IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 26054.0000 53.4762000 0 0 34 102625 1451 1 0.0 0.0 0 0 0 62625 1451 2 1.00000000 60000000.0 0 0 10 20022625 1451 3 300.000000 0.0 1 0 470 82625 1451 4 26-Fe- 54 FEI/LANL EVAL-Jul13 K.I.Zolotarev 2625 1451 5 DIST-May14 Rev.4 May 2014 2625 1451 6 ----IRDF-2002 MATERIAL 2625 2625 1451 7 -----INCIDENT NEUTRON DATA 2625 1451 8 ------ENDF-6 FORMAT 2625 1451 9 ******************************************************************2625 1451 10 IAEA, Feb. 2014 (A. Trkov) 2625 1451 11 Extended cross sections and covariances from 20 to 60 MeV 2625 1451 12 by TENDL-2013, renormalised for continuity. 2625 1451 13 ******************************************************************2625 1451 14 ***************************************************************** 2625 1451 15 -----Russian Reactor Dosimetry File RRDF-2013 40204-13: 0.19 0.92 2625 1451 16 ***************************************************************** 2625 1451 17 Author of evaluation: K.I.Zolotarev 2625 1451 18 ***************************************************************** 2625 1451 19 MF=3 2625 1451 20 MT=103 - Fe-54(n,p)Mn-54 reaction 2625 1451 21 ------------------------------------- 2625 1451 22 Microscopic experimental data [1-41] were analyzed in the 2625 1451 23 process of preparation of input data base for the evaluation of 2625 1451 24 cross sections and relevant uncertainties for the Fe-54(n,p)Mn-54 2625 1451 25 reaction. During this procedure experimental data of works [1], 2625 1451 26 [5-7], [10-11], [13-19], [21-29], [31-34], [36-37], [39-41] were 2625 1451 27 corrected to the new standards for monitor reactions used in the 2625 1451 28 measurements and to the recommended decay data for Mn-54 [42]. 2625 1451 29 Special correction was applied to the experimental data [7], 2625 1451 30 [8] and [16]. 2625 1451 31 Corrected to the new standards experimental data of Lauber 2625 1451 32 and Malmskog [7] were renormalized to the integral of cross sec- 2625 1451 33 tion calculated from experimental data by Smith and Meadows [16] 2625 1451 34 in the overlapping energy range 2.31-3.81 MeV. 2625 1451 35 Original experimental data by Salisbury et al. [8] in the ene-2625 1451 36 rgy range 2.23-16.75 MeV were corrected to the preliminary evalu- 2625 1451 37 ated cross-section of 505.0 mb at 6.18 MeV. 2625 1451 38 Correction factors for the experimental data [7] and [8] were 2625 1451 39 equal to Fc= 1.41721 and Fc= 0.8938, respectively. 2625 1451 40 Data of Smith and Meadows [16] measured with using neutrons 2625 1451 41 from D(d,n)He3 reaction were renormalized to the results of this 2625 1451 42 experiment obtained with Li7(p,n)Be7 neutron source in the over- 2625 1451 43 lappins interval 5.407 - 5.438 MeV. D(d,n)He3 data in the energy 2625 1451 44 range 5.407 - 9.948 MeV were multiplied to the factor Fc=1.06614. 2625 1451 45 Data of March and Morton for total Fe-54(n,p)Mn-54 reaction 2625 1451 46 cross section at 13.5 MeV [2] were obtained by summation of measu-2625 1451 47 red compaund and direct processes cross sections. 2625 1451 48 Experimental data of Carroll and Smith [9] were taken only 2625 1451 49 for the incident neutron energies 3.55-6.02 MeV. Data measured at 2625 1451 50 15.7 MeV and 17.4 MeV energy points were rejected due to their 2625 1451 51 discrepancy with the main bulk of experimental data. 2625 1451 52 Excitation function for the Fe-54(n,p)Mn-54 reaction in the 2625 1451 53 energy region from threshold to 30 MeV was evaluated by means of 2625 1451 54 statistical analysis of experimental cross section data [1-2], 2625 1451 55 [6-14], [16-20], [22-26], [28-30], [32], [34], [36-41], and data 2625 1451 56 from theoretical model calculation, which were obtained by means 2625 1451 57 of modified GNASH code [43]. 2625 1451 58 Statistical analysis of input cross section data was carried 2625 1451 59 out by means of PADE-2 code [44]. Rational function was used as 2625 1451 60 the model function [45]. 