IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 28060.0000 59.4160000 0 0 41 12831 1451 1 0.0 0.0 0 0 0 62831 1451 2 1.00000000 60000000.0 0 0 10 22831 1451 3 300.000000 0.0 1 0 184 42831 1451 4 28-Ni- 60 FEI EVAL-Aug07 K.I.Zolotarev 2831 1451 5 DIST-Sep07 2831 1451 6 ----BROND-2 MATERIAL 2831 2831 1451 7 -----INCIDENT NEUTRON DATA 2831 1451 8 ------ENDF-6 FORMAT 2831 1451 9 ******************************************************************2831 1451 10 IAEA, June 2012 (A. Trkov) 2831 1451 11 Extended cross sections and covariances from 20 to 60 MeV 2831 1451 12 by TENDL-2011, renormalised for continuity. 2831 1451 13 ******************************************************************2831 1451 14 ***************************************************************** 2831 1451 15 * Extension to the International Reactor Dosimetry Library * 2831 1451 16 * supported partially by the International Atomic Energy Agency * 2831 1451 17 * through IAEA research contract 13335. * 2831 1451 18 * Published as a technical report INDC(NDS)-0526 (2008). * 2831 1451 19 * Available online at * 2831 1451 20 * http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/ * 2831 1451 21 * indc-nds-0526.pdf * 2831 1451 22 ***************************************************************** 2831 1451 23 ------Russian Reactor Dosimetry File RRDF-2007 2831 1451 24 ***************************************************************** 2831 1451 25 Author of evaluation: K.I.Zolotarev 2831 1451 26 ***************************************************************** 2831 1451 27 MF=3 2831 1451 28 MT=103 - Ni60(n,p)Co60m+g reaction 2831 1451 29 ------------------------------------- 2831 1451 30 Microscopic experimental data [1-32] were analyzed in the 2831 1451 31 process of preparation of input data base for the evaluation of 2831 1451 32 cross sections and their uncertainty for the Ni-60(n,p)Co-60m+g 2831 1451 33 reaction. During this procedure all experimental data if it was 2831 1451 34 possible were corrected to the new recommended cross section data 2831 1451 35 for monitor reactions used in the measurements and to the new re- 2831 1451 36 commended decay data from Ref. [33]. 2831 1451 37 Special correction was done with experimental data [2-6], [8], 2831 1451 38 [9], [11-13], [17], [19-22] and [24-25]. 2831 1451 39 Data of Vonach et al. [12] were renormalized to the experimen- 2831 1451 40 tal data of Wagner et al. [14] in the overlapping energy interval 2831 1451 41 7.71-12.00 MeV. Corrected preliminary to the new standards cross 2831 1451 42 sections from Ref. [12] were multiplied to the factor Fc= 1.11621.2831 1451 43 Experimental data [2-6], [8-9], [11], [13], [17], [19-22] and 2831 1451 44 [24-25] obtained by means of Ni-samples with natural isotopes com-2831 1451 45 position were corrected for contribution from Ni-61(n,x)Co-60m+g 2831 1451 46 reaction. Cross section data for the Ni-61(n,x)Co-60m+g reaction 2831 1451 47 were taken from Ref. [34]. After applied correction data of Wang 2831 1451 48 Yongchang et al. [13] were renormalized to the integral of experi-2831 1451 49 mental data of Konno et al. [18] in the overlapping energy range 2831 1451 50 13.64 - 14.80 MeV. Cross sections from Ref. [13] were decreased 2831 1451 51 to the factor Fc= 0.87085 . 2831 1451 52 Excitation function for the Ni-60(n,p)Co-60m+g reaction in the 2831 1451 53 energy region from threshold to 21 MeV was evaluated by means of 2831 1451 54 statistical analysis of experimental cross section data [1-25]. 2831 1451 55 Data of Viennot et al. [15] at 14.83 MeV and Huang Xiaolong et 2831 1451 56 al. [23] at 7.07 and 11.40 MeV were not taken into account in the 2831 1451 57 evaluation due to significant underestimation and overestimation 2831 1451 58 the Ni-60(n,p)Co-60m+g reaction cross sections, respectively. 2831 1451 59 Experimental cross section data [26-32] were rejected comple- 2831 1451 60 tely due to their discrepancy with the main bulk of experimental 2831 1451 61 data [1-25]. In the rejected experimental works [26-27], [30-32] 2831 1451 62 cross section values were measured only in a one energy point in 2831 1451 63 the interval 14 - 15 MeV. 2831 1451 64 Statistical analysis of input cross section data was carried 2831 1451 65 out by means of PADE-2 code [35]. Rational function was used as 2831 1451 66 the model function [36]. 