IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 40090.0000 89.1324000 0 0 41 14025 1451 1 0.0 0.0 0 0 0 64025 1451 2 1.00000000 60000000.0 0 0 10 24025 1451 3 300.000000 0.0 1 0 187 44025 1451 4 40-Zr- 90 FEI EVAL-Nov08 K.I.Zolotarev 4025 1451 5 DIST-Dec08 4025 1451 6 ----BROND-2 MATERIAL 4025 4025 1451 7 -----INCIDENT NEUTRON DATA 4025 1451 8 ------ENDF-6 FORMAT 4025 1451 9 ******************************************************************4025 1451 10 IAEA, July 2011 (A. Trkov) 4025 1451 11 Extended cross sections and covariances from 20 to 60 MeV 4025 1451 12 by TENDL-2010, renormalised for continuity. 4025 1451 13 ******************************************************************4025 1451 14 ***MF2 ADDEd **************************************************** 4025 1451 15 * Extension to the International Reactor Dosimetry Library * 4025 1451 16 * supported partially by the International Atomic Energy Agency * 4025 1451 17 * through IAEA research contract 13335. * 4025 1451 18 * Unpublished, received on December 2008. * 4025 1451 19 ***************************************************************** 4025 1451 20 ------Russian Reactor Dosimetry File RRDF-2008 24110-20 C=0.30 4025 1451 21 ***************************************************************** 4025 1451 22 Author of evaluation: K.I.Zolotarev 4025 1451 23 ***************************************************************** 4025 1451 24 MF=3 4025 1451 25 MT= 16 - (n,2n) cross section 4025 1451 26 ------------------------------------- 4025 1451 27 Microscopic experimental data [1-43] were analyzed in the 4025 1451 28 process of preparation of input data base for the evaluation of 4025 1451 29 cross sections and their uncertainty for the Zr-90(n,2n)Zr-89m+g 4025 1451 30 reaction. During this procedure the experimental data of Refs. [1-4025 1451 31 5], [8-14], [16-21], and [23] were corrected to the new standards.4025 1451 32 Careful analysis of the experimental cross-section data for the4025 1451 33 Zr-90(n,2n)Zr-89m+g reaction between 13 and 15 MeV indicates that 4025 1451 34 the most reliable data in this energy range have been measured by 4025 1451 35 Pavlik et al. [9], Iguchi et al. [15], Ikeda et al. [22], and 4025 1451 36 Filatenkov and Chuvaev [23]. Experimental data of Refs. [2], [5], 4025 1451 37 [10-14], [17], [19] and [21] are in good agreement with tese data 4025 1451 38 after correction with respect to the new standards. 4025 1451 39 The results of precise measurements of Pavlik et al. in the 4025 1451 40 neutron energies range 13.435 - 14.830 MeV [9] and Filatenkov and 4025 1451 41 Chuvaev in the interval 13.56 - 14.78 MeV [23] were used as a re- 4025 1451 42 ference data for correction experimental data from Refs. [1], [6].4025 1451 43 Original experimental data of Nethaway obtained in the energy ran-4025 1451 44 ge 13.67 - 14.81 MeV [6] were renormalized to a factor Fc=0.94580.4025 1451 45 Data of Prestwood and Bayhurst measured in a wide energy region of4025 1451 46 12.13-19.76 MeV were renormalized to a factor Fc=0.94723 after a 4025 1451 47 special correction. 4025 1451 48 Special correction was applied to the data reported in Refs. 4025 1451 49 [1], [3] and [8]. Original experimental data of Prestwood and Bay-4025 1451 50 hurst [1], Rieder and Muenzer [3] and Bayhurst et al. [8] was not 4025 1451 51 corrected for 6.32% of metastable state decay to Y-88. The lack 4025 1451 52 part of cross-section was determined from the Zr-90(n,2n)Zr-89m 4025 1451 53 reaction excitation function evaluated in Ref. [44]. 