2625 1451 61 U-235 thermal fission [46] and Cf-252 spontaneous fission 2625 1451 62 neutron spectra [47] averaged cross sections calculated from the 2625 1451 63 the evaluated Fe-54(n,p)Mn-54 excitation function are given below 2625 1451 64 in comparison with experimental data. 2625 1451 65 2625 1451 66 ----------------------+------------------+----------------------- 2625 1451 67 TYPE OF SPECTRUM | , mb (calc.) | , mb (measured) 2625 1451 68 ----------------------+------------------+----------------------- 2625 1451 69 U-235 neutron fission | 78.257 | 78.09 +- 1.17 2625 1451 70 ----------------------+------------------+----------------------- 2625 1451 71 CF-252 spont. fission | 86.578 | 86.62 +- 1.17 2625 1451 72 ----------------------+------------------+----------------------- 2625 1451 73 2625 1451 74 Experimental integral cross section 78.09+-1.17 mb for U-235 2625 1451 75 thermal fission neutron spectrum was determined as average weigh- 2625 1451 76 ted value from fission plate converter (FPC) measurements [48-50] 2625 1451 77 and [57-60]. Experimental integral cross section 86.62+-1.17 mb 2625 1451 78 for Cf-252 spontaneous fission neutron spectrum was obtained as 2625 1451 79 average weighted value from works [51-57]. 2625 1451 80 2625 1451 81 MT=33 2625 1451 82 MT=103 -(n,p) cross section cov. matrix 2625 1451 83 ---------------------------------------- 2625 1451 84 Uncertainties in the evaluated excitation function for the 2625 1451 85 reaction Fe-54(n,p)Mn-54 given in the form of relative covari- 2625 1451 86 ance matrix for the 45-neutron energy groups (LB=5). Covariance 2625 1451 87 matrix of uncertainties was calculated simultaneously with 2625 1451 88 recommended cross section data by means of PADE-2 code. 2625 1451 89 Eigenvalues of the 6-th digits relative covariance matrix 2625 1451 90 given in the 33-file are the following: 2625 1451 91 2625 1451 92 6.90511E-07 6.93234E-07 6.96921E-07 7.01168E-07 2625 1451 93 7.05292E-07 7.10306E-07 7.17869E-07 7.35083E-07 2625 1451 94 7.55545E-07 7.98141E-07 8.39606E-07 9.29082E-07 2625 1451 95 1.02500E-06 1.15143E-06 1.39468E-06 1.64886E-06 2625 1451 96 1.91803E-06 2.45934E-06 3.22329E-06 4.05437E-06 2625 1451 97 4.72864E-06 5.96803E-06 7.70244E-06 9.82298E-06 2625 1451 98 1.22946E-05 1.50778E-05 1.81318E-05 2.17691E-05 2625 1451 99 2.71222E-05 3.32873E-05 3.87824E-05 4.33509E-05 2625 1451 100 4.69942E-05 5.10461E-05 2.72934E-04 1.99654E-03 2625 1451 101 2.93121E-03 3.94152E-03 4.88506E-03 5.77641E-03 2625 1451 102 9.45929E-03 1.16711E-02 2.32610E-02 3.84256E-02 2625 1451 103 4.04256E-01 2625 1451 104 2625 1451 105 References: 2625 1451 106 1. D.L.Allan, J. Proc. Physical Society 70A (1957) 195 2625 1451 107 2. P.V.March, W.T.Morton, Philosophical Magazine 3 (1958) 143 2625 1451 108 3. D.L.Allan, Nucl. Phys. 10 (1959) 348 2625 1451 109 4. H.Pollehn, H.Neuert, Zeitschrift f. Naturforschung A 16 2625 1451 110 (1961) 227 2625 1451 111 5. J.J.Van Loef, Nucl. Phys. 24 (1961) 340-345 2625 1451 112 6. W.G.Cross, R.L.Clare, K.Morin, G.Slinn, N.M.Ahmed, K.Beg, 2625 1451 113 Progress Report EANDC(CAN)-16, p.1, January 1963 2625 1451 114 7. A.Lauber, S.G.Malmskog, Nucl. Phys. 73 (1965) 234 2625 1451 115 8. S.R.Salisbury, R.A.Chalmers, Phys. Rev. 140 (1965) 305-310 2625 1451 116 9. E.E.Carroll JR, G.G.Smith, Nucl. Sci. Eng. 22 (1965) 411-415 2625 1451 117 10. P.Venugopala Rao, R.W.Fink, Phys. Rev. 154 (1967) 1023-1028 2625 1451 118 11. R.C.Barrall, J.A.Holmes, M.Silbergeld, Report AFWL-TR-68-134, 2625 1451 119 Albuquerque, NM, March 1969 2625 1451 120 12. R.C.Barrall, M.Silbergeld, D.G.Gardner, Nucl. Phys. A 138 2625 1451 121 (1969) 387 2625 1451 122 13. A.Paulsen, R.Widera, Proc. of Conf. on Chemical Nucrear Data, 2625 1451 123 Measurements and Applications, University of Kent, Canterbury,2625 1451 124 20-22 September 1971, pp.129-137 2625 1451 125 14. S.M.Qaim, R.Woelfle, G.Stoecklin, Proc of Conf. on Chemical 2625 1451 126 Nuclear Data, Measurements and Applications, University of 2625 1451 127 Kent, Canterbury, 20-22 September 1971, p.121 2625 1451 128 15. J.J.Singh, J. Trans. Amer. Nucl. Soc. 15 (1972) 147 2625 1451 129 