IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 26056.0000 55.4544000 0 0 34 102631 1451 1 0.0 0.0 0 0 0 62631 1451 2 1.00000000 60000000.0 0 0 10 20022631 1451 3 300.000000 0.0 1 0 247 42631 1451 4 26-Fe- 56 FEI EVAL-Oct02 K.I.Zolotarev 2631 1451 5 DIST-Feb2004 2631 1451 6 ----IRDF-2002 MATERIAL 2631 2631 1451 7 -----INCIDENT NEUTRON DATA 2631 1451 8 ------ENDF-6 FORMAT 2631 1451 9 ******************************************************************2631 1451 10 IAEA, June 2012 (A. Trkov) 2631 1451 11 Extended cross sections and covariances from 20 to 60 MeV 2631 1451 12 by TENDL-2011, renormalised for continuity. 2631 1451 13 ******************************************************************2631 1451 14 ***************************************************************** 2631 1451 15 26-FE- 56 FEI EVAL-Oct02 K.I.Zolotarev 2631 1451 16 DIST-Nov03 20031105 2631 1451 17 ----BROND-3 MATERIAL 2631 Revision 2 2631 1451 18 -----INCIDENT NEUTRON DATA 2631 1451 19 ------ENDF-6 FORMAT 2631 1451 20 ------Russian Reactor Dosimetry File RRDF-2002 2631 1451 21 ***************************************************************** 2631 1451 22 Author of evaluation: K.I.Zolotarev 2631 1451 23 ***************************************************************** 2631 1451 24 MF=3 2631 1451 25 MT=103 -(n,p) cross section 2631 1451 26 ------------------------------------- 2631 1451 27 Excitation function for the Fe-56(n,p)Mn-56 reaction in the 2631 1451 28 energy region from threshold to 20 MeV was evaluated by means of 2631 1451 29 statistical analysis of experimental cross section data [1-40]. 2631 1451 30 The energy dependence of cross-section from 4.0 MeV to the 2631 1451 31 threshold was extrapolated with L=0 penetrability function for 2631 1451 32 the outgoing p + Mn-56 channel [41]. 2631 1451 33 Analised microscopic experimental data [1-40], [42-69] were 2631 1451 34 renormalized if it were possible to the new recommended standards 2631 1451 35 for monitor reaction cross sections and decay data. 2631 1451 36 Special correction was done with experimental data [2],[9-10] 2631 1451 37 and [17]. Experimental data of Terrell and Holm [2] corresponding 2631 1451 38 to neutron energies 6.54 MeV,7.41 MeV, 8.21 MeV were renormalized 2631 1451 39 to the preliminary evaluated cross section value at En=8.2 MeV. 2631 1451 40 Data of Liskien and Paulsen [9] measured in the energy range 2631 1451 41 12.60 - 19.58 MeV were corrected to the preliminary evaluated 2631 1451 42 integral of cross section in the energy interval 14-15 MeV. Data 2631 1451 43 obtained by Liskien and Paulsen in the energy range 6.06-8.20 MeV 2631 1451 44 [10] were renormalized to the preliminary evaluated cross section 2631 1451 45 value at 8.0 MeV. The correction factors for the experimental 2631 1451 46 data [2], [9] and [10] were Fc=1.23487, Fc=1.09674 and Fc=1.05835,2631 1451 47 respectively. Data of Smith and Meadows [17] obtained in the expe-2631 1451 48 riment with neutrons from D(d,n)He3 reaction in the energy range 2631 1451 49 6.486 - 9.945 MeV were renormalized to the preliminary evaluated 2631 1451 50 cross section value at 9.945 MeV. The correction factor for this 2631 1451 51 data was Fc=1.14066 . 2631 1451 52 Experimental information about Fe-56(n,p)Mn-56 reaction exci- 2631 1451 53 tation function are given in the ref. [13],[21],[23] in the form 2631 1451 54 of cross section ratios to monitor reactions. The results of pre- 2631 1451 55 cise relative measurements of Vonach et al. [13] in the energy 2631 1451 56 range 13.6-14.7 MeV were normalized to the preliminary evaluated 2631 1451 57 absolute cross section value 107.13 mb for Fe-56(n,p)Mn-56 reac- 2631 1451 58 tion at 14.7 MeV point. Raics et al. [21] and Antov et al. [23] 2631 1451 59 measured ratios of Fe-56(n,p)Mn-56 cross section to U-238(n,f) 2631 1451 60 and Al-27(n,a)Na-24 reactions cross section. Recommended absolute 2631 1451 61 cross section data for U-238(n,f) and Al-27(n,a)Na-24 reactions 2631 1451 62 were taken from ref. [70] and [71], respectively. 