IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 12024.0000 23.7790000 0 0 0 11225 1451 1 0.0 0.0 0 0 0 61225 1451 2 1.00000000 60000000.0 0 0 10 21225 1451 3 300.000000 0.0 1 0 195 41225 1451 4 12-Mg- 24 FEI EVAL-Nov07 K.Zolotarev 1225 1451 5 DIST-Dec07 1225 1451 6 ----ENDF/B-II MATERIAL 1225 1225 1451 7 -----INCIDENT NEUTRON DATA 1225 1451 8 ------ENDF-6 FORMAT 1225 1451 9 ******************************************************************1225 1451 10 IAEA, July 2011 (A. Trkov) 1225 1451 11 Extended cross sections and covariances from 20 to 60 MeV 1225 1451 12 by TENDL-2010, renormalised for continuity. 1225 1451 13 ******************************************************************1225 1451 14 *** MF2 added *************************************************** 1225 1451 15 * Extension to the International Reactor Dosimetry Library * 1225 1451 16 * supported partially by the International Atomic Energy Agency * 1225 1451 17 * through IAEA research contract 13335. * 1225 1451 18 * Published as a technical report INDC(NDS)-0526 (2008). * 1225 1451 19 * Available online at * 1225 1451 20 * http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/ * 1225 1451 21 * indc-nds-0526.pdf * 1225 1451 22 ***************************************************************** 1225 1451 23 ------Russian Reactor Dosimetry File RRDF-2007 1225 1451 24 ***************************************************************** 1225 1451 25 Author of evaluation: K.I.Zolotarev 1225 1451 26 ***************************************************************** 1225 1451 27 MF=3 1225 1451 28 MT=103 - Mg-24(n,p)Na-24m+g reaction 1225 1451 29 ------------------------------------- 1225 1451 30 Microscopic experimental data [1-37] were analyzed in the 1225 1451 31 process of preparation of input data base for the evaluation of 1225 1451 32 cross sections and their uncertainty for the Mg-24(n,p)Na-24m+g 1225 1451 33 reaction. During this procedure all experimental data if it was 1225 1451 34 possible were corrected to the new standars. 1225 1451 35 Special correction was done with experimental data [1], [4], 1225 1451 36 [6-8], [11-21], [24-28], [31], [33] and [37]. 1225 1451 37 Data of Tewes et al. [4] were renormalized to the experimental 1225 1451 38 data of Mannhart and Schmidt [30] at the neutron energy 10.1 MeV. 1225 1451 39 Experimental data [1], [6-8], [11-21], [24-28], [31], [33] and 1225 1451 40 [37] obtained by means of Mg-samples with natural isotopes compo- 1225 1451 41 sition were corrected for contribution from Mg-25(n,x)Na-24m+g 1225 1451 42 and Mg-26(n,t)Na-24m+g reactions. Cross section data for thise 1225 1451 43 reactions were taken from Ref. [38]. 1225 1451 44 Excitation function for the Mg-24(n,p)Na-24m+g reaction in the 1225 1451 45 energy region from threshold to 21 MeV was evaluated by means of 1225 1451 46 statistical analysis of experimental cross section data [1-30]. 1225 1451 47 Experimental cross section data [31-37] were rejected due to 1225 1451 48 their discrepancy with the main bulk of experimental data [1-30]. 1225 1451 49 Statistical analysis of input cross section data was carried 1225 1451 50 out by means of PADE-2 code [46]. Rational function was used as 1225 1451 51 the model function [47]. 1225 1451 52 Evaluated excitation function of the Mg-24(n,p)Na-24m+g reac-1225 1451 53 tion was tested by comparison with integral experimental data for 1225 1451 54 U-235 thermal fission and Cf-252 spontaneous fission neutron spec-1225 1451 55 tra. Calculated and measured average cross section values for 1225 1451 56 U-235 thermal fission neutron spectrum [48] and Cf-252 spontaneous1225 1451 57 fission neutron spectrum [49] are given in the Table 1. 