4025 1451 54 Cross-section dat from Refs. [25-43] were rejected due to in- 4025 1451 55 consistency with the representative experimental data, furthermo- 4025 1451 56 re, data from Refs. [25-26], [30], [32-35], [38-39], [41], [43] 4025 1451 57 were only measured at one energy point between 14 - 15 MeV. 4025 1451 58 Excitation function for the Zr-90(n,2n)Zr-89m+g reaction in the4025 1451 59 energy range from threshold to 40 MeV was evaluated by means of 4025 1451 60 comprehensive statistical analysis of the experimental cross-sec- 4025 1451 61 tion data [1-24] and data obtained from theoretical model calcula-4025 1451 62 tion. 4025 1451 63 Statistical analysis of input cross section data was carried 4025 1451 64 out by means of PADE-2 code [45]. Rational function was used as 4025 1451 65 the model function [46]. 4025 1451 66 Evaluated excitation function of the Zr-90(n,2n)Zr-89m+g reac- 4025 1451 67 tion was compared with recommended integral experimental data [47]4025 1451 68 for U-235 thermal fission and Cf-252 spontaneous fission neutron 4025 1451 69 spectra. Calculated and measured average cross sections for U-235 4025 1451 70 thermal fission neutron spectrum [48] and Cf-252 spontaneous fis- 4025 1451 71 sion neutron spectrum [49] are given in the Table 1. 4025 1451 72 Table 1 4025 1451 73 ----------------------+-----------------+----------------------- 4025 1451 74 Type of spectrum | ,mb (calc.) | , mb (measured) 4025 1451 75 ----------------------+-----------------+----------------------- 4025 1451 76 U-235 neutron fission | 0.09344 | 0.1027 +- 0.0028 [47] 4025 1451 77 ----------------------+-----------------+----------------------- 4025 1451 78 CF-252 spont. fission | 0.21708 | 0.2210 +- 0.0064 [47] 4025 1451 79 ----------------------+-----------------+----------------------- 4025 1451 80 4025 1451 81 MF=33 4025 1451 82 MT= 16 - (n,2n) cross section cov. matrix 4025 1451 83 ----------------------------------------- 4025 1451 84 Uncertainties in the evaluated excitation function for the 4025 1451 85 reaction Zr-90(n,2n)Zr-89m+g are given in the form of relative co-4025 1451 86 variance matrix for the 46-neutron energy groups (LB=5). Covarian-4025 1451 87 ce matrix of uncertainties was calculated simultaneously with 4025 1451 88 recommended cross section data by means of PADE-2 code [45]. 4025 1451 89 Eigenvalues of the 6-th digits relative covariance matrix 4025 1451 90 given in the 33-file are the following: 4025 1451 91 4025 1451 92 6.23724E-07 6.27795E-07 6.33912E-07 6.44490E-07 4025 1451 93 6.59408E-07 6.75080E-07 6.98174E-07 7.30611E-07 4025 1451 94 7.60534E-07 8.03916E-07 8.71141E-07 9.20493E-07 4025 1451 95 9.81385E-07 1.03561E-06 1.10034E-06 1.16750E-06 4025 1451 96 1.22867E-06 1.32391E-06 1.45806E-06 1.60547E-06 4025 1451 97 1.71646E-06 1.94412E-06 2.27292E-06 2.47336E-06 4025 1451 98 2.94345E-06 3.56946E-06 4.01120E-06 5.32616E-06 4025 1451 99 5.91221E-06 8.04621E-06 9.54973E-06 1.16616E-05 4025 1451 100 1.56257E-05 1.90592E-05 2.13849E-05 5.41284E-05 4025 1451 101 2.94052E-04 4.57017E-04 7.37718E-04 3.06321E-03 4025 1451 102 3.25375E-03 6.52383E-03 8.70755E-03 2.59362E-02 4025 1451 103 9.20734E-02 4.86308E-01 4025 1451 104 4025 1451 105 References: 4025 1451 106 1. L.A.Rayburn, Phys. Rev., v. 122, p. 168, 1961 4025 1451 107 2. R.J.Prestwood, B.P.Bayhurst, Phys. Rev., v. 121, p.1438, 1961 4025 1451 108 3. R.Rieder, H.Muenzer, Acta Physica Austriaca, v.23, p.42, 1966 4025 1451 109 4. R.C.Barrall, J.A.Holmes, M.Silbergeld Report AFWL-TR-68-134, 4025 1451 110 Albuquerque, NM, March 1969 4025 1451 111 5. W.D.Lu, N.Ranakumar, R.W.Fink, Phys. Rev. C, v. 1, p. 350, 4025 1451 112 January 1970 4025 1451 113 6. D.R.Nethaway, Nucl. Phys. A, v. 190, p. 635, 1972 4025 1451 114 7. S.M.Qaim, G.Stoecklin, Proc. 8-th Symp. on Fusion Technology, 4025 1451 115 Noordwijkerhout, 17 - 21 June 1974 , Report EUR-5182E, p.939, 4025 1451 116 September 1974 4025 1451 117 8. B.P.Bayhurst et al., Phys. Rev. C, v.12, p.451, August 1975 4025 1451 118 9. A.Pavlik et al., J. of Physics, pt. G, v. 8, p. 1283, 1982 4025 1451 119 10. J.Csikai, Proc. of Int. Conf. on Nucl. 