16. D.L.Smith, J.W.Meadows, Nucl. Sci. Eng. 58 (1975) 314 2625 1451 130 17. Chi-Fong Ai, Mien-Win Wu, Jen-Chang Chou, Nuclear Science 2625 1451 131 Journal (Taiwan) 14 (1977) 1-14 2625 1451 132 18. K.Fukuda et al., Progress Report NEANDC(J)-56/U, p.44, 1978 2625 1451 133 19. A.Paulsen et al., Nucl. Sci. Eng. 72 (1979) 113 2625 1451 134 20. O.I.Artem'ev et al., Atomnaja Energija (Sov.) 49 (1980) 195 2625 1451 135 21. M.Viennot et al., Progress Report MOH-5, p.10, 1982 2625 1451 136 22. B.M.Bahal, R.Pepelnik, Report GKSS-85-E-11, 1985 2625 1451 137 23. Fan Peiguo, Zhao Wenrong, Teng Dan, Lu Hanlin, Chinese J. of 2625 1451 138 Nuclear Physics 7 (1985) 242 2625 1451 139 24. I.Garlea et al., Revue Roumaine de Physique 31 (1986) 149 2625 1451 140 25. L.R.Greenwood, Report ASTM-STP-956, pp.743-749, 1987 2625 1451 141 26. Y.Ikeda et al., Report JAERI-1312, March 1988 2625 1451 142 27. K.Kobayashi, I.Kimura, Proc. of an Int. Conf. on Nuclear Data 2625 1451 143 for Science and Technology, 30 May - 3 June 1988, Mito, Japan,2625 1451 144 Saikon Publishing Co., LTD, pp.261-265, 1989; 2625 1451 145 I.Kimura, K.Kobayashi, Nucl. Sci. Eng. 106 (1990) 332 2625 1451 146 28. Lu Hanlin et al., Report INDC(CPR)-16, IAEA, Vienna, 1989 2625 1451 147 29. Y.Ikeda et al., Prorgess Report INDC(JPN)-142, p.11, IAEA, 2625 1451 148 Vienna, August 1990 2625 1451 149 30. S.K.Saraf et al., Nucl. Sci. Eng 107 (1991) 365-373 2625 1451 150 31. M.Viennot et al., Nucl. Sci. Eng. 108 (1991) 289-301 2625 1451 151 32. J.W.Meadows et al.,Proc. of an Int. Conf. on Nuclear Data for 2625 1451 152 Science and Technology, Juelich, FRG, 13-17 May 1991,Springer-2625 1451 153 Verlag, 1992, pp.288-290 2625 1451 154 33. A.Ercan et al., Proc. of an Int. Conf. on Nuclear Data for 2625 1451 155 Sci. and Technology, Juelich, FRG, 13-17 May 1991, Springer- 2625 1451 156 Verlag, 1992, p.376 2625 1451 157 34. I.Garlea et al., Revue Roumaine de Physique 37 (1992) 19-25 2625 1451 158 35. L.I.Klochkova, B.S.Kovrigin, V.N.Kuritsyn, VANT, Serija: 2625 1451 159 Yadernye Konstanty, v.1, p.27, 1992 2625 1451 160 36. A.Grallert et al., Report INDC(NDS)-286, IAEA, Vienna, p.131, 2625 1451 161 1993 2625 1451 162 37. J.W.Meadows, D.L.Smith, L.R.Greenwood, R.C.Haight, Y.Ikeda, 2625 1451 163 C.Konno, Annals of Nuclear Energy 23 (1996) 877-899 2625 1451 164 38. Huang Xiaolong, Lu Hanlin, Zhao Wenrong, Yu Weixiang, Han 2625 1451 165 Xiaogang, Report INDC(CPR)-045, IAEA, Vienna, October 1998 2625 1451 166 39. A.A.Filatenkov, S.V.Chuvaev, Preprit RI-252, M.: CNIIAtom- 2625 1451 167 inform, Moscow 1999 2625 1451 168 40. T.Shimizu et al., Annal. Nucl. Energy 31 (2004) 975 2625 1451 169 41. W.Mannhart, D.Schmidt, Report PTB-N-53, Braunschweig, 2007 2625 1451 170 42. Huo Junde, Huo Su, Nuclear Data Sheets 107 (2006) 1393 2625 1451 171 43. G.Y.Tertychnyj, E.L.Trykov, Modified version of GNASH code. 2625 1451 172 Private communication, IPPE, Obninsk, May 1999 2625 1451 173 44. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 2625 1451 174 45. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 2625 1451 175 st's. Meeting on Evaluation and Processing of Covariance Data,2625 1451 176 Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105 2625 1451 177 46. P.G.Young et al., Evaluated Neutron Data for Uranium-235, 2625 1451 178 ENDF/B-VII.1 Library, MAT=9228, MF=5, MT=18, eval. Sept. 2006 2625 1451 179 47. W.Mannhart, Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 2625 1451 180 48. J.W.Boldeman, Nuclear Energy A/B 18 (1964) 417 2625 1451 181 49. A.Fabry, J.P.Deworm, Progess Report EANDC(E)-57, p.69, 1965 2625 1451 182 50. A.M.Bresesti et al., Nucl. Sci. Eng. 40 (1970) 331 2625 1451 183 51. G.J.Kirouac et al., Knolls Atomic Power Laboratory Report 2625 1451 184 KAPL-P-4005, January 1974 2625 1451 185 52. J.Csikai, Z.Dezso, Proc. of 7th Int. Symp. on the Interaction 2625 1451 186 of Fast Neutrons with Nuclei, November 21-25, 1977 Gaussig, 2625 1451 187 GDR, Report ZFK-376, p.44, 1978 2625 1451 188 53. W.Mannhart, W.G.Alberts, Nucl. Sci. Eng. 69 (1979) 333-338 2625 1451 189 