777 0 0 0 9.019000+3 1.883520+1 0 0 41 1 925 1451 1 0.000000+0 0.000000+0 0 0 0 6 925 1451 2 1.000000+0 0.000000+0 0 0 10 2 925 1451 3 3.000000+2 0.000000+0 0 0 131 3 925 1451 4 9-F - 19 FEI EVAL-OCT01 K.I.Zolotarev 925 1451 5 DIST-JAN02 Rev.3 October 2009 925 1451 6 ----BROND-3 MATERIAL 925 925 1451 7 -----INCIDENT NEUTRON DATA 925 1451 8 ------ENDF-6 FORMAT 925 1451 9 ***************************************************************** 925 1451 10 ------Russian Reactor Dosimetry File RRDF-2002 925 1451 11 ***************************************************************** 925 1451 12 Authors of evaluation: K.I.Zolotarev and A.B.Pashchenko 925 1451 13 ***************************************************************** 925 1451 14 MF= 3 925 1451 15 MT= 16 -(n,2n) cross section data 925 1451 16 -------------------------------------- 925 1451 17 Excitation function for the F-19(n,2n)F-18 reaction in the 925 1451 18 energy region from threshold to 30 MeV was evaluated by means of 925 1451 19 statistical analysis of experimental cross section data [1-17] and 925 1451 20 data from GNASH [18,19] calculation. 925 1451 21 Experimental data [2-3],[5],[9-13],[15-17] were renormalized 925 1451 22 to the new standards for monitor reactions cross sections. Data 925 1451 23 of Mc Crary et al. [1], Rayburn et al.[2], Bormann et al.[4], and 925 1451 24 Shiokawa et al. [7] were renormalized to the results of precise 925 1451 25 measurements Vonach et al. [9] and Ikeda et al. [15] in the 14 MeV 925 1451 26 region. Data of Chatterjee et al. [8] were corrected to their pre- 925 1451 27 vious measurements at the 14.8 MeV point [6]. Results of measure- 925 1451 28 ments of Nagel [5] were taken only from SUBENT 005, EXFOR 20198. 925 1451 29 Experimental cross section data from ref. [20-31] were rejec- 925 1451 30 ted due to their big discrepancy with the main bulk of experimen- 925 1451 31 al data [1-17] and data from theoretical model calculation. 925 1451 32 The final procedure of evaluation F-19(n,2n)F-18 excitation 925 1451 33 function from threshold to 30 MeV has been carried out within the 925 1451 34 framework of generalized least squares method. Rational function 925 1451 35 was used as model function [32]. Calculations was performed by 925 1451 36 means of Pade-2 code [33]. 925 1451 37 U-235 thermal fission [34] and Cf-252 spontaneous fission 925 1451 38 neutron spectra [35] averaged cross-sections calculated from the 925 1451 39 evaluated F-19(n,2n)F-18 excitation function are the following: 925 1451 40 925 1451 41 ----------------------+-----------------+------------------------ 925 1451 42 Type of spectrum | ,mb (calc.) | , mb (measured) 925 1451 43 ----------------------+-----------------+------------------------ 925 1451 44 U-235 neutron fission | 0.0069802 | 0.007200+-0.001000 [36] 925 1451 45 | | 0.006509+-0.000300 [37] 925 1451 46 | | 0.008653+-0.000464 [38] 925 1451 47 | | 0.008624+-0.000463 [40] 925 1451 48 ----------------------+-----------------+------------------------ 