IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 29063.0000 62.3894000 0 0 41 12925 1451 1 0.0 0.0 0 0 0 62925 1451 2 1.00000000 60000000.0 0 0 10 22925 1451 3 300.000000 0.0 1 0 701 102925 1451 4 29-Cu- 63 FEI EVAL-Jul06 K.I.Zolotarev 2925 1451 5 DIST-Sep06 2925 1451 6 ----BROND-2 MATERIAL 2925 2925 1451 7 -----INCIDENT NEUTRON DATA 2925 1451 8 ------ENDF-6 FORMAT 2925 1451 9 ******************************************************************2925 1451 10 IAEA, June 2012 (A. Trkov) 2925 1451 11 Original evaluated file cu63n2n-dos.endf by Zolotarev was edited 2925 1451 12 manually to insert (n,tot), (n,el), (n,g) and (n,a) from IRDF-20022925 1451 13 Cross sections and covariances were extended from 20 to 60 MeV 2925 1451 14 by TENDL-2011, renormalised for continuity. 2925 1451 15 Additional points were added at threshold for consistency with Q 2925 1451 16 ******************************************************************2925 1451 17 ***************************************************************** 2925 1451 18 * Extension to the International Reactor Dosimetry Library * 2925 1451 19 * supported partially by the International Atomic Energy Agency * 2925 1451 20 * through IAEA research contract 13335. * 2925 1451 21 * Published as a technical report INDC(NDS)-0526 (2008). * 2925 1451 22 * Available online at * 2925 1451 23 * http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/ * 2925 1451 24 * indc-nds-0526.pdf * 2925 1451 25 ***************************************************************** 2925 1451 26 ------Russian Reactor Dosimetry File RRDF-2006 (n,2n), (n,a) 2925 1451 27 ------IRDF-2002 (ENDF/B-VI.8) reactions (n,tot), (n,el), (n,g) 2925 1451 28 ***************************************************************** 2925 1451 29 Author of evaluation: K.I.Zolotarev 2925 1451 30 ***************************************************************** 2925 1451 31 MF=3 2925 1451 32 MT= 16 - (n,2n) cross section 2925 1451 33 ------------------------------------- 2925 1451 34 Microscopic experimental data [1-41] were analyzed in the 2925 1451 35 process of preparation of input data base for the evaluation of 2925 1451 36 cross sections and their uncertainty for the Cu-63(n,2n)Cu-62 2925 1451 37 reaction. During this procedure experimental data [1-2], [9-10], 2925 1451 38 [12], [16-17], [21-22], [25-27], [29], [31], [34], [36-38], [40] 2925 1451 39 were corrected to the new recommended cross section data for moni-2925 1451 40 tor reactions used in the measurements and to the new recommended 2925 1451 41 decay data from ref. [42] and [43]. 2925 1451 42 Excitation function for the Cu-63(n,2n)Cu-62 reaction in the 2925 1451 43 energy region from threshold to 20 MeV was evaluated by means of 2925 1451 44 statistical analysis of experimental cross section data [1-29]. 2925 1451 45 Carefully analysis of experimental cross section data for the 2925 1451 46 reaction Cu-63(n,2n)Cu-62 between 13 - 15 MeV show that the more 2925 1451 47 representative in this energy range are data measured by De Juren 2925 1451 48 and Stooksberry [5], Sakisaka et al. [6], Glover and Weigold [9], 2925 1451 49 Grimeland et al. [15], Qaim [21], Valconen [23], Ryves et al.