2631 1451 63 Experimental data from refs.[5] and [11] were used partially. 2631 1451 64 It were used only data obtained at 14.5 MeV [5] and in the energy 2631 1451 65 range 3.95 - 10.0 MeV [11]. Cross et al. data [5] for the neutron 2631 1451 66 energies 13.78 MeV, 14.07 MeV and 14.73 MeV were rejected due 2631 1451 67 to their systematically underestimation Fe-56(n,p)Mn-56 cross 2631 1451 68 section. The result of Grundl measurements at 14.1 MeV [11] was 2631 1451 69 not taken into account due to a very overestimated cross section 2631 1451 70 value obtained for this energy point. 2631 1451 71 Experimental cross section data [42-69] were rejected due to 2631 1451 72 their discrepancy with the main bulk of experimental data [1-40]. 2631 1451 73 In the rejected experiments [42-51], [53], [56-58], [60-62], 2631 1451 74 [64-67] and [69] the cross section values were measured only in a 2631 1451 75 one energy point in the interval 14 - 15 MeV. 2631 1451 76 Statistical analysis of input cross section data was carried 2631 1451 77 out by means of PADE-2 code [72]. Rational function was used as 2631 1451 78 the model function [73]. 2631 1451 79 U-235 thermal fission [74] and Cf-252 spontaneous fission 2631 1451 80 neutron spectra [75] averaged cross-sections calculated from the 2631 1451 81 evaluated Fe-56(n,p)Mn-56 excitation function are the following: 2631 1451 82 2631 1451 83 ---------------------------------------------------------------- 2631 1451 84 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 2631 1451 85 ---------------------------------------------------------------- 2631 1451 86 U-235 neutron fission I 1.0997 I 1.09 +- 0.04 [76] 2631 1451 87 I I 1.13 +- 0.07 [77] 2631 1451 88 I I 1.083 +- 0.017 [78] 2631 1451 89 ---------------------------------------------------------------- 2631 1451 90 Cf-252 spont. fission I 1.4626 I 1.471 +- 0.025 [79] 2631 1451 91 I I 1.465 +- 0.026 [80] 2631 1451 92 ---------------------------------------------------------------- 2631 1451 93 2631 1451 94 MT=33 2631 1451 95 MT=103 -(n,p) cross section cov. matrix 2631 1451 96 --------------------------------------- 2631 1451 97 Uncertainties in the evaluated excitation function for the 2631 1451 98 reaction Fe-56(n,p)Mn-56 are given in the form of relative covari-2631 1451 99 ance matrix for the 25-neutron energy groups (LB=5). Covariance 2631 1451 100 matrix of uncertainties was calculated simultaneously with 2631 1451 101 recommended cross section data by means of PADE-2 code. 2631 1451 102 Eigenvalues of the 6-th digits relative covariance matrix 2631 1451 103 given in the 33-file are the following: 2631 1451 104 2631 1451 105 4.35195E-09 4.49367E-09 4.76919E-09 5.19445E-09 2631 1451 106 5.64595E-09 6.15408E-09 7.11594E-09 7.89561E-09 2631 1451 107 9.40785E-09 1.19394E-08 1.48739E-08 1.86574E-08 2631 1451 108 2.18905E-08 1.32640E-06 2.77587E-04 3.86559E-04 2631 1451 109 6.52483E-04 1.02062E-03 1.26078E-03 1.33119E-03 2631 1451 110 1.81407E-03 2.05264E-03 3.00443E-03 4.57086E-03 2631 1451 111 8.12954E-03 2631 1451 112 2631 1451 113 References : 2631 1451 114 1. G.Brown Philosophical Magazine, v.2, p.785, 1957 2631 1451 115 2. J.Terrell, D.M.Holm Phys. Rev., v.109, p.2031, 1958 2631 1451 116 