925 1451 49 CF-252 spont. fission | 0.01628 | 0.01628+-0.00054 [39] 925 1451 50 | | 0.01612+-0.00054 [40] 925 1451 51 ----------------------+-----------------+------------------------ 925 1451 52 925 1451 53 MF=33 925 1451 54 MT= 16 -(n,2n) cross section cov. matrix 925 1451 55 --------------------------------------------- 925 1451 56 Uncertainties in the evaluated excitation function for the 925 1451 57 reaction F-19(n,2n)F-18 are given in the form of relative covari- 925 1451 58 ance matrix for the 26-neutron energy groups (LB=5). Covariance 925 1451 59 matrix of uncertainties was calculated simultaneously with 925 1451 60 recommended cross section data by means of PADE-2 code. 925 1451 61 Eigenvalues of the 6-th digits relative covariance matrix 925 1451 62 given in the 33-file are the following: 925 1451 63 925 1451 64 3.67622E-08 3.74071E-08 3.79051E-08 3.91111E-08 925 1451 65 4.11094E-08 4.32321E-08 4.68199E-08 4.98738E-08 925 1451 66 5.55426E-08 6.01322E-08 7.00100E-08 7.85485E-08 925 1451 67 9.57150E-08 1.06820E-07 1.28694E-07 1.47868E-07 925 1451 68 2.58858E-07 6.32301E-07 3.80384E-06 5.45023E-04 925 1451 69 1.36448E-03 3.28506E-03 8.26671E-03 1.39754E-02 925 1451 70 1.58981E-02 6.37025E-02 925 1451 71 925 1451 72 References : 925 1451 73 1. J.H.Mc Crary,I.L.Morgan Bull. American Phys. Soc., v.5, 925 1451 74 p.246, April 1960 ; 925 1451 75 J.H.Mc Crary,I.L.Morgan Report AFSWC-TR-60-30, 1960 925 1451 76 2. L.A.Rayburn Proc. of Conf. on Direct Interactions and Nuclear 925 1451 77 Reaction Mechanisms, Padua, 3-8 September 1962, Gordon and 925 1451 78 Breach, New York, 1963, p.322. ; 925 1451 79 L.A.Rayburn Bull. Am. Phys. Soc., v.7, p.335, April 1962 925 1451 80 3. M.Cevolani, S.Petralia Nuovo Cimento, v.26, p.1328, Dec.1962 925 1451 81 4. M.Bormann et al. Nucl. Phys., v.63, p.438, March 1965 925 1451 82 5. W.Nagel EXFOR 20198.005, 1966 925 1451 83 6. A.Chatterjee et al. Progress Report BARC-305, p.30, Nov. 1967 925 1451 84 7. T.Shiokawa et al. J. Inorg. Nucl. Chem., v.30, p.1, Jan. 1968 925 1451 85 8. A.Chatterjee e.a. Proc.of Symposium Nucl.Phys. and Solid State 925 1451 86 Phys., Roorke, India, 1969, v.2, p.117, December 1969 925 1451 87 9. H.K.Vonach et al. Proc. of 2-nd Conference on Nuclear Cross- 925 1451 88 Sections and Technology, Washington D.C., 4-7 March 1968, v.2, 925 1451 89 p.885 925 1451 90 10. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 925 1451 91 11. R.Mogharrab, H.Neuert Atomkernenergie, v.19, p.107, April 1972 925 1451 92 12. J.C.Robertson et al. J. Nucl. Energ., v.27, p.531, Aug. 1973 925 1451 93 13. R.A.Sigg Dissert. Abstr., sect. B, v.37, p.2237, Nov. 1976 925 1451 94 14. T.B.Ryves et al. J. of Physics, pt.G, v.4, n.11, p.1783, 1978 925 1451 95 15. Y.Ikeda et al. Report JAERI-1312, 1988 925 1451 96 16. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v.106, p.332, 1990 925 1451 97 17. C.L.Hartmann, P.M.DeLuca Nucl. Sci. Eng., v.109, p.319, 1991 925 1451 98 18. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 925 1451 99 Model Code for Calculation of Cross Section and Emission 925 1451 100 Spectra. Report LA-6947, Los Alamos, 1977 925 1451 101 19. E.L.Trykov, G.Ya.Tertychnyi Private communication, IPPE, 925 1451 102 Obninsk, May 1999 925 1451 103 20. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31, p.267, 1953 925 1451 104 21. V.J.Ashby e.a. Phys. Rev., v.111, p.616, 1958 925 1451 105 22. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 925 1451 106 23. O.D.Brill et al. Doklady Akademii Nauk, v.136,n.1,p.55, 1961; 925 1451 107 O.D.Brill et al. Soviet Physics-Doklady, v.6, p.24, 1961 925 1451 108 24. J.Picard, C.F.Williamson Nucl. Phys., v.63, p.673, April 1965 925 1451 109 25. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 925 1451 110 26. J.Csikai Report EANDC-50 S, paper 102, July 1965 925 1451 111 27. A.Pasquarelli Nucl. Phys. A, v.93, p.218, March 1967 925 1451 112 28. M.Bormann, I.Riehle Zeitschrift f.Physik, v.207, p.64, 925 1451 113 October 1967 925 1451 114 29. H.O.Menlove et al. Phys. Rev., v.163, p.1308, 1967 925 1451 115 30. D.Crumpton J.Inorg. Nucl. Chem., v.31, p.3727, December 1969 925 1451 116 31. J.Araminowicz, J.Dresler Report INR-1464, p.14, May 1973 925 1451 117 32. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 925 1451 118 st's Meeting on Evaluation and Processing of Covariance Data, 925 1451 119 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 925 1451 120 33. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 925 1451 121 34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 925 1451 122 Library, MAT=9228, MF=5, MT=18, eval. April 1989 925 1451 123 35. W.Mannhart, Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 925 1451 124 36. F.Nasyrov, B.D.Sciborskij Atomnaja Energija, v.25, no.5, 925 1451 125 p.437, November 1968 925 1451 126 37. M.Najzer, J.Rant Report IAEA-208, v.2, p.247, 1978 925 1451 127 38. W.Mannhart Progress Report INDC(Ger)-045, pp.40-43, 1999 925 1451 128 39. W.Mannhart Handbook on Nuclear Activation Data. IAEA Tech- 925 1451 129 nical Report series No.273, p.413, 1987 925 1451 130 40. W.Mannhart Validation of Differential Cross Sections with 925 1451 131 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 925 1451 132 September 2002 925 1451 133 ***************************************************************** 925 1451 134 925 1451 135 1 451 138 1 925 1451 136 3 16 67 1 925 1451 137 33 16 71 1 925 1451 138 925 1 0 139 925 0 0 140 9.019000+3 1.883520+1 0 0 0 0 925 3 16 141 -1.043240+7-1.043240+7 0 0 1 192 925 3 16 142 192 2 925 3 16 143 1.098642+7 0.000000+0 1.100000+7 2.875920-5 1.110000+7 8.388660-5 925 3 16 144 1.120000+7 1.914240-4 1.130000+7 3.931250-4 1.140000+7 7.043160-4 925 3 16 145 1.150000+7 1.130770-3 1.160000+7 1.673520-3 1.170000+7 2.330670-3 925 3 16 146 1.180000+7 3.098310-3 1.190000+7 3.971100-3 1.200000+7 4.942670-3 925 3 16 147 1.210000+7 6.005950-3 1.220000+7 7.153420-3 1.230000+7 8.377380-3 925 3 16 148 1.240000+7 