IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 9019.00000 18.8352000 0 0 34 10 925 1451 1 0.0 0.0 0 0 0 6 925 1451 2 1.00000000 60000000.0 0 0 10 2002 925 1451 3 300.000000 0.0 1 0 150 4 925 1451 4 9-F - 19 FEI EVAL-OCT01 K.I.Zolotarev 925 1451 5 DIST-Feb2004 925 1451 6 ----IRDF-2002 MATERIAL 925 925 1451 7 -----INCIDENT NEUTRON DATA 925 1451 8 ------ENDF-6 FORMAT 925 1451 9 ****************************************************************** 925 1451 10 IAEA, July 2011 (A. Trkov) 925 1451 11 Extended cross sections and covariances from 30 to 60 MeV 925 1451 12 by TENDL-2010, renormalised for continuity. 925 1451 13 ****************************************************************** 925 1451 14 ***************************************************************** 925 1451 15 9-F -19 FEI EVAL-OCT01 K.I.Zolotarev 925 1451 16 DIST-JAN02 20020125 925 1451 17 ----BROND-2 MATERIAL 925 925 1451 18 -----INCIDENT NEUTRON DATA 925 1451 19 ------ENDF-6 FORMAT 925 1451 20 ------Russian Reactor Dosimetry File RRDF-2002 925 1451 21 ***************************************************************** 925 1451 22 Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko 925 1451 23 ***************************************************************** 925 1451 24 MF= 3 925 1451 25 MT= 16 -(n,2n) cross section data 925 1451 26 -------------------------------------- 925 1451 27 Excitation function for the F-19(n,2n)F-18 reaction in the 925 1451 28 energy region from threshold to 30 MeV was evaluated by means of 925 1451 29 statistical analysis of experimental cross section data [1-17] and 925 1451 30 data from GNASH [18,19] calculation. 925 1451 31 Experimental data [2-3],[5],[9-13],[15-17] were renormalized 925 1451 32 to the new standards for monitor reactions cross sections. Data 925 1451 33 of Mc Crary et al. [1], Rayburn et al.[2], Bormann et al.[4], and 925 1451 34 Shiokawa et al. [7] were renormalized to the results of precise 925 1451 35 measurements Vonach et al. [9] and Ikeda et al. [15] in the 14 MeV 925 1451 36 region. Data of Chatterjee et al. [8] were corrected to their pre- 925 1451 37 vious measurements at the 14.8 MeV point [6]. Results of measure- 925 1451 38 ments of Nagel [5] were taken only from SUBENT 005, EXFOR 20198. 925 1451 39 Experimental cross section data from ref. [20-31] were rejec- 925 1451 40 ted due to their big discrepancy with the main bulk of experimen- 925 1451 41 al data [1-17] and data from theoretical model calculation. 925 1451 42 The final procedure of evaluation F-19(n,2n)F-18 excitation 925 1451 43 function from threshold to 30 MeV has been carried out within the 925 1451 44 framework of generalized least squares method. Rational function 925 1451 45 was used as model function [32]. Calculations was performed by 925 1451 46 means of Pade-2 code [33]. 925 1451 47 U-235 thermal fission [34] and Cf-252 spontaneous fission 925 1451 48 neutron spectra [35] averaged cross-sections calculated from the 925 1451 49 evaluated F-19(n,2n)F-18 excitation function are the following: 925 1451 50 925 1451 51 ----------------------------------------------------------------- 925 1451 52 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 925 1451 53 ----------------------I-----------------I------------------------ 925 1451 54 U-235 neutron fission I 0.007299 I 0.007200+-0.001000 [36] 925 1451 55 I I 0.006509+-0.000300 [37] 925 1451 56 I I 0.008653+-0.000464 [38] 925 1451 57 ----------------------I-----------------I------------------------ 925 1451 58 CF-252 spont. fission I 0.01615 I 0.01628+-0.00054 [39] 925 1451 59 I I 0.01612+-0.00054 [40] 925 1451 60 ----------------------------------------------------------------- 925 1451 61 925 1451 62 MF=33 925 1451 63 MT= 16 -(n,2n) cross section cov. matrix 925 1451 64 --------------------------------------------- 925 1451 65 Uncertainties in the evaluated excitation