3. H.Pollehn, H.Neuert Zeitschrift f. Naturforschung, sect. A, 2631 1451 117 v.16, p.227, 1961 2631 1451 118 4. F.Gabbard, B.D.Kern Phys. Rev., v.128, p.1276, 1962 2631 1451 119 5. W.G.Cross et al. Prog. Report EANDC(CAN)-16, p.1, Jan. 1963 2631 1451 120 6. D.C.Santry, J.P.Batler Can. J. Phys., v.42, p.1030, 1964 2631 1451 121 7. C.G.Bonazzola et al. Nucl. Phys., v.51, p.337, February 1964 2631 1451 122 8. M.Bormann et al. Nucl. Phys., v.63, p.438, March 1965 2631 1451 123 9. H.Liskien,A.Paulsen J. of Nucl. Energy, v.19, p.73, Feb. 1965 2631 1451 124 10. H.Liskien, A.Paulsen Nukleonik, v.8, p.315, June 1966 2631 1451 125 11. J.A.Grundl Nucl. Sci. Eng., v.30, p.39, October 1967 2631 1451 126 12. V.N.Levkovskiy et al. Yadernaja Fizika (Sov.), v.8, n.1, p.7, 2631 1451 127 July 1968 2631 1451 128 13. H.K.Vonach et al. Proc. of 2nd Conference on Nuclear Cross- 2631 1451 129 Sections and Technology, Washington D.C., 4-7 March 1968, 2631 1451 130 v.2, p.885 2631 1451 131 14. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 2631 1451 132 15. N.C.Dyer, J.H.Hamilton Inorg. Nucl. 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Phys., v.15,no.4,p.341, 1993 2631 1451 163 37. Y.Ikeda et al. Journal of Nuclear Science and Technology, 2631 1451 164 v.30, n.9, pp.870-880, September 1993 2631 1451 165 38. Lu Hanlin et al. Report INDC(CPR)-045, IAEA, October 1998 2631 1451 166 39. A.A.Filatenkov et al. Report, RI-252, May 1999 ; 2631 1451 167 A.A.Filatenkov et al. VANT, Ser.: Yadernye Konstanty, v.2, 2631 1451 168 p.8, Moscow, 1996 2631 1451 169 40. A.Fessler Report JUL-3502, FZ Julich GmbH, Germany, 1998 ; 2631 1451 170 A.Fessler et al. Nucl. Sci. Eng., v.134, no.2, p.171, 2000 2631 1451 171 41. S.A.Badikov, A.B.Pashchenko Voprosy Atomnoy Nauki i Tekhniki 2631 1451 172 Ser. Jadernye Konstanty, 2(53), p.70, 1987 2631 1451 173 42. S.G.Forbes Phys. Rev., v.88, p.1309, December 1952 2631 1451 174 43. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31, p.267, 1953 2631 1451 175 44. G.W.Mc Clure, D.W.Kent J. Franklin Inst., v.260, p.238, 1955 2631 1451 176 45. D.L.Allan Proc. Physical Society, section A, v.70, p.195, 2631 1451 177 March 1957 2631 1451 178 46. S.Yasumi J. Phys. Soc. Japan, v.12, p.443, May 1957 2631 1451 179 47. P.V.March,W.T.Morton Philosophical Magazine, v.3, p.143, 1958 2631 1451 180 48. B.D.Kern et al. Nucl. Phys., v.10, p.226, May 1959 2631 1451 181 49. M.J.Depraz et al. Journal Phys. Radium, v.21, p.377, May 1960 2631 1451 182 50. R.S.Storey et al. Proc. Phys. Soc., v.75, p.526, 1960 2631 1451 183 51. D.M.Chittenden et al. Phys. Rev., v.122, p.860, May 1961 2631 1451 184 52. M.Bormann et al. Zeitschrift fuer Physik, v.166, p.477, 1962 2631 1451 185 53. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 2631 1451 186 54. J.D.Hemingway et al. Proc. Royal Society, section A, v.292, 2631 1451 187 p.180, May 1966 2631 1451 188 55. P.Cuzzocrea et al. Nuovo Cimento B, v.54, p.53, March 1968 2631 1451 189 56. S.M.Qaim et al. Proc. of Conference on Chemical Nuclear Data, 2631 1451 190 Measurements and Applicat., Univ. of Kent, Canterbury, 20-22 2631 1451 191 September 1971, p.121 2631 1451 192 57. J.J.Singh Trans. Amer. Nucl. Soc., v.15, p.147, June 1972 2631 1451 193 58. R.Spangler et al. Ann. Nucl. Sci., v.22, p.818, November 1975 2631 1451 194 59. A.B.M.G.Mostafa Nuclear Science and Applications, Series B: 2631 1451 195 Physical sciences, v.9, p.10, October 1976 2631 1451 196 60. Z.A.Ramendik et al. Atomnaja Energija (Sov.), v.42, no.2, 2631 1451 197 p.136, February 1977 2631 1451 198 61. S.Sothras Dissertation Abstracts, v.B38, p.280, July 1978 2631 1451 199 62. D.Sharma et