taking into account the similar experimental 2931 1451 73 method used in the ref.[42]. Systematic errors were evaluated and 2931 1451 74 added to the experimental data [7], [18], [24l, [29]. Uncertainty 2931 1451 75 in the standard cross sections was added to the experimental data 2931 1451 76 [4] and [12]. 2931 1451 77 In the energy region above 15 MeV the more representative are 2931 1451 78 experimental data of Ryves et al. [27]. Cross sections given in 2931 1451 79 the Ref. [27] were obtained in two series measurements carried 2931 1451 80 out with different monitor reactions. The results of these measu- 2931 1451 81 rements are agree well in the all overlapping points in the inves-2931 1451 82 tigated energy range 14.67 - 18.95 MeV. 2931 1451 83 Data of Prestwood and Bayhurst [4] measured with using reac- 2931 1451 84 tion U-238(n,f) for neutron flux monitoring were renormalized at 2931 1451 85 16.5 MeV to the cross section value of 1072.6 mb determined from 2931 1451 86 experimental data of Ryves et al. [27]. 2931 1451 87 Experimental data for the Cu-65(n,2n)Cu-64 reaction given in 2931 1451 88 Refs.[6] and [8] were used partially. Data obtained in these works2931 1451 89 above 16 MeV were rejected due to systematical underestimation of 2931 1451 90 cross sections. 2931 1451 91 Cross section data given in the ref. [39-46] were rejected 2931 1451 92 completely due to their big discrepancy with the main bulk of ex- 2931 1451 93 perimental data. In the rejected experimental data [39-42], [45] 2931 1451 94 and [46] cross section values were measured only in a one energy 2931 1451 95 point in the interval 14 - 15 MeV. 2931 1451 96 Statistical analysis of input cross section data was carried 2931 1451 97 out by means of PADE-2 code [49]. Rational function was used as 2931 1451 98 the model function [50]. 2931 1451 99 Evaluated excitation function for the reaction Cu65(n,2n)Cu64 2931 1451 100 was tested with using integral experimental data [51] for Cf-252 2931 1451 101 spontaneous fission neutron spectrum. Calculated average cross 2931 1451 102 section values for U-235 thermal fission neutron spectrum [52] 2931 1451 103 and Cf-252 spontaneous fission neutron spectrum [53] in a compa- 2931 1451 104 rison with experimental data are given in the table 1. 2931 1451 105 Table 1 2931 1451 106 ================================================================= 2931 1451 107 TYPE OF SPECTRUM ,mb (calc.) , mb (measured) 2931 1451 108 ----------------------------------------------------------------- 2931 1451 109 U-235 neutron fission 0.33339 2931 1451 110 ----------------------------------------------------------------- 2931 1451 111 CF-252 spont. fission 0.65436 0.6582+- 0.0146 [51] 2931 1451 112 ================================================================= 2931 1451 113 2931 1451 114 MF=33 2931 1451 115 MT= 16 - (n,2n) cross section cov. matrix 2931 1451 116 ----------------------------------------- 2931 1451 117 Uncertainties in the evaluated excitation function for the 2931 1451 118 reaction Cu-65(n,2n)Cu-64 are given in the form of relative cova- 2931 1451 119 riance matrix for the 35-neutron energy groups (LB=5). Covariance 2931 1451 120 matrix of uncertainties was calculated simultaneously with 2931 1451 121 recommended cross section data by means of PADE-2 code [49]. 