[26],2925 1451 50 Ghanbari and Robertson [27]. New experimental data of Sakane et 2925 1451 51 al. [28] and Mannhart and Schmidt [29] are agree within uncerta- 2925 1451 52 inties with these data. 2925 1451 53 Results of the relative measurements of Koehler and Alford 2925 1451 54 [11], Rayburn [12], Csikai [14] and Cuzzocrea et al. [20] were 2925 1451 55 corrected to the Cu-63(n,2n)Cu 62 reaction cross section data ob- 2925 1451 56 tained at the normalizing neutron energies from preliminary evalu-2925 1451 57 ation carried out on the basis of experimental data [5], [6], [9],2925 1451 58 [15], [21], [26-29]. 2925 1451 59 The results of preliminary evaluation was used also for cor- 2925 1451 60 rection of experimental data [16] and [25]. Data of Liskien and 2925 1451 61 Paulsen [16] were renormalized to the integral of cross section 2925 1451 62 calculated from preliminary evaluated excitation function in the 2925 1451 63 energy interval 13.5 - 15.5 MeV. After applied corrections to the 2925 1451 64 new standards data of Liskien and Paulsen were multiplied to the 2925 1451 65 factor Fc=0.81256 . Cross section data of Jarjis [25] measured in 2925 1451 66 the energy interval 12.92-14.91 MeV by means of Van de Graaff fa- 2925 1451 67 cility were renormalized to the preliminary evaluated integral of 2925 1451 68 cross section between 13.86 - 14.77 MeV. Total correction factor 2925 1451 69 for these experimental data was equal Fc=0.98690 . 2925 1451 70 In the energy region above 15 MeV the more representative are 2925 1451 71 experimental data of Ryves et al. [26]. Cross sections given in 2925 1451 72 the Ref. [26] were obtained in two series measurements carried 2925 1451 73 out with different monitor reactions. The results of these measu- 2925 1451 74 rements are agree well in all energy points in the investigated 2925 1451 75 range 14.67 - 18.95 MeV. 2925 1451 76 Experimental data of Brolley et al. [2] and experimental data 2925 1451 77 of Jarjis [25] obtained by means of Dinamitron accelerator in the 2925 1451 78 energy interval 13.24-15.94 MeV were renormalized to the integral 2925 1451 79 of cross section calculated from the experimental data of Ryves 2925 1451 80 et al. [26] in the overlapping energy ranges. Total correction fa-2925 1451 81 ctors for these experimental data were Fc=0.85715 and Fc=0.89123, 2925 1451 82 respectively. 2925 1451 83 Total uncertainty of 3.9 % and 5 % were assigned, respective- 2925 1451 84 ly, to the cross section data from Refs. [14] and [17]. Systema- 2925 1451 85 tic errors were evaluated and added to the experimental data [6], 2925 1451 86 [21], [22l and [27]. 2925 1451 87 Experimental data for the Cu-63(n,2n)Cu-62 reaction given in 2925 1451 88 the Ref. [12] were used partially. Data obtained in this work 2925 1451 89 above 15 MeV were rejected due to systematical underestimation of 2925 1451 90 cross sections. 2925 1451 91 Cross section data given in the ref. [30-41] were rejected 2925 1451 92 completely due to their big discrepancy with the main bulk of ex- 2925 1451 93 perimental data. In the rejected experimental data [32], [38] and 2925 1451 94 [40] cross section values were measured only in a one or two ener-2925 1451 95 gy points in the interval 14 - 15 MeV. 2925 1451 96 Statistical analysis of input cross section data was carried 2925 1451 97 out by means of PADE-2 code [44]. Rational function was used as 2925 1451 98 the model function [45]. 2925 1451 99 Evaluated excitation function for the reaction Cu63(n,2n)Cu62 2925 1451 100 was tested with using integral experimental data [46] for U-235 2925 1451 101 thermal fission spectrum [47] and Cf-252 spontaneous fission neut-2925 1451 102 ron spectrum [48]. Calculated and measured integral cross section 2925 1451 103 values are given below in the table 1. 