54. K.Kobayashi, I.Kimura, Report EUR-6813, p.1004, 1980 2625 1451 190 55. K.Kobayashi, I.Kimura, W.Mannhart, Nucl. Sci. Technology 19 2625 1451 191 (1982) 341-351 2625 1451 192 56. Z.Dezso, J.Csikai, Proc. of Int. Conf. on Nuclear Data for 2625 1451 193 Science and Technology, 6-10 September 1982, Antwerp, Holland 2625 1451 194 D.Reidel Publishing Company, 1983, pp.418-420 2625 1451 195 57. G.P.Lamaze et al., Proc. of Int. Conf. on Nuclear Data for 2625 1451 196 Science and Technology, 6-10 September 1982, Antwerp, Holland 2625 1451 197 D.Reidel Publishing Company, 1983, pp.425-428 2625 1451 198 58. W.Mannhart, Proc. of 5-th ASTM-EURATOM Symp. on Reactor Dosi- 2625 1451 199 metry. September 24-28, 1984, Geesthacht, FRG,J.P.Genthon and 2625 1451 200 H.Rettger (eds.), Brussels-Luxembourg 1985, Vol.2, pp.813-825 2625 1451 201 59. O.Horibe et al., Proc. of Conf.:50 Years with Nuclear Fission,2625 1451 202 Washington D.C., 25-28 April 1989, American Nuclear Society 2625 1451 203 Inc., 1989, Vol.2, p.927 2625 1451 204 60. K.Kobayashi, T.Kobayashi, Report KURRI-AR-25, p.21, 1992 2625 1451 205 ***************************************************************** 2625 1451 206 ------Russian Reactor Dosimetry File RRDF-2002 2625 1451 207 ***************************************************************** 2625 1451 208 Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko 2625 1451 209 MF=3 2625 1451 210 MT= 16 - (n,2n) cross section 2625 1451 211 MT=107 - (n,a) cross section 2625 1451 212 ------------------------------------- 2625 1451 213 Excitation function for the Fe-54(n,2n)Fe-53m+g reaction in 2625 1451 214 the energy region from threshold to 21 MeV was evaluated by means 2625 1451 215 of statistical analysis of experimental cross section data [1-16] 2625 1451 216 and data from GNASH [31-32] calculation. 2625 1451 217 All experimental data if it was possible were renormalized to 2625 1451 218 the new standards for monitor reactions cross sections and decay 2625 1451 219 data. Decay data for the iron-53 were taken from ref. [17]. Recom-2625 1451 220 mended cross sections for the reaction Al-27(n,p)Mg-27 used as a 2625 1451 221 monitor in the measurements [7-8], [11-14] and [16] were taken 2625 1451 222 from new evaluation [18]. 2625 1451 223 Special correction was done with experimental data [1], [6]. 2625 1451 224 Data of Terrel and Holm [1] measured at 16.89 and 17.89 MeV 2625 1451 225 have been corrected introducing the Fc= 0.5 coefficient, because 2625 1451 226 of authors used double decreased value for positron yield. 2625 1451 227 Data of Andreev et al.[6] were renormalized using preliminary 2625 1451 228 evaluated integral of cross section value in the neutron energy 2625 1451 229 range from 15.0 to 16.5 MeV. Renormalised experimental data of 2625 1451 230 Andreev et al. are well consistent with Ryves measurements [9-10] 2625 1451 231 and with new experimental data for Fe-54(n,2n)Fe-53m+g reaction 2625 1451 232 obtained by Fessler [16]. 2625 1451 233 Experimental data from ref.[19-27] were rejected due to their 2625 1451 234 discrepancy with the main bulk of experimental data [1-16] and 2625 1451 235 data from theoretical model calculation. 2625 1451 236 The final procedure of evaluation Fe54(n,2n)Fe53m+g excitati- 2625 1451 237 on function from threshold to 21 MeV has been carried out within 2625 1451 238 the framework of generalized least squares method. Rational func- 2625 1451 239 tion was used as model function [28]. 2625 1451 240 U-235 thermal fission [29] and Cf-252 spontaneous fission 2625 1451 241 neutron spectra [30] averaged cross sections calculated from the 2625 1451 242 evaluated Fe54(n,2n)Fe53m+g excitation function are the following:2625 1451 243 2625 1451 244 ---------------------------------------------- 2625 1451 245 TYPE OF SPECTRUM I , mb (calc.) 2625 1451 246 ---------------------------I------------------ 2625 1451 247 U-235 neutron fission I 1.2839E-3 2625 1451 248 CF-252 spontan. fission I 3.6219E-3 2625 1451 249 ---------------------------------------------- 2625 1451 250 2625 1451 251 MF=33 2625 1451 252 MT= 16 - (n,2n) cross section cov. matrix 2625 1451 253 ------------------------------------------ 2625 1451 254 Uncertainties in the evaluated excitation function for the 2625 1451 255 reaction Fe-54(n,2n)Fe-53m+g are given in the form of relative co-2625 1451 256 variance matrix for the 12-neutron energy groups (LB=5). Covari- 2625 1451 257 ance matrix of uncertainties was calculated simultaneously with 2625 1451 258 recommended cross section data by means of PADE-2 code [33]. 