2931 1451 122 Eigenvalues of the 6-th digits relative covariance matrix 2931 1451 123 given in the 33-file are the following: 2931 1451 124 2931 1451 125 2.04728E-06 2.06457E-06 2.10040E-06 2.13452E-06 2931 1451 126 2.20189E-06 2.27085E-06 2.32645E-06 2.39031E-06 2931 1451 127 2.46534E-06 2.55291E-06 2.65581E-06 2.77928E-06 2931 1451 128 2.92594E-06 3.10543E-06 3.32520E-06 3.59791E-06 2931 1451 129 3.94655E-06 4.39463E-06 4.99206E-06 5.80794E-06 2931 1451 130 6.95579E-06 8.65847E-06 1.12921E-05 1.56717E-05 2931 1451 131 2.36510E-05 3.97544E-05 7.86225E-05 2.14266E-04 2931 1451 132 6.08499E-04 1.59686E-03 2.22254E-03 2.73248E-03 2931 1451 133 6.42193E-03 9.57466E-03 2.09712E-02 2931 1451 134 2931 1451 135 References : 2931 1451 136 1. A.Poularikas, R.W.Fink Phys. Rev., v.115, p.989, 1959 2931 1451 137 2. J.H.Mc Crary, I.L.Morgan Bull. American Phys. Soc., v.5, 2931 1451 138 p.246, April 1960 2931 1451 139 3. M.J.Depraz et al. Journal de Physique-Colloque, v.21, p.377, 2931 1451 140 May 1960 2931 1451 141 4. R.J.Prestwood B.P.Bayhurst Phys. Rev., v.121, p.1438, 2931 1451 142 March 1961 2931 1451 143 5. H.Pollehn, H.Neuert Zeitschrift f. Naturforschung, sec.A, 2931 1451 144 v.16, p.227, 1961 2931 1451 145 6. L.A.Rayburn Proc. of Conference on Direct Interactions and 2931 1451 146 Nuclear Reaction Mechanisms, Padua, 3-8 September 1962, p.322 2931 1451 147 7. R.N.Glover, E.Weigold Nucl. Phys., v.29, p.309, 1962 2931 1451 148 8. M.Bormann et al. Zeitsch. f. Physik, v.174, p.1, Feb. 1963 2931 1451 149 9. C.G.Bonazzola et al. Nucl. Phys., v.51, p.337, February 1964 2931 1451 150 10. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 2931 1451 151 11. A.Paulsen, H.Liskien Nukleonik, v.7, no.3, p.117, March 1965 2931 1451 152 12. D.C.Santry, J.P.Butler Can. J. Phys, v.44, p.1183, 1965 2931 1451 153 13. J.Csikai Report, EANDC-50S,(2), paper 102, July 1965 2931 1451 154 14. W.Nagel J. Nucl. Energy, v.20, p.475, June 1966 2931 1451 155 15. H.K.Vonach et al. Proc. of 2nd Conf. on Nuclear Cross-Sec- 2931 1451 156 tions and Technology, Washington DC, 4-7 March 1968, v.2, 2931 1451 157 p.885, NBS special publication 299 2931 1451 158 16. P.Cuzzocrea et al. Nuovo Cimento, Sec. B, v.54, p.53, 2931 1451 159 March 1968 2931 1451 160 17. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 2931 1451 161 18. M.Bormann, B.Lammers Progress Report, EANDC(E)-115U, 2931 1451 162 March 1969 ; 2931 1451 163 M.Bormann, B.Lammers Nucl. Phys., v.A130, p.195, June 1969 2931 1451 164 19. A.Chatterjee et al. Proc. of the 12th Nucl. Phys. and Solid 2931 1451 165 State Phys. Symposium, Roorkee, 28-31 December 1969, v.2, 2931 1451 166 p. 117, 1969 2931 1451 167 20. I.G.Clator Dssertation Abstracts, section B, v.30, p.2850, 2931 1451 168 December 1969 2931 1451 169 21. S.M.Qaim Nuclear Physics, v. A185, p.614, May 1972 2931 1451 170 22. R.Mogharrab, H.Neuert Atomkernenergie, v.19, p.107, 1972 2931 1451 171 23. J.C.Robertson, B.Audric, P.Kolkowski J. of Nuclear Energy, 2931 1451 172 v.27, p.531, August 1973 2931 1451 173 24. J.Araminowicz, J.Dresler Progress Report, INR-1464, p.14, 2931 1451 174 May 1973 2931 1451 175 25. W.Mannhart, H.Vonach Zeitschrift f. Physik, Sect. A, v.272, 2931 1451 176 p.279, March 1975 2931 1451 177 26. R.A.Sigg Dissertation Abstract, sec.B, v.37, p.2237, 2931 1451 178 November 1976 2931 1451 179 27. T.B.Ryves et al. J. Metrologia, v.14, n.3, p.127, June 1978 2931 1451 180 28. J.Csikai Proc. of International Conference Nuclear Data for 2931 1451 181 Science and Technology, 6 - 10 September 1982, Antwerp, 2931 1451 182 Holland, D.Reidel Publishing Company, p.414, 1983 2931 1451 183 29. G.Winkler, T.B.Ryves Annals of Nuclear Energy, v.10, no.11, 2931 1451 184 p.601, April 1983 2931 1451 185 30. P.N.Ngoc et al. Nukleonika, v.29, p.87, 1984 2931 1451 186 31. F.Ghanbari, J.C.Robertson Annals of Nucl. Energy, v.13, n.6, 2931 1451 187 pp.301-306, June 1986 2931 1451 188 