al. Proc. of the 21-st Nuclear Physics and Solid 2631 1451 200 State Physics Symposium, Bombay, India, 28-31 December 1978 , 2631 1451 201 v.2, p.349 2631 1451 202 63. P.N.Ngoc et al. Progress Report INDC(HUN)-20,p.3, March 1983; 2631 1451 203 P.N.Ngoc et al. Nucleonika (Pol), v.29, p.87, 1984 2631 1451 204 64. P.N.Ngoc et al. Report INDC(VN)-2, November 1983 2631 1451 205 65. I.Garlea et al. Rev. Roum. Phys., v.29, p.421, 1984 2631 1451 206 66. J.P.Gupta et al. Pramana, v.24, p.637, 1985 2631 1451 207 67. M.Viennot et al. Nucl. Sci. Eng., v.108, p.289, July 1991 2631 1451 208 68. A.Ercan et al. Proc. of an Int. Conference on Nuclear Data 2631 1451 209 for Science and Technology, Juelich, FRG, 13-17 May 1991, 2631 1451 210 Springer-Verlag, 1992 2631 1451 211 69. L.I.Klochkova et al. Voprosy Atomnoy Nauki i Techniki, Ser.: 2631 1451 212 Yadernye Konstanty, v.1, p.27, 1992 2631 1451 213 70. ENDF/B-VI library,MAT=9237, eval. L.W.Weston et al. Nov.1989; 2631 1451 214 H.Conde editor Nuclear Data Standards for Nuclear Measu- 2631 1451 215 rements, Report NEANDC-311 U, pp.70-74, OECD, Paris, 1992. 2631 1451 216 71. M.Wagner et al. Evaluation of cross sections for 14 important 2631 1451 217 neutron-dosimetry reactions. Physics Data No.13-5, 1990 2631 1451 218 72. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 2631 1451 219 73. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2631 1451 220 st's Meeting on Evaluation and Processing of Covariance Data, 2631 1451 221 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 2631 1451 222 74. L.W.Weston et al. Evaluated Neutron Data for Uranium-235, 2631 1451 223 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 2631 1451 224 75. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 2631 1451 225 76. W.Mannhart Proc. 5-th ASTM-EUR. Symp. on Reactor Dosimetry, 2631 1451 226 Geesthacht, FRG, September 24-28, 1984, Vol.2, p.813, 1985 2631 1451 227 77. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2631 1451 228 Washington D.C., 25-28 April 1989, v.2, p.923 2631 1451 229 78. W.Mannhart Progress Report INDC(Ger)-045, pp.40-43, 1999 2631 1451 230 79. W.Mannhart Handbook on Nuclear Activation Cross Sections , 2631 1451 231 IAEA Tech. Report Ser. No.273, p.413, 1987 2631 1451 232 80. W.Mannhart Validation of Differential Cross Sections with 2631 1451 233 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2631 1451 234 September 2002 2631 1451 235 ***************************************************************** 2631 1451 236 The Q values and threshold energies were updated prior to pro- 2631 1451 237 cessing through the codes to comply with the values obtained 2631 1451 238 using the NNDC calculation program which is based on the 1995 2631 1451 239 Update to the Atomic mass Evaluation. 2631 1451 240 2631 1451 241 File 2 added to the pointwise file containing only the effective 2631 1451 242 scattering radius with no resonance parameters given. 2631 1451 243 Taken from ENDF/B-VI 2631 1451 244 ***************************************************************** 2631 1451 245 ***************** Program LINEAR (VERSION 2012-1) ***************2631 1451 246 For All Data Greater than 1.0000D-10 barns in Absolute Value 2631 1451 247 Data Linearized to Within an Accuracy of .100000000 per-cent 2631 1451 248 ***************** Program GROUPIE (VERSION 2012-1) **************2631 1451 249 Unshielded Group Averages Using 640 Groups 2631 1451 250 Weighting Spectrum: Flat (Constant) Spectrum 2631 1451 251 1 451 244 12631 1451 252 2 151 4 12631 1451 253 3 103 36 12631 1451 254 33 103 73 12631 1451 255 2631 1 0 256 2631 0 0 257 26056.0000 55.4540000 0 0 1 