function for the 925 1451 66 reaction F-19(n,2n)F-18 are given in the form of relative covari- 925 1451 67 ance matrix for the 26-neutron energy groups (LB=5). Covariance 925 1451 68 matrix of uncertainties was calculated simultaneously with 925 1451 69 recommended cross section data by means of PADE-2 code. 925 1451 70 Eigenvalues of the 6-th digits relative covariance matrix 925 1451 71 given in the 33-file are the following: 925 1451 72 925 1451 73 3.67622E-08 3.74071E-08 3.79051E-08 3.91111E-08 925 1451 74 4.11094E-08 4.32321E-08 4.68199E-08 4.98738E-08 925 1451 75 5.55426E-08 6.01322E-08 7.00100E-08 7.85485E-08 925 1451 76 9.57150E-08 1.06820E-07 1.28694E-07 1.47868E-07 925 1451 77 2.58858E-07 6.32301E-07 3.80384E-06 5.45023E-04 925 1451 78 1.36448E-03 3.28506E-03 8.26671E-03 1.39754E-02 925 1451 79 1.58981E-02 6.37025E-02 925 1451 80 925 1451 81 References : 925 1451 82 1. J.H.Mc Crary,I.L.Morgan Bull. American Phys. Soc., v.5, 925 1451 83 p.246, April 1960 ; 925 1451 84 J.H.Mc Crary,I.L.Morgan Report AFSWC-TR-60-30, 1960 925 1451 85 2. L.A.Rayburn Proc. of Conf. on Direct Interactions and Nuclear 925 1451 86 Reaction Mechanisms, Padua, 3-8 September 1962, Gordon and 925 1451 87 Breach, New York, 1963, p.322. ; 925 1451 88 L.A.Rayburn Bull. Am. Phys. Soc., v.7, p.335, April 1962 925 1451 89 3. M.Cevolani, S.Petralia Nuovo Cimento, v.26, p.1328, Dec.1962 925 1451 90 4. M.Bormann et al. Nucl. Phys., v.63, p.438, March 1965 925 1451 91 5. W.Nagel EXFOR 20198.005, 1966 925 1451 92 6. A.Chatterjee et al. Progress Report BARC-305, p.30, Nov. 1967 925 1451 93 7. T.Shiokawa et al. J. Inorg. Nucl. Chem., v.30, p.1, Jan. 1968 925 1451 94 8. A.Chatterjee e.a. Proc.of Symposium Nucl.Phys. and Solid State 925 1451 95 Phys., Roorke, India, 1969, v.2, p.117, December 1969 925 1451 96 9. H.K.Vonach et al. Proc. of 2-nd Conference on Nuclear Cross- 925 1451 97 Sections and Technology, Washington D.C., 4-7 March 1968, v.2, 925 1451 98 p.885 925 1451 99 10. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 925 1451 100 11. R.Mogharrab, H.Neuert Atomkernenergie, v.19, p.107, April 1972 925 1451 101 12. J.C.Robertson et al. J. Nucl. Energ., v.27, p.531, Aug. 1973 925 1451 102 13. R.A.Sigg Dissert. Abstr., sect. B, v.37, p.2237, Nov. 1976 925 1451 103 14. T.B.Ryves et al. J. of Physics, pt.G, v.4, n.11, p.1783, 1978 925 1451 104 15. Y.Ikeda et al. Report JAERI-1312, 1988 925 1451 105 16. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v.106, p.332, 1990 925 1451 106 17. C.L.Hartmann, P.M.DeLuca Nucl. Sci. Eng., v.109, p.319, 1991 925 1451 107 18. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 925 1451 108 Model Code for Calculation of Cross Section and Emission 925 1451 109 Spectra. Report LA-6947, Los Alamos, 1977 925 1451 110 19. E.L.Trykov, G.Ya.Tertychnyi Private communication, IPPE, 925 1451 111 Obninsk, May 1999 925 1451 112 20. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31, p.267, 1953 925 1451 113 21. V.J.Ashby e.a. Phys. Rev., v.111, p.616, 1958 925 1451 114 22. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 925 1451 115 23. O.D.Brill et al. Doklady Akademii Nauk, v.136,n.1,p.55, 1961; 925 1451 116 O.D.Brill et al. Soviet Physics-Doklady, v.6, p.24, 1961 925 1451 117 24. J.Picard, C.F.Williamson Nucl. Phys., v.63, p.673, April 1965 925 1451 118 25. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 925 1451 119 26. J.Csikai Report EANDC-50 S, paper 102, July 1965 925 1451 120 27. A.Pasquarelli Nucl. Phys. A, v.93, p.218, March 1967 925 1451 121 28. M.Bormann, I.Riehle Zeitschrift f.Physik, v.207, p.64, 925 1451 122 October 1967 925 1451 123 29. H.O.Menlove et al. Phys. Rev., v.163, p.1308, 1967 925 1451 124 30. D.Crumpton J.Inorg. Nucl. Chem., v.31, p.3727, December 1969 925 1451 125 31. J.Araminowicz, J.Dresler Report INR-1464, p.14, May 1973 925 1451 126 32. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 925 1451 127 st's Meeting on Evaluation and Processing of Covariance Data, 925 1451 128 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 925 1451 129 33. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 925 1451 130 34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 925 1451 131 Library, MAT=9228, MF=5, MT=18, eval. April 1989 925 1451 132 35. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 925 1451 133 36. F.Nasyrov, B.D.Sciborskij Atomnaja Energija, v.25, no.5, 925 1451 134 p.437, November 1968 925 1451 135 37. M.Najzer, J.Rant Report IAEA-208, v.2, p.247, 1978 925 1451 136 38. W.Mannhart Progress Report INDC(Ger)-045, pp.40-43, 1999 925 1451 137 39. W.Mannhart Handbook on Nuclear Activation Data. IAEA Tech- 925 1451 138 nical Report series No.273, p.413, 1987 925 1451 139 40. W.Mannhart Validation of Differential Cross Sections with 925 1451 140 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 925 1451 141 September 2002 925 1451 142 ***************************************************************** 925 1451 143 File 2 added to the pointwise file containing only the effective 925 1451 144 scattering radius with no resonance parameters given. 925 1451 145 Taken from ENDF/B-VI 925 1451 146 925 1451 147 ***************************************************************** 925 1451 148 ***************** Program LINEAR (VERSION 2012-1) *************** 925 1451 149 For All Data Greater than 1.0000D-10 barns in Absolute Value 925 1451 150 Data Linearized to Within an Accuracy of .100000000 per-cent 925 1451 151 ***************** Program GROUPIE (VERSION 2012-1) ************** 925 1451 152 Unshielded Group Averages Using 640 Groups 925 1451 153 Weighting Spectrum: Flat (Constant) Spectrum 925 1451 154 1 451 147 1 925 1451 155 2 151 4 1 925 1451 156 3 16 25 1 925 1451 157 33 16 76 1 925 1451 158 925 1 0 159 925 0 0 160 9019.00000 18.8352000 0 0 1 0 925 2151 161 9.019000+3 1.000000+0 0 0 1 0 925 2151 162 1.000000-5 2.000000+7 0 0 0 0 925 2151 163 5.000000-1 5.360000-1 0 0 0 0 925 2151 164 925 2 0 165 925 0 0 166 9019.00000 18.8352000 0 0 0 0 925 3 16 167 -10432200.0-10432200.0 0 0 1 92 925 3 16 168 92 1 925 3 16 169 10900000.0 2.02752E-6 11000000.0 5.63229E-5 11100000.0 1.37655E-4 925 3 16 170 11200000.0 2.92275E-4 11300000.0 5.48721E-4 11400000.0 9.17543E-4 925 3 16 171 11500000.0 .001402145 11600000.0 .002002095 11700000.0 .002714490 925 3 16 172 11800000.0 .003534705 11900000.0 .004456885 12000000.0 .005474310 925 3 16 173 12100000.0 .006579685 12200000.0 .007765400 12300000.0 .009023740 925 3 16 174 12400000.0 .010347050 12500000.0 .011727850 12600000.0 .013159000 925 3 16 175 12700000.0 .014633700 12800000.0 .016152650 12900000.0 .017695750 925 3 16 176 13000000.0 .019265950 13100000.0 .020863250 13200000.0 .022460550 925 3 16 177 13300000.0 .024071763 13400000.0 .025696888 13500000.0 .027322013 925 3 16 178 13600000.0 .028947138 13700000.0 .030572263 13800000.0 .032197388 925 3 16 179 13900000.0 .033822513 14000000.0 .035447638 14100000.0 .037049625 925 3 16 180 14200000.0 .038628475 14300000.0 .040207325 14400000.0 .041786175 925 3 16 181 14500000.0 .043331888 14600000.0 .044844463 14700000.0 .046357038 925 3 16 182 14800000.0 .047869613 14900000.0 .049339675 15000000.0 .050767225 925 3 16 183 15100000.0 .052194775 15200000.0 .053622325 15300000.0 .054999450 925 3 16 184 15400000.0 .056326150 15500000.0 .057652850 15600000.0 .058979550 925 3 16 185 15700000.0 .060248850 15800000.0 .061460750 15900000.0 .062672650 925 3 16 186 16000000.0 .063884550 16100000.0 .065033000 16200000.0 .066118000 925 3 16 187 16300000.0 .067203000 16400000.0 .068288000 16500000.0 .069304550 925 3 16 188 16600000.0 .070252650 16700000.0 .071200750 16800000.0 .072148850 925 3 16 189 16900000.0 .073024838 17000000.0 .073828713 17100000.0 .074632588 925 3 16 190 17200000.0 .075436463 17300000.0 .076166188 