1225 1451 58 Table 1 1225 1451 59 ----------------------+-----------------+----------------------- 1225 1451 60 Type of spectrum | ,mb (calc.) | , mb (measured) 1225 1451 61 ----------------------+-----------------+----------------------- 1225 1451 62 U-235 neutron fission | 1.5106 | 1.490 +- 0.027 [ *] 1225 1451 63 | | 1.451 +- 0.023 [45] 1225 1451 64 ----------------------+-----------------+----------------------- 1225 1451 65 CF-252 spont. fission | 2.1038 | 2.022 +- 0.061 [44] 1225 1451 66 | | 1.996 +- 0.049 [45] 1225 1451 67 ----------------------+-----------------+----------------------- 1225 1451 68 *- average weighted value obtained from experimental data [39-43] 1225 1451 69 1225 1451 70 MT=33 1225 1451 71 MT=103 -(n,p) cross section cov. matrix 1225 1451 72 --------------------------------------- 1225 1451 73 Uncertainties in the evaluated excitation function for the 1225 1451 74 reaction Mg-24(n,p)Na-24m+g are given in the form of relative co- 1225 1451 75 variance matrix for the 49-neutron energy groups (LB=5). Covari- 1225 1451 76 ance matrix of uncertainties was calculated simultaneously with 1225 1451 77 recommended cross section data by means of PADE-2 code. 1225 1451 78 Eigenvalues of the 6-th digits relative covariance matrix 1225 1451 79 given in the 33-file are the following: 1225 1451 80 1225 1451 81 1.55727E-08 1.67377E-08 1.91246E-08 2.28687E-08 1225 1451 82 2.38958E-08 2.47166E-08 2.52915E-08 2.57443E-08 1225 1451 83 2.66240E-08 2.88798E-08 3.03155E-08 3.58359E-08 1225 1451 84 4.31075E-08 5.20677E-08 6.20313E-08 7.12929E-08 1225 1451 85 7.97354E-08 3.86395E-07 2.10781E-06 6.80212E-06 1225 1451 86 2.42172E-05 2.97164E-05 3.88705E-05 5.73034E-05 1225 1451 87 7.75092E-05 8.22933E-05 9.42793E-05 1.11842E-04 1225 1451 88 1.20553E-04 1.34987E-04 1.44469E-04 1.74828E-04 1225 1451 89 1.82501E-04 2.15794E-04 2.22742E-04 2.57857E-04 1225 1451 90 2.63646E-04 2.75939E-04 3.40886E-04 3.66270E-04 1225 1451 91 5.30002E-04 5.44725E-04 6.89741E-04 7.78637E-04 1225 1451 92 8.72319E-04 1.47812E-03 2.89228E-03 4.66436E-03 1225 1451 93 4.77065E-02 1225 1451 94 1225 1451 95 References : 1225 1451 96 1. E.B.Paul, R.L.Clarke Can. J. Phys., v.31, p.267, 1953. 1225 1451 97 2. A.V.Cohen, P.H.White Nucl. Phys., v.1, p.73, February 1956 1225 1451 98 3. B.D.Kern, W.E.Thompson, J.M.Ferguson Nuclear Physics, v. 10, 1225 1451 99 pp. 226-334, May 1959 1225 1451 100 4. H.A.Tewes, A.A.Caretto, A.E.Miller, D.R.Nethaway Report, 1225 1451 101 UCRL-6028-T, June 1960 1225 1451 102 5. F.Gabbard, B.D.Kern Phys. Rev., v. 128, p. 1276, 1962 1225 1451 103 6. J.P.Butler, D.C.Santry Can. J. Phys., v. 41, p. 372, 1963 1225 1451 104 7. W.L.Imhof EXFOR 11526, USALOK, February 1964 1225 1451 105 8. A.Paulsen, H.Liskien J. of Nuclear Energy Parts AB, v. 19, 1225 1451 106 pp. 907-911, November 1965 1225 1451 107 9. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 1225 1451 108 10. H.Liskien, A.Paulsen Nukleonik, v.8, p.315, June 1966 1225 1451 109 11. J.M.Ferguson, J.C.Albergotti Nucl. Phys., Sec.A, v.98, p.65, 1225 1451 110 May 1967 1225 1451 111 12. A.Pasquarelli Nucl. Phys., v. A93, p. 218, March 1967 1225 1451 112 13. H.K.Vonach, W.G.Vonach, H.Muenzer, P.Schrammel 1225 1451 113 Proc. of 2nd Conf. on Nuclear Cross-Sections and Technology, 1225 1451 114 Washington DC, 4-7 March 1968, v.2, p.885, NBS special publi- 1225 1451 115 cation 299 1225 1451 116 14. R.C.Barrall, J.A.Holmes, M.Silbergeld Report, AFWL-TR-68-134,1225 1451 117 Kirtland, New Mexico, March 1969 1225 1451 118 15. I.G.Clator Dssertation Abstracts, section B, v. 30, p. 2850, 1225 1451 119 December 1969 1225 1451 120 