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A.Bari, Dissertation Abstracts B, v. 32, p. 5091, 1972 4025 1451 150 31. Y.Kanda Nucl. Phys. A, v. 185, p. 177, 1972 4025 1451 151 32. J.Araminowicz, J.Dresler, Progress Report, INR-1464, pp.14-18,4025 1451 152 May 1973 4025 1451 153 33. R.A.Sigg, Dissertation Abstracts B, v. 37, p. 2237, 1976 4025 1451 154 34. R.Spangler et al., Trans. Am. Nucl. Soc., v. 22, p. 818-819, 4025 1451 155 November 1975 4025 1451 156 35. S.L.Sothras, G.N.Salaita, J. Inorg. Nucl. Chemistry, v. 40, 4025 1451 157 p. 585, 1978 4025 1451 158 36. A.Chiadli et al., Proc. of Int. Conf. on Nucl. Data for Sci. 4025 1451 159 and Technology, 6-10 September 1982, Antwerp, Belgium, D.Rei- 4025 1451 160 del Publishing Company, p. 404, 1983 4025 1451 161 37. A.Chiadli, G.Paic, Progress Report MOH-5, p. 13, Rabat 1982 4025 1451 162 38. I.Garlea et al. Proc. of the 14-th Intern. Symp. on Nuclear 4025 1451 163 Physics, Gaussig, GDR, 19-23 November 1984 , Report ZFK-562, 4025 1451 164 p. 126, July 1985 4025 1451 165 39. I.F.Goncalves et al., Appl. Radiat. Isot., v. 38, p.989, 1987 4025 1451 166 40. S.I.Bhuiyan, EXFOR 30936.002, September 1989 4025 1451 167 41. K.T.Osman, F.I.Habbani, Report INDC(SUD)-001, IAEA, Vienna, 4025 1451 168 October 1996 4025 1451 169 42. M.I.Majah et al., Appl. Radiat. Isot., v. 54, p. 655, 2001 4025 1451 170 43. Tran Due Thiep et al., Nucl. Phys. A, v. 722, p. 568, 2003 4025 1451 171 44. K.I.Zolotarev Evaluation of the Zr90(n,2n)Z90m reaction exci-4025 1451 172 tation function in the energy range from thresold to 30 MeV. 4025 1451 173 IPPE, Obninsk, October, 2008 4025 1451 174 45. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 4025 1451 175 46. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 4025 1451 176 st's Meeting on Evaluation and Processing of Covariance Data, 4025 1451 177 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 4025 1451 178 47. W.Mannhart Validation of Differential Cross Sections with 4025 1451 179 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 4025 1451 180 September 2002 4025 1451 181 48. L.W.Weston et al., Evaluated Neutron Data for Uranium-235, 4025 1451 182 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 4025 1451 183 49. W.Mannhart Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 4025 1451 184 ***************************************************************** 4025 1451 185 ***************** Program LINEAR (VERSION 2012-1) ***************4025 1451 186 For All Data Greater than 1.0000D-10 barns in Absolute Value 4025 1451 187 Data Linearized to Within an Accuracy of .100000000 per-cent 4025 1451 188 ***************** Program GROUPIE (VERSION 2012-1) **************4025 1451 189 Unshielded Group Averages Using 640 Groups 4025 1451 190 Weighting Spectrum: Flat (Constant) Spectrum 4025 1451 191 1 451 184 14025 1451 192 2 151 4 14025 1451 193 3 16 43 14025 1451 194 33 16 206 14025 1451 195 4025 1 0 196 4025 0 0 197 40090.0000 89.1324000 0 0 1 04025 2151 198 4.009000+4 1.000000+0 0 0 1 04025 2151 199 1.000000+0 2.000000+7 0 0 0 04025 2151 200 0.000000+0 7.100000-1 0 0 0 04025 2151 201 4025 2 0 202 4025 0 0 203 40090.0000 89.1324000 0 0 0 04025 3 16 204 -11969700.0-11969700.0 0 0 1 804025 3 16 205 80 1 4025 3 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