32. J.W.Meadows, D.L.Smith, M.M.Bretscher, S.A.Cox Annals of 2931 1451 189 Nucl. Energy, v.14, p.489, September 1987 2931 1451 190 33. Y.Ikeda et al. Report JAERI-1312, March 1988 2931 1451 191 34. A.Ercan et.al. Proc. of an Intern. Conf. on Nuclear Data for 2931 1451 192 Science and Technology, 13-17 May 1991, Julich, FRG, Springer-2931 1451 193 Verlag, 1992, pp. 376-377 2931 1451 194 35. Y.Ikeda et al. J. Nuclear Science and Technology, v.30, n.9, 2931 1451 195 p.26, 1993 2931 1451 196 36. N.I.Molla et al. Proc. of an Int. Conf. on Nuclear Data for 2931 1451 197 Science and Technology, Gatlinburg, Tennessee, May 9-13, 1994,2931 1451 198 Vol. 2, pp.938-940 2931 1451 199 37. A.A.Filatenkov, S.V.Chuvaev Preprint RI-252, M.: Atominform, 2931 1451 200 May 1999 2931 1451 201 38. W.Mannhart, D.Schmidt Measurement of Neutron Cross Sections 2931 1451 202 between 8 and 14 MeV. Proc. of Int. Conf. on Nuclear Data for 2931 1451 203 Science and Technology, Santa Fe, New Mexico, USA, September 2931 1451 204 26 - October 1 2004, Part One, pp. 609-612 2931 1451 205 39. S.G.Forbes Phys. Rev., v.88, p.1309, December 1952 2931 1451 206 40. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31, p.267, 1953 2931 1451 207 41. E.Weigold Australian J. Phys., v.13, p.186, 1960 2931 1451 208 42. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 2931 1451 209 43. E.Weigold, R.N.Glover Nucl. Phys., v.32, p.106, 1962 2931 1451 210 44. M.Bormann, I.Riehle Zeitsch. f. Physik, v.207, p.64, 2931 1451 211 October 1967 2931 1451 212 45. D.Crumpton et al. J. Inorg. Nucl. Chem., v. 31, p.1, 2931 1451 213 January 1969 2931 1451 214 46. R.Spangler et al. J. Trans. Amer. Nucl. Soc., v.22, p.818, 2931 1451 215 November 1975 2931 1451 216 47. Decay Radiation Data Base, version 11/28/2005, 2931 1451 217 http://www.nds.iaea.org/nudat2/dec 2931 1451 218 48. R.B.Firestone Table of Isotopes, Eighth edition, Vol. 1, 2931 1451 219 John Wiley & Sons, Inc., New York, 1995 2931 1451 220 49. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 2931 1451 221 50. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2931 1451 222 st's Meeting on Evaluation and Processing of Covariance Data, 2931 1451 223 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 2931 1451 224 51. W.Mannhart Validation of Differential Cross Sections with 2931 1451 225 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2931 1451 226 September 2002 2931 1451 227 52. L.W.Weston et al. Evaluated Neutron Data for Uranium-235, 2931 1451 228 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 2931 1451 229 53. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 2931 1451 230 ***************************************************************** 2931 1451 231 ***************** Program LINEAR (VERSION 2012-1) ***************2931 1451 232 For All Data Greater than 1.0000D-10 barns in Absolute Value 2931 1451 233 Data Linearized to Within an Accuracy of .100000000 per-cent 2931 1451 234 ***************** Program GROUPIE (VERSION 2012-1) **************2931 1451 235 Unshielded Group Averages Using 640 Groups 2931 1451 236 Weighting Spectrum: Flat (Constant) Spectrum 2931 1451 237 1 451 230 12931 1451 238 2 151 4 12931 1451 239 3 16 75 12931 1451 240 33 16 128 12931 1451 241 2931 1 0 242 2931 0 0 243 29065.0000 64.3700000 0 0 1 02931 2151 244 2.906500+4 1.000000+0 0 0 1 02931 2151 245 1.000000-5 9.950000+4 0 0 0 02931 2151 246 1.500000+0 6.700000-1 0 0 0 02931 2151 247 2931 2 0 248 2931 0 0 249 29065.0000 64.3700000 0 0 0 02931 3 16 250 -9909811.00-9909811.00 0 0 1 1012931 3 16 251 101 1 2931 3 16 252 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