9.670100-3 1.250000+7 1.102400-2 1.260000+7 1.243170-2 925 3 16 149 1.270000+7 1.388630-2 1.280000+7 1.538110-2 1.290000+7 1.691000-2 925 3 16 150 1.300000+7 1.846730-2 1.310000+7 2.004770-2 1.320000+7 2.164650-2 925 3 16 151 1.330000+7 2.325920-2 1.340000+7 2.488200-2 1.350000+7 2.651120-2 925 3 16 152 1.360000+7 2.814360-2 1.370000+7 2.977620-2 1.380000+7 3.140650-2 925 3 16 153 1.390000+7 3.303200-2 1.400000+7 3.465060-2 1.410000+7 3.626020-2 925 3 16 154 1.420000+7 3.785920-2 1.430000+7 3.944570-2 1.440000+7 4.101830-2 925 3 16 155 1.450000+7 4.257560-2 1.460000+7 4.411630-2 1.470000+7 4.563900-2 925 3 16 156 1.480000+7 4.714260-2 1.490000+7 4.862590-2 1.500000+7 5.008800-2 925 3 16 157 1.510000+7 5.152770-2 1.520000+7 5.294410-2 1.530000+7 5.433610-2 925 3 16 158 1.540000+7 5.570290-2 1.550000+7 5.704360-2 1.560000+7 5.835720-2 925 3 16 159 1.570000+7 5.964290-2 1.580000+7 6.089980-2 1.590000+7 6.212730-2 925 3 16 160 1.600000+7 6.332440-2 1.610000+7 6.449050-2 1.620000+7 6.562480-2 925 3 16 161 1.630000+7 6.672670-2 1.640000+7 6.779540-2 1.650000+7 6.883050-2 925 3 16 162 1.660000+7 6.983130-2 1.670000+7 7.079720-2 1.680000+7 7.172790-2 925 3 16 163 1.690000+7 7.262290-2 1.700000+7 7.348170-2 1.710000+7 7.430410-2 925 3 16 164 1.720000+7 7.508970-2 1.730000+7 7.583840-2 1.740000+7 7.654990-2 925 3 16 165 1.750000+7 7.722420-2 1.760000+7 7.786110-2 1.770000+7 7.846070-2 925 3 16 166 1.780000+7 7.902290-2 1.790000+7 7.954800-2 1.800000+7 8.003600-2 925 3 16 167 1.810000+7 8.048710-2 1.820000+7 8.090170-2 1.830000+7 8.128010-2 925 3 16 168 1.840000+7 8.162260-2 1.850000+7 8.192960-2 1.860000+7 8.220160-2 925 3 16 169 1.870000+7 8.243910-2 1.880000+7 8.264270-2 1.890000+7 8.281300-2 925 3 16 170 1.900000+7 8.295060-2 1.910000+7 8.305610-2 1.920000+7 8.313040-2 925 3 16 171 1.930000+7 8.317400-2 1.940000+7 8.318780-2 1.950000+7 8.317260-2 925 3 16 172 1.960000+7 8.312910-2 1.970000+7 8.305820-2 1.980000+7 8.296070-2 925 3 16 173 1.990000+7 8.283750-2 2.000000+7 8.268940-2 2.010000+7 8.251740-2 925 3 16 174 2.020000+7 8.232230-2 2.030000+7 8.210490-2 2.040000+7 8.186620-2 925 3 16 175 2.050000+7 8.160700-2 2.060000+7 8.132820-2 2.070000+7 8.103070-2 925 3 16 176 2.080000+7 8.071540-2 2.090000+7 8.038310-2 2.100000+7 8.003450-2 925 3 16 177 2.110000+7 7.967070-2 2.120000+7 7.929230-2 2.130000+7 7.890030-2 925 3 16 178 2.140000+7 7.849530-2 2.150000+7 7.807810-2 2.160000+7 7.764960-2 925 3 16 179 2.170000+7 7.721040-2 2.180000+7 7.676120-2 2.190000+7 7.630270-2 925 3 16 180 2.200000+7 7.583570-2 2.210000+7 7.536070-2 2.220000+7 7.487850-2 925 3 16 181 2.230000+7 7.438950-2 2.240000+7 7.389440-2 2.250000+7 7.339390-2 925 3 16 182 2.260000+7 7.288830-2 2.270000+7 7.237830-2 2.280000+7 7.186430-2 925 3 16 183 2.290000+7 7.134690-2 2.300000+7 7.082650-2 2.310000+7 7.030360-2 925 3 16 184 2.320000+7 6.977860-2 2.330000+7 6.925190-2 2.340000+7 6.872380-2 925 3 16 185 2.350000+7 6.819490-2 2.360000+7 6.766530-2 2.370000+7 6.713550-2 925 3 16 186 