2625 1451 259 Eigenvalues of the 6-th digits relative covariance matrix 2625 1451 260 given in the 33-file are the following: 2625 1451 261 2625 1451 262 3.65349E-06 4.84130E-06 6.69851E-06 1.07852E-05 2625 1451 263 2.27150E-05 7.28051E-05 4.72794E-04 5.38548E-03 2625 1451 264 1.13987E-02 1.32443E-02 3.40784E-02 1.48451E-01 2625 1451 265 2625 1451 266 References : 2625 1451 267 1. J.Terrell, D.M.Holm Physical Review, v.109, p.2031, 1958 2625 1451 268 2. M.J.Depraz et al. Journal de Physique, v.21, p.377, May 1960 2625 1451 269 3. D.M.Chittenden et al. Physical Review, v.122, p.860, 1961 2625 1451 270 4. W.G.Cross et al. Prog. Report EANDC(CAN)-16, p., January 1963 2625 1451 271 3. W.G.Cross et al. Prog. Report EANDC(CAN)-16, p.1, Jan. 1963 2625 1451 272 5. S.R.Salisbury, R.A.Chalmers Phys. Rev., v.B140, p.305, 1965 2625 1451 273 6. M.F.Andreev, V.I.Serov Jadernaja Fizika (Sov.), v.7, n.4, 2625 1451 274 p.745, April 1968 2625 1451 275 7. S.M.Qaim Nuclear Physics, v.A185, p.614, May 1972 2625 1451 276 8. R.A.Sigg, P.K.Kuroda Inorg. Nucl. Chem., v.37, p.631, 1975 2625 1451 277 9. T.B.Ryves et al. J. Metrologia, v.14, n.3, p.127, June 1978 2625 1451 278 10. T.B.Ryves et al. J. of Physics, pt.G, v.4, p.1783, 1978 2625 1451 279 11. B.M.Bahal, R.Pepelnik Report GKSS-84-E-, 1984 ; 2625 1451 280 B.M.Bahal, R.Pepelnik Progress Report NEANDC(E)-252/U,(5), 2625 1451 281 p.28, June 1984 2625 1451 282 12. L.R.Greenwood, R.K.Smither Proc. of Intern. Conf. on Nuclear 2625 1451 283 Data for Basic and Applied Science, Santa Fe, New Mexico, USA,2625 1451 284 13-17 May 1985, v.1, p.163 2625 1451 285 13. T.Katoh et al. Report JAERI-M-89-083, 1989 2625 1451 286 14. M.Viennot et al. Nucl. Sci. Eng., v.108, p.289, July 1991 2625 1451 287 15. A.Ercan et al. Proc. of International Conference on Nuclear 2625 1451 288 Data for Science and Technology, 13-17 May 1991, Julich, FRG, 2625 1451 289 Springer-Verlag, 1992, p.376-377 2625 1451 290 16. A.Fessler Report JUL-3502, FZ Julich GmbH, Germany, 1998 2625 1451 291 17. E.Browne, R.B.Firestone Table of Radioactive Isotopes, 2625 1451 292 John Wiley & Sons, New York, 1986 ; 2625 1451 293 R.B.Firestone Table of Isotopes, Eighth edition, Vol. 1, 2625 1451 294 John Wiley & Sons, Inc., New York, 1995 2625 1451 295 18. K.I.Zolotarev Report INDC(CCP)-431, Distr.: J+R/EL, IAEA, 2625 1451 296 Vienna, August 2002 2625 1451 297 19. D.L.Allan J. Proc. Phys. Soc., v.70, p.195, 1956 2625 1451 298 20. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 2625 1451 299 21. H.Pollehn, H.Neuert Zeitschrift f. Naturforschung, sect.A, 2625 1451 300 v.16, p.227, 1961 2625 1451 301 22. C.Carles Comptes Rendus, v.257, p.659, July 1963 2625 1451 302 23. J.Csikai Report EANDC-50S, v.2, p.102, July 1965 2625 1451 303 24. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 2625 1451 304 25. J.Araminowicz, J.Dresler Rep.INR-1464, Swierk-Warsew,May 1973 2625 1451 305 26. M.Bormann et al. Zeitsch. f. Physik, sect.A, v.277, p.203, 2625 1451 306 June 1976 2625 1451 307 27. Zhou Muyao et al. Chinese J. of Nucl. Phys., v.9, p.34, 1987 2625 1451 308 28. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2625 1451 309 st's Meeting on Evaluation and Processing of Covariance Data, 2625 1451 310 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 2625 1451 311 29. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2625 1451 312 Library, MAT-9228, MF=5, MT=18, eval. April 1989 2625 1451 313 30. W.Mannhart Report IAEA-TECDOC-410, p.158, 1987 2625 1451 314 31. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 2625 1451 315 Model Code for Calculation of Cross Section and Emission 2625 1451 316 Spectra. Report LA-6947, Los Alamos, 1977 2625 1451 317 32. E.L.Trykov, G.Ya.Tertychnyi Private communication, IPPE, 2625 1451 318 Obninsk, May 1999 2625 1451 319 33. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 2625 1451 320 34. P.Venugopala Rao, R.W.Fink Phys. Rev., v.154, p.1023, 1967 2625 1451 321 35. S.M.Qaim et al. Conf. on Chemical Nuclear Data, Measurements 2625 1451 322 and Applicat., Univ. of Kent, Canterbury,20-22 September 1971,2625 1451 323 p.121 2625 1451 324 36. J.J.Singh Trans. Amer. Nucl. Soc., v.15, p.147, June 1972 2625 1451 325 37. G.N.Maslov et al. Sov. J. Yadernye Konstanty, v.9, p.50, 1972 2625 1451 326 38. K.Fukuda et al. Prog. Report NEANDC(J)-56/U, p.44, Sep. 1978 2625 1451 327 39. A.Paulsen et al. Nucl. Sci. Eng., v.72, v.1, p.113, 1979 2625 1451 328 40. O.I.Artem'ev et al. Atomnaja Energija (Sov.), v.49, no.3, 2625 1451 329 p.195, September 1980 2625 1451 330 41. L.R.Greenwood Progress Report DOE-ER-0046-21, p.15, May 1985 2625 1451 331 42. J.W.Meadows et al. Annals of Nuclear Energy, v.14, p.489, 2625 1451 332 September 1987 2625 1451 333 43. Y.Ikeda, C.Konno, K.Oishi et al. Report JAERI-1312, 1988 2625 1451 334 44. Lu Hanlin et al. Report INDC(CPR)-16, August 1989 2625 1451 335 45. S.K.Saraf et al. Nucl. Sci. Eng., v.107, p.365, April 1991 2625 1451 336 46. J.W.Meadows, W.Mannhart et.al. Proc. of Intern. Conference 2625 1451 337 on Nuclear Data for Science and Technology, 13-17 May 1991, 2625 1451 338 Julich, FRG, Springer-Verlag, 1992, p.288-290 2625 1451 339 47. A.Grallert et al. Report INDC(NDS)-286, p.193, IAEA, 1993 2625 1451 340 48. J.W.Meadows et al. Annals of Nuclear Energy, v.23, p.877, 2625 1451 341 July 1996 2625 1451 342 49. Lu Hanlin et al. Report INDC(CPR)-045, IAEA, Vienna, 1998 2625 1451 343 50. Y.M.Gledenov et al. Report INDC(CPR)-042, IAEA, Vienna, 1997 2625 1451 344 51. H.Braun, L.Nagy Radiochimica Acta, v.10, p.15, 1968 2625 1451 345 52. A.V.Bushuev et al. Atomnaja Energija (Sov.), v.63, no.3, 2625 1451 346 p.207, September 1987 2625 1451 347 53. O.Horibe et al. Proc. of Conference: 50 Years with Nuclear 2625 1451 348 Fission, Washington D.C., 25-28 April 1989, v.2, p.923 2625 1451 349 2625 1451 350 Author of evaluation: K.I.Zolotarev 2625 1451 351 MT=107 - (n,a) cross section 2625 1451 352 ------------------------------------- 2625 1451 353 Excitation function for the Fe-54(n,a)Cr-51 reaction in the 2625 1451 354 energy region from 3 MeV to 20 MeV was evaluated by means of 2625 1451 355 statistical analysis of experimental cross section data [1-21] 2625 1451 356 and data from GNASH [22-23] calculation. 2625 1451 357 All experimental data were renormalized to the new standards 2625 1451 358 for monitor reactions cross sections and decay data. Experimental 2625 1451 359 data of S.R.Salisbury and R.A.Chalmers [24] were rejected due to 2625 1451 360 their inconsistency with theoretical model calculations data in 2625 1451 361 the energy region 3-5 MeV. Data of Y.M.Gledenov et al. [25] at 2625 1451 362 7 MeV were rejected due to their very big discrepancy with measu- 2625 1451 363 rements [9,18,21] and data from theoretical model calculation. 2625 1451 364 The final procedure of evaluation Fe-54(n,a)Cr-51 excitation 2625 1451 365 function from 3 MeV to 20 MeV have been carried out within the 2625 1451 366 framework of generalized least squares method. Rational function 2625 1451 367 was used as a model function [26]. 2625 1451 368 Integral experimental data for U-235 neutron fission spectrum 2625 1451 369 [27-29] was used for testing evaluated Fe-54(n,a)Cr-51 excitation 2625 1451 370 function. The results of testing are given in Table 1. 2625 1451 371 Data for U-235 thermal fission neutron spectrum and Cf-252 2625 1451 372 spontaneous fission neutron spectrum were taken from ref.[30] and 2625 1451 373 [31], respectively. 2625 1451 374 Table 1. 