16. W.Schantl Abstract communicated by Nuclear Data Section, 1225 1451 121 IAEA, Vienna, 1970 1225 1451 122 17. J.C.Robertson, B.Audric, P.Kolkowski, J. of Nuclear Energy, 1225 1451 123 v. 27, p. 531, August 1973 1225 1451 124 18. W.Mannhart, H.Vonach Zeitschrift f. Physik, Sect. A, v. 272, 1225 1451 125 p. 279, March 1975 1225 1451 126 19. M.Hyvoenen-Dabek, M.Tarvainen, P.Holmberg J., JRC, v. 46, 1225 1451 127 p. 357, 1978 1225 1451 128 20. A.Mostafa Nuclear Science and Applications, Ser. B: Physical 1225 1451 129 sciences, v. 9, p. 10, October 1976 1225 1451 130 21. J.P.Gupta, H.D.Bhardwai, R.Prasad Indian J. Pramana, v. 24, 1225 1451 131 p. 637, 1985 1225 1451 132 22. Y.Ikeda, C.Konno, K.Oishi et al. Report,JAERI-1312,March 1988 1225 1451 133 23. L.P.Geraldo, D.L.Smith, J.W.Meadows Annals of Nuclear Energy,1225 1451 134 v. 16, pp. 293-299, June 1989 1225 1451 135 24. P.Kolkowski, T.B.Ryves Nuclear Instruments and Methods in 1225 1451 136 Physics Research, Section A, v. 276, p. 539, 1989 1225 1451 137 25. Zhao Wenrong, Lu Hanlin, Yu Weixiang, Yuan Xialin Report, 1225 1451 138 INDC(CPR)-16, August 1989 1225 1451 139 26. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v. 106, p. 332, 1990 1225 1451 140 27. A.Ercan et.al. Proc. of an Intern. Conf. on Nuclear Data for 1225 1451 141 Science and Technology, 13-17 May 1991, Julich, FRG, Springer-1225 1451 142 Verlag, 1992, pp.376-377 1225 1451 143 28. M.Belgaid, M.Siad, M.Allab J. of Radioanalytical and Nuclear 1225 1451 144 Chemistry, Letters, v. 166, no. 6, p. 493, 1992 1225 1451 145 29. J.Janczyszyn, G.Domanska, W.Pohorecki, Annals of Nuclear 1225 1451 146 Energy, v. 26, p. 83, 1999 1225 1451 147 30. W.Mannhart, D.Schmidt, "Measurement of Neutron Activation 1225 1451 148 Cross Sections in the Energy Range from 8 to 15 MeV". Report, 1225 1451 149 PTB-N-53, Braunschweig, January 2007 1225 1451 150 31. L.Colli, G.M.Marcazzan, F.Merzari et al., Nuovo Cimento, v.17,1225 1451 151 p. 634, September 1960 1225 1451 152 32. M.J.Depraz, G.Legros, M.R.Sallin Journal de Physique-Colloque,1225 1451 153 v. 21, p. 377, May 1960 1225 1451 154 33. D.L.Allan Nucl. Phys., v. 24, p. 274, April 1961 1225 1451 155 34. J.M.F.Jeronymo, G.S.Mani, J.Olkowski et al., Nuclear Physics, 1225 1451 156 v. 47, no. 1, p. 157, July 1963 1225 1451 157 35. R.Prasad, D.C.Sarkar Nuovo Cimento, v.A3, n.3, p.467, 1971 1225 1451 158 36. N.I.Molla, M.M.Rahman, S.Khatum et al., Report, INDC(BAN)-003,1225 1451 159 September 1986 1225 1451 160 37. Tran Du Thhiep, Nguyen Van Do,Truong Thi An, Nguyen Ngoc Sona,1225 1451 161 Nucl. Phys., Vol. A722, p. 568, 2003 1225 1451 162 38. K.I.Zolotarev Evaluation of excitation functions for the reac-1225 1451 163 tions Mg-25(n,x)Na24m+g and Mg-26(n,t)Na-24m+g in the energy 1225 1451 164 region from threshold to 38 MeV. IPPE, Obninsk, October 2007 1225 1451 165 39. J.W.Boldeman J. Nuclear Energy, sect. AB, vol. 18, p. 417, 1225 1451 166 August 1964 1225 1451 167 40. A.Fabry, J.P.Deworm Progress Report EANDC(E)-57, p. 69, 1225 1451 168 February 1965 1225 1451 169 41. M.Najzer, J.Rant, H.Solinc, Proc. of 2nd IAEA Conference on 1225 1451 170 Nuclear Data for Reactors, Helsinki, Finland, 15-19 June 1970,1225 1451 171 42. M.Najzer, J.Rant, Report, IAEA-208, v.2, p.247, 1978 1225 1451 172 43. K.Kobayashi, I.Kimura Progress Report NEANDC(J)-61U, p.81, 1225 1451 173 September 1979 1225 1451 174 44. W.Mannhart, Proc. of an Int. Conference on Nuclear Data for 1225 1451 175 Science and Technology, 6-10 September 1982, Antwerp, Holland,1225 1451 176 D.Reidel Publishing Company, p.429 1225 1451 177 45. W.Mannhart, "Validation of Differential Cross Sections with 1225 1451 178 Integral Data", Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 1225 1451 179 September 2002 1225 1451 180 46. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 1225 1451 181 47. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 1225 1451 182 st's Meeting on Evaluation and Processing of Covariance Data, 1225 1451 183 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 1225 1451 184 48. L.W.Weston et al., Evaluated Neutron Data for Uranium-235, 1225 1451 185 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 1225 1451 186 49. W.Mannhart Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 1225 1451 187 **************************************************************** 1225 1451 188 1225 1451 189 ***************** Program SIGMA1 (VERSION 2010-1) ***************1225 1451 190 Data Doppler Broadened to 300.000000 Kelvin 1225 1451 191 for All Data Greater than 1.0000E-10 barns in Absolute Value 1225 1451 192 Data Linearized to Within an Accuracy of .010000000 per-cent 1225 1451 193 ***************** Program LINEAR (VERSION 2012-1) ***************1225 1451 194 For All Data Greater than 1.0000D-10 barns in Absolute Value 1225 1451 195 Data Linearized to Within an Accuracy of .100000000 per-cent 1225 1451 196 ***************** Program GROUPIE (VERSION 2012-1) **************1225 1451 197 Unshielded Group Averages Using 640 Groups 1225 1451 198 Weighting Spectrum: Flat (Constant) Spectrum 1225 1451 199 1 451 192 11225 1451 200 2 151 4 11225 1451 201 3 103 128 11225 1451 202 33 103 231 11225 1451 203 1225 1 0 204 1225 0 0 205 12024.0000 23.7790000 0 0 1 01225 2151 206 1.202400+4 1.000000+0 0 0 1 01225 2151 207 1.000000+0 2.000000+7 0 0 0 01225 2151 208 2.500000+0 3.150000-1 0 0 0 01225 2151 209 1225 2 0 210 1225 0 0 211 12024.0000 23.7790000 0 0 0 01225 3103 212 -4733500.00-4733500.00 0 0 1 1521225 3103 213 152 1 1225 3103 214 4900000.00 6.74400E-6 5000000.00 2.47500E-5 5100000.00 3.17410E-51225 3103 215 5200000.00 3.74910E-5 5300000.00 4.39999E-5 5400000.00 5.11250E-51225 3103 216 5500000.00 6.51250E-5 5600000.00 1.45000E-4 5700000.00 2.69999E-41225 3103 217 5800000.00 4.85357E-4 5900000.00 .001555201 6000000.00 .0030798651225 3103 218 6100000.00 .003976685 6200000.00 .004957239 6300000.00 .0067861091225 3103 219 6400000.00 .014912437 6500000.00 .029511500 6600000.00 .0427365011225 3103 220 6700000.00 .044019134 6800000.00 .036593630 6900000.00 .0338871761225 3103 221 7000000.00 .042290946 7100000.00 .050315558 7200000.00 .0529886291225 3103 222 7300000.00 .050504046 7400000.00 .048628208 7500000.00 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11300000.0 .168553750 11400000.0 .1741937501225 3103 236 11500000.0 .182479375 11600000.0 .188375250 11700000.0 .1789081251225 3103 237 11800000.0 .167094500 11900000.0 .162586875 12000000.0 .1620051251225 3103 238 12100000.0 .163727250 12200000.0 .169725125 12300000.0 .1875947501225 3103 239 12400000.0 .201916125 12500000.0 .200078750 12600000.0 .1862772501225 3103 240 12700000.0 .192710125 12800000.0 .190067000 12900000.0 .1917768751225 3103 241 13000000.0 .190053625 13100000.0 .188042875 13200000.0 .1921555001225 3103 242 13300000.0 .202150500 13400000.0 .211282625 13500000.0 .2069751251225 3103 243 13600000.0 .196587375 13700000.0 .189312375 13800000.0 .1878795001225 3103 244 13900000.0 .190737375 14000000.0 .192525250 14100000.0 .1929912501225 3103 245 14200000.0 .192264750 14300000.0 .189142000 14400000.0 .1842560001225 3103 246 14500000.0 .179407500 14600000.0 .175294000 14700000.0 .1718284741225 3103 247 14800000.0 .168800630 14900000.0 .166055808 15000000.0 .1635055001225 3103 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