2.380000+7 6.660580-2 2.390000+7 6.607650-2 2.400000+7 6.554790-2 925 3 16 187 2.410000+7 6.502020-2 2.420000+7 6.449370-2 2.430000+7 6.396860-2 925 3 16 188 2.440000+7 6.344520-2 2.450000+7 6.292370-2 2.460000+7 6.240430-2 925 3 16 189 2.470000+7 6.188720-2 2.480000+7 6.137250-2 2.490000+7 6.086050-2 925 3 16 190 2.500000+7 6.035120-2 2.510000+7 5.984490-2 2.520000+7 5.934160-2 925 3 16 191 2.530000+7 5.884150-2 2.540000+7 5.834480-2 2.550000+7 5.785140-2 925 3 16 192 2.560000+7 5.736150-2 2.570000+7 5.687520-2 2.580000+7 5.639260-2 925 3 16 193 2.590000+7 5.591380-2 2.600000+7 5.543880-2 2.610000+7 5.496760-2 925 3 16 194 2.620000+7 5.450040-2 2.630000+7 5.403710-2 2.640000+7 5.357790-2 925 3 16 195 2.650000+7 5.312280-2 2.660000+7 5.267170-2 2.670000+7 5.222480-2 925 3 16 196 2.680000+7 5.178200-2 2.690000+7 5.134340-2 2.700000+7 5.090900-2 925 3 16 197 2.710000+7 5.047870-2 2.720000+7 5.005270-2 2.730000+7 4.963080-2 925 3 16 198 2.740000+7 4.921320-2 2.750000+7 4.879970-2 2.760000+7 4.839040-2 925 3 16 199 2.770000+7 4.798540-2 2.780000+7 4.758440-2 2.790000+7 4.718770-2 925 3 16 200 2.800000+7 4.679510-2 2.810000+7 4.640660-2 2.820000+7 4.602220-2 925 3 16 201 2.830000+7 4.564200-2 2.840000+7 4.526570-2 2.850000+7 4.489350-2 925 3 16 202 2.860000+7 4.452540-2 2.870000+7 4.416120-2 2.880000+7 4.380100-2 925 3 16 203 2.890000+7 4.344470-2 2.900000+7 4.309230-2 2.910000+7 4.274380-2 925 3 16 204 2.920000+7 4.239910-2 2.930000+7 4.205820-2 2.940000+7 4.172110-2 925 3 16 205 2.950000+7 4.138780-2 2.960000+7 4.105810-2 2.970000+7 4.073210-2 925 3 16 206 2.980000+7 4.040970-2 2.990000+7 4.009100-2 3.000000+7 3.977580-2 925 3 16 207 925 3 0 208 925 0 0 209 9.019000+3 1.883520+1 0 0 0 1 92533 16 210 0.000000+0 0.000000+0 0 16 0 1 92533 16 211 0.000000+0 0.000000+0 1 5 406 28 92533 16 212 1.000000-5 1.098642+7 1.200000+7 1.250000+7 1.300000+7 1.350000+7 92533 16 213 1.400000+7 1.450000+7 1.500000+7 1.550000+7 1.600000+7 1.650000+7 92533 16 214 1.700000+7 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7 92533 16 215 2.000000+7 2.100000+7 2.200000+7 2.300000+7 2.400000+7 2.500000+7 92533 16 216 2.700000+7 2.800000+7 2.900000+7 3.000000+7 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 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 220 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 0.000000+0 92533 16 221 0.000000+0 7.844560-3 4.898350-3 3.027060-3 1.929170-3 1.321910-3 92533 16 222 9.926111-4 8.097050-4 6.990610-4 6.218640-4 5.596050-4 5.048120-4 92533 16 223 4.555230-4 4.121780-4 3.758470-4 3.473540-4 3.269110-4 3.140740-4 92533 16 224 3.073570-4 3.120960-4 3.231580-4 3.310920-4 3.298620-4 3.041000-4 92533 16 225 2.525070-4 2.039030-4 1.464150-4 3.648070-3 2.360540-3 1.449110-3 92533 16 226 9.104930-4 6.319380-4 5.059420-4 4.569550-4 4.388680-4 4.266530-4 92533 16 227 4.088340-4 3.819840-4 3.470900-4 3.071470-4 2.656870-4 2.259100-4 92533 16 228 1.902720-4 1.486420-4 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