2625 1451 375 ----------------------+-----------------+----------------------- 2625 1451 376 Type of spectrum | ,mb (calc.) | , mb (measured) 2625 1451 377 ----------------------+-----------------+----------------------- 2625 1451 378 U-235 neutron fission | 0.8419 | 0.790 +- 0.119 [27] 2625 1451 379 | | 0.850 +- 0.100 [28] 2625 1451 380 | | 0.891 +- 0.070 [29] 2625 1451 381 | | 0.850 +- 0.050 [* ] 2625 1451 382 ----------------------+-----------------+----------------------- 2625 1451 383 CF-252 spont. fission | 1.1131 | 2625 1451 384 ----------------------+-----------------+----------------------- 2625 1451 385 [*] - Averaged cross section value obtained from ref. [27-29] 2625 1451 386 2625 1451 387 MF=33 2625 1451 388 MT=107 - (n,a) cross section cov. matrix 2625 1451 389 ---------------------------------------- 2625 1451 390 Uncertainties in the evaluated excitation function for the 2625 1451 391 reaction Fe-54(n,a)Cr-51 are given in the form of relative covari-2625 1451 392 ance matrix for the 21-neutron energy groups (LB=5). Covariance 2625 1451 393 matrix of uncertainties was calculated simultaneously with 2625 1451 394 recommended cross section data by means of PADE-2 code [32]. 2625 1451 395 Eigenvalues of the 6-th digits relative covariance matrix 2625 1451 396 given in the 33-file are the following: 2625 1451 397 2625 1451 398 2.56136E-06 2.60754E-06 2.67487E-06 2.79431E-06 2625 1451 399 2.91036E-06 3.12841E-06 3.36732E-06 3.67713E-06 2625 1451 400 4.28447E-06 5.05230E-06 6.20130E-06 9.55522E-06 2625 1451 401 1.89432E-05 1.30102E-04 1.16270E-03 2.34052E-03 2625 1451 402 3.33633E-03 3.39619E-03 8.36607E-03 1.48685E-02 2625 1451 403 1.83812E-01 2625 1451 404 2625 1451 405 References: 2625 1451 406 1. D.M.Chittenden et al. Phys. Rev., v.122, n.3, p.860, May 1961 2625 1451 407 2. H.Pollehn, H.Neuert, Zeitschrift f. Naturforschung, sect.A, 2625 1451 408 v.16, p.227, 1961 2625 1451 409 3. W.G.Cross et al., Prog. Report EANDC(CAN)-16, p.1, Jan. 1963 2625 1451 410 4. P.Venugopala Rao, R.W.Fink, Phys. Rev., v.154, p.1023, 1967 2625 1451 411 5. S.M.Qaim et al., Conf. on Chemical Nuclear Data, Measurements 2625 1451 412 and Applicat., Univ. of Kent, Canterbury,20-22 September 1971,2625 1451 413 p.121 2625 1451 414 6. J.J.Singh Trans. Amer. Nucl. Soc., v.15, p.147, June 1972 2625 1451 415 7. G.N.Maslov et al. Sov. J. Yadernye Konstanty, v.9, p.50, 1972 2625 1451 416 8. K.Fukuda et al., Prog. Report NEANDC(J)-56/U, p.44, Sep. 1978 2625 1451 417 9. A.Paulsen et al., Nucl. Sci. Eng., v.72, v.1, p.113, 1979 2625 1451 418 10. O.I.Artem'ev et al., Atomnaja Energija (Sov.), v.49, no.3, 2625 1451 419 p.195, September 1980 2625 1451 420 11. B.M.Bahal, R.Pepelnik, Report GKSS-84-E-, 1984 ; 2625 1451 421 B.M.Bahal, R.Pepelnik, Progress Report NEANDC(E)-252/U,(5), 2625 1451 422 p.28, June 1984 2625 1451 423 12. L.R.Greenwood, Progress Report DOE-ER-0046-21, p.15, May 1985 2625 1451 424 13. J.W.Meadows et al., Annals of Nuclear Energy, v.14, p.489, 2625 1451 425 September 1987 2625 1451 426 14. Y.Ikeda, C.Konno, K.Oishi et al., Report JAERI-1312, 1988 2625 1451 427 15. Lu Hanlin et al., Report INDC(CPR)-16, August 1989 2625 1451 428 16. S.K.Saraf et al., Nucl. Sci. Eng., v.107, p.365, April 1991 2625 1451 429 17. A.Ercan et al., Proc. of International Conference on Nuclear 2625 1451 430 Data for Science and Technology, 13-17 May 1991, Julich, FRG, 2625 1451 431 Springer-Verlag, 1992, p.376-377 2625 1451 432 18. J.W.Meadows, W.Mannhart et.al., Proc. of Intern. Conference 2625 1451 433 on Nuclear Data for Science and Technology, 13-17 May 1991, 2625 1451 434 Julich, FRG, Springer-Verlag, 1992, p.288-290 2625 1451 435 19. A.Grallert et al., Report INDC(NDS)-286, p.193, IAEA, 1993 2625 1451 436 20. J.W.Meadows et al., Annals of Nuclear Energy, v.23, p.877, 2625 1451 437 July 1996 2625 1451 438 21. Lu Hanlin et al., Report INDC(CPR)-045, IAEA, Vienna, 1998 2625 1451 439 22. P.G.Young, E.D.Arthur, A Preequilibrium Statistical Nuclear 2625 1451 440 Model Code for Calculation of Cross Section and Emission 2625 1451 441 Spectra. Report LA-6947, Los Alamos, 1977 2625 1451 442 23. E.L.Trykov, G.Ya.Tertychnyi, Private communication, IPPE, 2625 1451 443 Obninsk, May 1999 2625 1451 444 24. S.R.Salisbury, R.A.Chalmers, Phys. Rev., v.B140, p.305, 1965 2625 1451 445 25. Y.M.Gledenov et al. Report INDC(CPR)-042, IAEA, Vienna, 1997 2625 1451 446 26. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 2625 1451 447 st's Meeting on Evaluation and Processing of Covariance Data, 2625 1451 448 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 2625 1451 449 27. H.Braun, L.Nagy, Radiochimica Acta, v.10, p.15, 1968 2625 1451 450 28. A.V.Bushuev et al., Atomnaja Energija (Sov.), v.63, no.3, 2625 1451 451 p.207, September 1987 2625 1451 452 29. O.Horibe et al., Proc. of Conference: 50 Years with Nuclear 2625 1451 453 Fission, Washington D.C., 25-28 April 1989, v.2, p.923 2625 1451 454 30. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2625 1451 455 Library, MAT=9228, MF=5, MT=18, eval. April 1989 2625 1451 456 31. W.Mannhart, Report IAEA-TECDOC-410, p.158, 1987 2625 1451 457 32. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 2625 1451 458 ***************************************************************** 2625 1451 459 The Q values and threshold energies were updated prior to pro- 2625 1451 460 cessing through the codes to comply with the values obtained 2625 1451 461 using the NNDC calculation program which is based on the 1995 2625 1451 462 Update to the Atomic mass Evaluation. 2625 1451 463 2625 1451 464 File 2 added to the pointwise file containing only the effective 2625 1451 465 scattering radius with no resonance parameters given. 2625 1451 466 Taken from ENDF/B-VI 2625 1451 467 ************************ C O N T E N T S *********************** 2625 1451 468 ***************** Program LINEAR (VERSION 2012-1) ***************2625 1451 469 For All Data Greater than 1.0000D-10 barns in Absolute Value 2625 1451 470 Data Linearized to Within an Accuracy of .100000000 per-cent 2625 1451 471 ***************** Program GROUPIE (VERSION 2012-1) **************2625 1451 472 Unshielded Group Averages Using 640 Groups 2625 1451 473 Weighting Spectrum: Flat (Constant) Spectrum 2625 1451 474 1 451 476 12625 1451 475 2 151 4 12625 1451 476 3 16 25 12625 1451 477 3 103 112 12625 1451 478 3 107 87 12625 1451 479 33 16 28 12625 1451 480 33 103 196 12625 1451 481 33 107 56 12625 1451 482 2625 1 0 483 2625 0 0 484 26054.0000 53.4760000 0 0 1 02625 2151 485 2.605400+4 1.000000+0 0 0 1 02625 2151 486 1.000000-5 7.000000+5 0 0 0 02625 2151 487 0.000000+0 5.480000-1 0 0 0 02625 2151 488 2625 2 0 489 2625 0 0 490 26054.0000 53.4762000 0 0 0 02625 3 16 491 -13378500.0-13378500.0 0 0 1 652625 3 16 492 65 1 2625 3 16 493 13600000.0 1.03647E-4 13700000.0 3.01866E-4 13800000.0 5.35999E-42625 3 16 494 13900000.0 8.84865E-4 14000000.0 .001354120 14100000.0 .0019488152625 3 16 495 14200000.0 .002673245 14300000.0 .003530825 14400000.0 .0045239552625 3 16 496 14500000.0 .005653915 14600000.0 .006920745 14700000.0 .0083231552625 3 16 497 14800000.0 .009858505 14900000.0 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18700000.0 .083139465 18800000.0 .083937067 18900000.0 .0846540002625 3 16 511 19000000.0 .085370933 19100000.0 .086008663 19200000.0 .0865671882625 3 16 512 19300000.0 .087125713 19400000.0 .087684238 19500000.0 .0881690762625 3 16 513 19600000.0 .088580229 19700000.0 .088991381 19800000.0 .0894025342625 3 16 514 19900000.0 .089702469 20000000.0 0.0 2625 3 16 515 2625 3 0 516 26054.0000 53.4762000 0 0 0 02625 3103 517 85260.0000 85260.0000 0 0 1 1992625 3103 518 199 1 2625 3103 519 690000.000 3.85392E-7 720000.000 2.31235E-6 760000.000 4.62470E-62625 3103 520 800000.000 7.14724E-6 840000.000 1.59914E-5 880000.000 4.06659E-52625 3103 521 920000.000 8.04350E-5 960000.000 1.35699E-4 1000000.00 2.83318E-42625 3103 522 1100000.00 5.67876E-4 1200000.00 9.69426E-4 1300000.00 .0015078452625 3103 523 1400000.00 .002220120 1500000.00 .003175685 1600000.00 .0045005602625 3103 524 1700000.00 .006408810 1800000.00 .009227450 1900000.00 .0133784002625 3103 525 2000000.00 .019269100 2100000.00 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