02631 2151 258 2.605600+4 1.000000+0 0 0 1 02631 2151 259 1.000000-5 8.500000+5 0 0 0 02631 2151 260 0.000000+0 5.437300-1 0 0 0 02631 2151 261 2631 2 0 262 2631 0 0 263 26056.0000 55.4544000 0 99 0 02631 3103 264 -2913100.00-2913100.00 0 0 1 1722631 3103 265 172 1 2631 3103 266 2900000.00 5.9515E-12 3000000.00 8.5020E-11 3100000.00 1.8579E-102631 3103 267 3200000.00 2.8657E-10 3300000.00 3.8734E-10 3400000.00 4.8811E-102631 3103 268 3500000.00 3.19099E-9 3600000.00 2.37217E-8 3700000.00 2.30222E-72631 3103 269 3800000.00 8.58242E-7 3900000.00 3.26945E-6 4000000.00 9.50803E-62631 3103 270 4100000.00 2.13588E-5 4200000.00 4.12059E-5 4300000.00 7.22240E-52631 3103 271 4400000.00 1.18636E-4 4500000.00 1.86046E-4 4600000.00 2.81858E-42631 3103 272 4700000.00 4.15816E-4 4800000.00 6.00655E-4 4900000.00 8.52843E-42631 3103 273 5000000.00 .001193315 5100000.00 .001648055 5200000.00 .0022481522631 3103 274 5300000.00 .003028741 5400000.00 .004026074 5500000.00 .0052718752631 3103 275 5600000.00 .006784800 5700000.00 .008560210 5800000.00 .0105616732631 3103 276 5900000.00 .012519191 6000000.00 .014238450 6100000.00 .0161199892631 3103 277 6200000.00 .018181130 6300000.00 .020072232 6400000.00 .0217811422631 3103 278 6500000.00 .023826650 6600000.00 .025746943 6700000.00 .0270864892631 3103 279 6800000.00 .028396693 6900000.00 .029706898 7000000.00 .0310583222631 3103 280 7100000.00 .032450965 7200000.00 .033907610 7300000.00 .0354282602631 3103 281 7400000.00 .037005959 7500000.00 .038640709 7600000.00 .0403027252631 3103 282 7700000.00 .041992008 7800000.00 .043681292 7900000.00 .0453705752631 3103 283 8000000.00 .047059858 8100000.00 .048700146 8200000.00 .0502914382631 3103 284 8300000.00 .051829760 8400000.00 .053315110 8500000.00 .0547360862631 3103 285 8600000.00 .056092686 8700000.00 .057449286 8800000.00 .0587423782631 3103 286 8900000.00 .059971958 9000000.00 .061201538 9100000.00 .0624311182631 3103 287 9200000.00 .063660698 9300000.00 .064888408 9400000.00 .0661142482631 3103 288 9500000.00 .067340088 9600000.00 .068565928 9700000.00 .0697917682631 3103 289 9800000.00 .071069201 9900000.00 .072398229 10000000.0 .0737272582631 3103 290 10100000.0 .075056286 10200000.0 .076448125 10300000.0 .0779027752631 3103 291 10400000.0 .079357425 10500000.0 .080812075 10600000.0 .0823283602631 3103 292 10700000.0 .083906280 10800000.0 .085484200 10900000.0 .0870621202631 3103 293 11000000.0 .088640040 11100000.0 .090238714 11200000.0 .0918581432631 3103 294 11300000.0 .093477571 11400000.0 .095097000 11500000.0 .0967164292631 3103 295 11600000.0 .098335857 11700000.0 .099955286 11800000.0 .1014997502631 3103 296 11900000.0 .102969250 12000000.0 .104438750 12100000.0 .1059082502631 3103 297 12200000.0 .107264833 12300000.0 .108508500 12400000.0 .1097521672631 3103 298 12500000.0 .110859000 12600000.0 .111829000 12700000.0 .1127990002631 3103 299 12800000.0 .113632500 12900000.0 .114329500 13000000.0 .1149057502631 3103 300 13100000.0 .115361250 13200000.0 .115689750 13300000.0 .1158912502631 3103 301 13400000.0 .115996000 13500000.0 .115908000 13600000.0 .1157240002631 3103 302 13700000.0 .115415750 13800000.0 .114983250 13900000.0 .1144076672631 3103 303 14000000.0 .113689000 14100000.0 .112970333 14200000.0 .1121030002631 3103 304 14300000.0 .111087000 14400000.0 .110071000 14500000.0 .1089375002631 3103 305 14600000.0 .107686500 14700000.0 .106435500 14800000.0 .1050908752631 3103 306 14900000.0 .103652625 15000000.0 .102214375 15100000.0 .1007761252631 3103 307 15200000.0 .099278768 15300000.0 .097722305 15400000.0 .0961658412631 3103 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