17400000.0 .076821763 925 3 16 191 17500000.0 .077477338 17600000.0 .078132913 17700000.0 .078714000 925 3 16 192 17800000.0 .079220600 17900000.0 .079727200 18000000.0 .080233800 925 3 16 193 18100000.0 .080667413 18200000.0 .081028038 18300000.0 .081388663 925 3 16 194 18400000.0 .081749288 18500000.0 .082040026 18600000.0 .082260879 925 3 16 195 18700000.0 .082481731 18800000.0 .082702584 18900000.0 .082858134 925 3 16 196 19000000.0 .082948381 19100000.0 .083038629 19200000.0 .083128876 925 3 16 197 19300000.0 .083180900 19400000.0 .083152770 19500000.0 .083082710 925 3 16 198 19600000.0 .083012650 19700000.0 .082942590 19800000.0 .082872530 925 3 16 199 19900000.0 .082772747 20000000.0 0.0 925 3 16 200 925 3 0 201 925 0 0 202 9019.00000 18.8352000 0 0 0 1 92533 16 203 0.000000+0 0.000000+0 0 16 0 2 92533 16 204 0.000000+0 0.000000+0 1 5 21 6 92533 16 205 1.000000-5 3.000010+7 3.400000+7 4.200000+7 5.000000+7 6.000000+7 92533 16 206 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 9.712910-3 92533 16 207 9.461980-3 9.204010-3 8.738320-3 9.336340-3 9.107870-3 8.719650-3 92533 16 208 8.998580-3 8.676580-3 8.583960-3 92533 16 209 0.000000+0 0.000000+0 1 5 406 28 92533 16 210 1.000000-5 1.090000+7 1.200000+7 1.250000+7 1.300000+7 1.350000+7 92533 16 211 1.400000+7 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7 92533 16 212 1.700000+7 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7 92533 16 213 2.000000+7 2.100000+7 2.200000+7 2.300000+7 2.400000+7 2.500000+7 92533 16 214 2.700000+7 2.800000+7 2.900000+7 3.000000+7 0.000000+0 0.000000+0 92533 16 215 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 216 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 217 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 218 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 219 0.000000+0 7.844560-3 4.898350-3 3.027060-3 1.929170-3 1.321910-3 92533 16 220 9.926111-4 8.097050-4 6.990610-4 6.218640-4 5.596050-4 5.048120-4 92533 16 221 4.555230-4 4.121780-4 3.758470-4 3.473540-4 3.269110-4 3.140740-4 92533 16 222 3.073570-4 3.120960-4 3.231580-4 3.310920-4 3.298620-4 3.041000-4 92533 16 223 2.525070-4 2.039030-4 1.464150-4 3.648070-3 2.360540-3 1.449110-3 92533 16 224 9.104930-4 6.319380-4 5.059420-4 4.569550-4 4.388680-4 4.266530-4 92533 16 225 4.088340-4 3.819840-4 3.470900-4 3.071470-4 2.656870-4 2.259100-4 92533 16 226 1.902720-4 1.486420-4 1.141580-4 1.016320-4 1.039070-4 1.134800-4 92533 16 227 1.281520-4 1.350840-4 1.314670-4 1.212070-4 1.826270-3 1.354210-3 92533 16 228 9.782671-4 7.059900-4 5.267220-4 4.207220-4 3.665780-4 3.449020-4 92533 16 229 3.398810-4 3.397380-4 3.365240-4 3.256910-4 3.054490-4 2.760780-4 92533 16 230 2.392420-4 1.754770-4 8.900070-5 1.611170-5-3.205140-5-5.099350-5 92533 16 231 -2.365820-5 5.330250-5 1.291950-4 2.188860-4 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2.248090-4 2.263440-4 2.532360-4 3.094430-4 3.658040-4 92533 16 245 4.035410-4 4.133410-4 3.692840-4 2.697090-4 1.753330-4 6.488820-5 92533 16 246 8.276580-4 7.994630-4 7.403910-4 6.622230-4 5.756870-4 4.895590-4 92533 16 247 4.102830-4 3.420170-4 2.868660-4 2.452630-4 2.075860-4 1.890180-4 92533 16 248 1.937990-4 2.070150-4 2.180840-4 2.167570-4 1.920930-4 1.606910-4 92533 16 249 1.194350-4 8.367870-4 8.381600-4 8.077220-4 7.513760-4 6.760250-4 92533 16 250 5.886680-4 4.958200-4 4.031020-4 3.150170-4 2.001340-4 8.278800-5 92533 16 251 1.074360-5-2.078540-5-2.009100-5 2.343720-5 9.478700-5 1.508320-4 92533 16 252 2.094530-4 9.030970-4 9.293760-4 9.163470-4 8.669560-4 7.869960-4 92533 16 253 6.839560-4 5.660230-4 4.412210-4 2.582200-4 4.586960-5-1.068070-4 92533 16 254 -1.912730-4-2.107930-4-1.358110-4 2.138250-5 1.612100-4 3.183170-4 92533 16 255 1.012600-3 1.049310-3 1.037800-3 9.812610-4 8.866920-4 7.633760-4 92533 16 256 6.215440-4 3.970180-4 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