2831 1451 67 Evaluated excitation function of the Ni-60(n,p)Co-60m+g react- 2831 1451 68 ion was tested by comparison with integral experimental data [37] 2831 1451 69 for U-235 thermal fission neutron spectrum. Calculated average 2831 1451 70 cross sections for U-235 thermal fission neutron spectrum [38] 2831 1451 71 and Cf-252 spontaneous fission neutron spectrum [39] are given in 2831 1451 72 the Table 1. 2831 1451 73 Table 1 2831 1451 74 ----------------------+-----------------+----------------------- 2831 1451 75 TYPE OF SPECTRUM | ,mb (calc.) | , mb (measured) 2831 1451 76 ----------------------+-----------------+----------------------- 2831 1451 77 U-235 neutron fission | 2.1810 | 2.180 +- 0.104 [37] 2831 1451 78 ----------------------+-----------------+----------------------- 2831 1451 79 Cf-252 spont. fission | 2.7988 | 2831 1451 80 ----------------------+-----------------+----------------------- 2831 1451 81 2831 1451 82 MT=33 2831 1451 83 MT=103 -(n,p) cross section cov. matrix 2831 1451 84 --------------------------------------- 2831 1451 85 Uncertainties in the evaluated excitation function for the 2831 1451 86 reaction Ni-60(n,p)Co-60m+g are given in the form of relative co- 2831 1451 87 variance matrix for the 35-neutron energy groups (LB=5). Covari- 2831 1451 88 ance matrix of uncertainties was calculated simultaneously with 2831 1451 89 recommended cross section data by means of PADE-2 code. 2831 1451 90 Eigenvalues of the 6-th digits relative covariance matrix 2831 1451 91 given in the 33-file are the following: 2831 1451 92 2831 1451 93 1.73704E-06 1.79002E-06 1.87221E-06 2.00249E-06 2831 1451 94 2.15991E-06 2.36667E-06 2.64302E-06 2.91385E-06 2831 1451 95 3.36594E-06 3.74685E-06 4.38254E-06 5.03985E-06 2831 1451 96 5.86891E-06 6.97586E-06 8.17859E-06 9.73493E-06 2831 1451 97 1.19698E-05 1.34917E-05 1.69430E-05 2.02914E-05 2831 1451 98 2.22877E-05 2.63835E-05 3.10218E-05 4.13754E-05 2831 1451 99 9.80006E-05 2.64611E-04 5.55947E-04 8.39901E-04 2831 1451 100 1.15624E-03 2.58009E-03 2.99923E-03 6.33064E-03 2831 1451 101 1.45176E-02 2.30044E-02 1.35417E-01 2831 1451 102 2831 1451 103 References: 2831 1451 104 1. P.V.March, W.T.Morton Philosophical Magazine, v.3,p.577, 1958 2831 1451 105 2. W.G.Cross, R.L.Clarke, K.Morin et al. Progress Report EANDC 2831 1451 106 (CAN)-16, p. 1, January 1963 2831 1451 107 3. V.N.Levkovskij et al. Jadernaja Fizika (Sov.), v. 10, no. 1, 2831 1451 108 p. 44, July 1969 2831 1451 109 4. G.N.Maslov, F.Nasyrov, N.F.Pashkin Yadernye Konstanty (YK-9),2831 1451 110 Obninsk report, p. 50, 1972 2831 1451 111 5. J.D.Hemingway J. Nucl. Energy, v. 27, p. 241, April 1973 2831 1451 112 6. H.Weigel,R.Michel,W.Herr Radiochimica Acta, v.22, p.11, 1975 2831 1451 113 7. K.Fukuda, K.Matsuo, S.Shirahama, I.Kumabe, Progress Report, 2831 1451 114 NEANDC(J)-56/U, p. 44, September 1978 2831 1451 115 8. B.M.Bahal, R.Pepelnik Report GKSS-84-E-, Geesthacht, 1984 2831 1451 116 9. N.I.Molla, M.M.Rahman, S.Khatun et al., Report INDC(BAN)-003, 2831 1451 117 September 1986 2831 1451 118 10. S.L.Graham, M.Ahmad, S.M.Grimes et al. Nucl. Sci. Eng., v.5, 2831 1451 119 p. 60, January 1987 2831 1451 120 11. L.R.Greenwood Progress Report, ASTM-STP-956, p. 743, 1987 2831 1451 121 12. H.Vonach, M.Wagner, R.C.Haight Report, NEANDC-259, p. 165, 2831 1451 122 September 1989 2831 1451 123 13. Wang Yongchang, Ren Zhongliang, Yuan Junqian et al. Chinese J.2831 1451 124 High Energy Phys. and Nucl. Phys., v.14, p.923, October 1990 2831 1451 125 14. M.Wagner, H.Vonach, R.C.Haight Proc. of an Int. Conference 2831 1451 126 on Nuclear Data for Science and Technology, Juelich, FRG, 2831 1451 127 13-17 May 1991, p. 358 2831 1451 128 15. M.Viennot et al. Nucl. Sci. Eng., v. 108, p. 289, July 1991 2831 1451 129 16. S.Sudar, J.Csikai, S.M.Qaim, G.Stoecklin Proc. of an Interna-2831 1451 130 tional Conference on Nuclear Data for Science and Technology, 2831 1451 131 Juelich, FRG, 13-17 May 1991, p. 291 2831 1451 132 17. Li Tingyan, Shi Zhaomin, Lu Hanlin et al., Chinese J. High 2831 1451 133 Energy Physics and Nuclear Physics, v. 16, n. 2, p. 151, 1992 2831 1451 134 18. C.Konno, Y.Ikeda, K.Oishi, K.Kawade, H.Yamamoto, H.Maekawa, 2831 1451 135 Report, JAERI-1329, October 1993 2831 1451 136 19. Lu Hanlin, Zhao Wenrong, Yu Weixiang Chinese J. of Nucl. 2831 1451 137 Phys., v. 16, no. 3, pp. 263-266, 1994 2831 1451 138 20. J.W.Meadows, D.L.Smith, L.R.Greenwood, R.C.Haight, Y.Ikeda, 2831 1451 139 C.Konno Report, INDC(NDS)-342, p.7, February 1996 2831 1451 140 21. R.Doczi, V.Semkova, A.Fenyvesi, N.Yamamuro, Cs.M.Buczko, 2831 1451 141 J.Csikai, Nucl. Sci. Eng., v. 129, pp. 164-174, June 1998 2831 1451 142 22. A.D.Majdeddin Measurement and analysis of excitation func- 2831 1451 143 tions for fast neutron induced reactions from threshold to 2831 1451 144 20 MeV. PHD dissertation, Inst. of Experimental Physics , 2831 1451 145 Kossuth University, Hungary, June 1998 2831 1451 146 23. Huang Xiaolong, Lu Hanlin, Zhao Wenrong et al., Report, 2831 1451 147 INDC(CPR)-045, IAEA, Vienna, October 1998 2831 1451 148 24. A.A.Filatenkov, S.V.Chuvaev, V.N.Aksenov et al. Report RI-252,2831 1451 149 St. Petersburg, May 1999 2831 1451 150 25. V.Semkova, V.Avrigeanu, T.Glodariu, A.J.M.Plompen, P.Reimer, 2831 1451 151 D.L.Smith, S.Sudar, A.Koning, R.Forrest Nucl. Phys., v. A730,2831 1451 152 p. 255, 2004 2831 1451 153 26. D.L.Allan Proc. Phys. Soc., sec.A, v. 70, p. 195, March 1957 2831 1451 154 27. D.L.Allan Nucl. Phys., v. 24, p. 274, April 1961 2831 1451 155 28. A.Paulsen, H.Liskien Nucleonik, v. 10, p. 91, July 1967 2831 1451 156 29. A.Paulsen, Zeitschrift fuer Physik, v.205, p.226, August 1967 2831 1451 157 30. S.M.Qaim, N.I.Molla, Nucl. Phys., v. A283, p. 269, 1977 2831 1451 158 31. E.W.Lees,B.H.Patrick,S.Lindley Report AERE-R-9390, March 1979 2831 1451 159 32. K.T.Osman, F.I.Habbani Report, INDC(SUD)-001, Distr. L, IAEA, 2831 1451 160 Vienna, October 1996 2831 1451 161 33. Decay Radiation Data Base, version February 6, 2007, 2831 1451 162 http://www.nds.iaea.org/nudat2/dec 2831 1451 163 34. K.I.Zolotarev Evaluation of excitation functions for the reac-2831 1451 164 tions Ni-61(n,x)Co-60m and Ni-61(n,x)Co-60m+g in the energy 2831 1451 165 region from threshold to 21 MeV. IPPE, Obninsk, August 2007 2831 1451 166 35. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 2831 1451 167 36. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2831 1451 168 st's Meeting on Evaluation and Processing of Covariance Data, 2831 1451 169 Oak Ridge, USA, 1992, OECD, Paris, 1993, p. 105 2831 1451 170 37. O.Horibe, H.Chatani, Y.Mizumoto, T.Kusakabe, Proc. of Conf.: 2831 1451 171 50 Years with Nuclear Fission, Washington D.C., 25 - 28 April 2831 1451 172 1989, American Nuclear Society Inc., 1989, v. 2, p. 927 2831 1451 173 38. L.W.Weston et al. Evaluated Neutron Data for Uranium-235, 2831 1451 174 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 2831 1451 175 39. W.Mannhart Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 2831 1451 176 ***************************************************************** 2831 1451 177 2831 1451 178 ***************** Program SIGMA1 (VERSION 2010-1) ***************2831 1451 179 Data Doppler Broadened to 300.000000 Kelvin 2831 1451 180 for All Data Greater than 1.0000E-10 barns in Absolute Value 2831 1451 181 Data Linearized to Within an Accuracy of .010000000 per-cent 2831 1451 182 ***************** Program LINEAR (VERSION 2012-1) ***************2831 1451 183 For All Data Greater than 1.0000D-10 barns in Absolute Value 2831 1451 184 Data Linearized to Within an Accuracy of .100000000 per-cent 2831 1451 185 ***************** Program GROUPIE (VERSION 2012-1) **************2831 1451 186 Unshielded Group Averages Using 640 Groups 2831 1451 187 Weighting Spectrum: Flat (Constant) Spectrum 2831 1451 188 1 451 181 12831 1451 189 2 151 4 12831 1451 190 3 103 66 12831 1451 191 33 103 128 12831 1451 192 2831 1 0 193 2831 0 0 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