2925 1451 104 Table 1 2925 1451 105 ================================================================= 2925 1451 106 TYPE OF SPECTRUM ,mb (calc.) , mb (measured) 2925 1451 107 ----------------------------------------------------------------- 2925 1451 108 U-235 neutron fission 0.09061 0.1184 +- 0.0070 [46] 2925 1451 109 ----------------------------------------------------------------- 2925 1451 110 CF-252 spont. fission 0.19843 0.1844 +- 0.0073 [46] 2925 1451 111 ================================================================= 2925 1451 112 2925 1451 113 MF=33 2925 1451 114 MT= 16 - (n,2n) cross section cov. matrix 2925 1451 115 ----------------------------------------- 2925 1451 116 Uncertainties in the evaluated excitation function for the 2925 1451 117 reaction Cu-63(n,2n)Cu-62 are given in the form of relative cova- 2925 1451 118 riance matrix for the 33-neutron energy groups (LB=5). Covariance 2925 1451 119 matrix of uncertainties was calculated simultaneously with 2925 1451 120 recommended cross section data by means of PADE-2 code [44]. 2925 1451 121 Eigenvalues of the 6-th digits relative covariance matrix 2925 1451 122 given in the 33-file are the following: 2925 1451 123 2925 1451 124 7.42042E-07 7.59925E-07 7.90851E-07 8.38334E-07 2925 1451 125 8.81284E-07 9.11081E-07 9.45308E-07 9.84989E-07 2925 1451 126 1.03138E-06 1.08588E-06 1.15052E-06 1.22803E-06 2925 1451 127 1.32202E-06 1.43773E-06 1.58233E-06 1.76682E-06 2925 1451 128 2.00726E-06 2.32906E-06 2.77323E-06 3.40949E-06 2925 1451 129 4.36207E-06 5.86939E-06 8.41904E-06 1.31240E-05 2925 1451 130 2.28475E-05 4.64323E-05 1.54121E-04 3.25466E-04 2925 1451 131 1.37825E-03 1.66307E-03 4.12994E-03 4.93817E-03 2925 1451 132 2.03005E-02 2925 1451 133 2925 1451 134 References : 2925 1451 135 1. J.L.Fowler, J.M.Slye Phys. Rev., v.77, p.787, March 1950 2925 1451 136 2. J.E.Brolley Phys. Rev., v.88, p.618, November 1952 2925 1451 137 3. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31, p.267, 1953 2925 1451 138 4. J.M.Ferguson, W.E.Thompson Phys. Rev., v.118, p.228, 1960 2925 1451 139 5. J.A.De Juren, R.W.Stooksberry Phys. Rev., v.120, p.901, 1960 2925 1451 140 6. M.Sakisaka et al. J. Phys. Soc. Japan, v.16, p.1869, 1961 2925 1451 141 7. H.Pollehn, H.Neuert Zeitschrift f. Naturforschung, sec.A, 2925 1451 142 v.16, p.227, 1961 2925 1451 143 8. M.Cevolani, S.Petralia Nuovo Cimento, v.26, p.1328, 1962 2925 1451 144 9. R.N.Glover, E.Weigold Nucl. Phys., v.29, p.309, 1962 2925 1451 145 10. J.Kantele, D.G.Gardner Nucl. Phys., v.35, p.353, 1962 2925 1451 146 11. D.R.Koehler, W.L.Alford Report, NP-11667, 1962 2925 1451 147 12. L.A.Rayburn Phys. Rev., v.130, p.731, 1963 2925 1451 148 13. J.Letessier, J.Dalmas J. Comptes Rendus, v.257, p.4620, 2925 1451 149 December 1964 2925 1451 150 14. J.Csikai Report, EANDC-50S,(2), paper 102, July 1965 2925 1451 151 15. B.Grimeland et al. Phys. Rev., v.B137, p.878, February 1965 2925 1451 152 16. H.Liskien, A.Paulsen J. Nucl. Energy, v.19, p.73, Feb. 1965 2925 1451 153 17. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 2925 1451 154 18. A.Pasquarelli Nucl. Phys., pt.A, v.93, p.218, March 1967 2925 1451 155 19. A.Chatterjee, A.Nath, A.M.Ghose Progress Report, BARC-305, 2925 1451 156 p.30, October 1967 2925 1451 157 20. P.Cuzzocrea et al. Nuovo Cimento, Sec. B, v.54, p.53, 2925 1451 158 March 1968 2925 1451 159 21. S.M.Qaim Nuclear Physics, v. A185, p.614, May 1972 2925 1451 160 22. R.Mogharrab, H.Neuert Atomkernenergie, v.19, p.107, Apr. 1972 2925 1451 161 23. M.Valkonen Report JU-RR-1/1976, Jyvaeskylae University, 1976 2925 1451 162 24. M.Majumder, B.Mitra Transactions of the Bose Research Inst., 2925 1451 163 v.40, p.81, Calcutta, 1977 2925 1451 164 25. R.A.Jarjis J. of Physics, pt.G, v.4, n.3, p.445, 1978 2925 1451 165 26. T.B.Ryves et al. J. Metrologia, v.14, n.3, p.127, June 1978 2925 1451 166 27. F.Ghanbari, J.C.Robertson Annals of Nucl. Energy, v.13, n.6, 2925 1451 167 pp.301-306, June 1986 2925 1451 168 28. H.Sakane et al. Annals of Nuclear Energy, v.28, p.1175, 2001 2925 1451 169 29. W.Mannhart, D.Schmidt Measurement of Neutron Cross Sections 2925 1451 170 between 8 and 14 MeV. Proc. of Int. Conf. on Nuclear Data for 2925 1451 171 Science and Technology, Santa Fe, New Mexico, USA, September 2925 1451 172 26 - October 1 2004, Part One, pp. 609-612 2925 1451 173 30. S.G.Forbes Phys. Rev., v.88, p.1309, December 1952 2925 1451 174 31. A.V.Cohen, P.H.White Nucl. Phys., v.1, p.73, February 1956 2925 1451 175 32. S.Yasumi J. Phys. Soc. Japan, v.12, p.443, May 1957 2925 1451 176 33. J.H.Mc Crary, I.L.Morgan Bull. American Phys. Soc., v.5, 2925 1451 177 p.246, April 1960 2925 1451 178 34. M.Bormann et al. Zeitsch. f. Physik, v.166, p.477, 2925 1451 179 February 1962 2925 1451 180 35. G.Bardolle et al. J. Comptes Rendus, v.261, p.1266, Aug. 1965 2925 1451 181 36. M.F.Andreev, V.I.Serov Yadernaya Fizika (Sov.), v.7, p.745, 2925 1451 182 April 1968 2925 1451 183 37. M.Bormann, B.Lammers Progress Report, EANDC(E)-115U, 2925 1451 184 March 1969 ; 2925 1451 185 M.Bormann, B.Lammers Nucl. Phys., v.A130, p.195, June 1969 2925 1451 186 38. D.Crumpton et al. J. Inorg. Nucl. Chem., v. 31, pp. 1-8, 2925 1451 187 January 1969 2925 1451 188 39. A.Chatterjee et al. Proc. of the 12th Nucl. Phys. and Solid 2925 1451 189 State Phys. Symposium, Roorkee, 28-31 December 1969, v.2, 2925 1451 190 p. 117, 1969 2925 1451 191 40. R.A.Sigg Dissertation Abstract, sec.B, v.37, p.2237, 2925 1451 192 November 1976 2925 1451 193 41. Y.Uwamino, H.Sugita, Y.Kondo, T.Nakamura Nucl. Sci. Eng., 2925 1451 194 v. 111, p. 391, 1992 2925 1451 195 42. Decay Radiation Data Base, version 11/28/2005, 2925 1451 196 http://www.nds.iaea.org/nudat2/dec 2925 1451 197 43. R.B.Firestone Table of Isotopes, Eighth edition, Vol. 1, 2925 1451 198 John Wiley & Sons, Inc., New York, 1995 2925 1451 199 44. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 2925 1451 200 45. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2925 1451 201 st's Meeting on Evaluation and Processing of Covariance Data, 2925 1451 202 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 2925 1451 203 46. W.Mannhart Validation of Differential Cross Sections with 2925 1451 204 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2925 1451 205 September 2002 2925 1451 206 47. L.W.Weston et al. Evaluated Neutron Data for Uranium-235, 2925 1451 207 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 2925 1451 208 48. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 2925 1451 209 2925 1451 210 MF=3 2925 1451 211 MT=107 (n,a) cross section 2925 1451 212 Evaluation of Cu-63(n,a)Co-60m+g- excitation function was car-2925 1451 213 ried out by means of statistical analysis of cross sections from 2925 1451 214 data base prepared in the energy range 2 - 20 Mev. In the energy 2925 1451 215 range 3.56 - 19.55 MeV input data base was formed with using of 2925 1451 216 experimental data from ref. [1-19]. Cross section data in the 2925 1451 217 interval 2.0 - 3.5 MeV were taken from theoretical model calcula- 2925 1451 218 tion. Experimental data included in the input data base were 2925 1451 219 renormalized using new cross sections standards for monitor reac- 2925 1451 220 tions and new standards for decay data. 2925 1451 221 The special correction was applied to the experimental data 2925 1451 222 [2,3,12,13,15,18]. Cross section data of A.Paulsen and H.Liskien 2925 1451 223 [2-3] measured in the energy region 12.09 - 19.55 MeV with using 2925 1451 224 T(d,n)He4 neutron source were multiplied to the factor 1.20805 . 2925 1451 225 Experimental data of Lu Hanlin et al. [12,18] , Wang Yongchag et 2925 1451 226 al. [13] and Konno et al. [15] were multiplied to the factors 2925 1451 227 0.88110, 0.86000, 0.84377 and 1.060, respectively. The correction 2925 1451 228 factors were derived from preliminary evaluated cross sections 2925 1451 229 integrals in the energy intervals 8.4 - 11.4 and 13 - 15 MeV . 2925 1451 230 Data of A.Paulsen and H.Liskien [2] in the energy range 2925 1451 231 5.76 - 11.48 MeV measured with using D(d,n)He3 , Be9(a,n)C12 , 2925 1451 232 C14(d,n)N15 , N15(d,n)O16 neutron sources were rejected due to 2925 1451 233 their inconsistency with precision measurements of G.Winkler et 2925 1451 234 al. [8] and integral experimental data for U-235 fission neutron 2925 1451 235 spectrum [20-23] and Cf-252 spontaneous fission neutron spectrum 2925 1451 236 [25-26]. Cross sections measured by J.Kantele and D.Gardner [27], 2925 1451 237 M.Bormann et al. [28], G.Maslov et al. [29] and K.Kayashima et al.2925 1451 238 [30] were also rejected due to the big discrepancy with the main 2925 1451 239 bulk experimental data. 2925 1451 240 The final procedure evaluation of (n,a) excitation function 2925 1451 241 was carried out by means of Pade-2 code [31]. 2925 1451 242 Evaluated excitation function for the reaction Cu63(n,a)Co60 2925 1451 243 was tested with using integral experimental data [20-24] for 2925 1451 244 U-235 thermal fission neutron spectrum and evaluated integral ex- 2925 1451 245 perimental data [32-33] for Cf-252 spontaneous fission neutron 2925 1451 246 spectrum. Calculated and measured average cross section values 2925 1451 247 for U-235 thermal fission neutron spectrum [34] and Cf-252 sponta-2925 1451 248 neous fission neutron spectrum [35] are given in the table 1. 2925 1451 249 Table 1 2925 1451 250 ----------------------+-----------------+----------------------- 2925 1451 251 Type of spectrum | ,mb (calc.) | , mb (measured) 2925 1451 252 ----------------------+-----------------+----------------------- 2925 1451 253 U-235 neutron fission | 0.53048 | 0.5255 +- 0.0316 [20] 2925 1451 254 | | 0.520 +- 0.040 [21] 2925 1451 255 | | 0.518 +- 0.035 [22] 2925 1451 256 | | 0.5255 +- 0.0156 [23] 2925 1451 257 | | 0.536 +- 0.015 [23] 2925 1451 258 | | 0.4935 +- 0.0242 [24] 2925 1451 259 | | 0.4918 +- 0.0241 [33] 2925 1451 260 ----------------------+-----------------+----------------------- 2925 1451 261 CF-252 spont. fission | 0.69351 | 0.709 +- 0.017 [25] 2925 1451 262 | | 0.675 +- 0.018 [26] 2925 1451 263 | | 0.6897 +- 0.0130 [32] 2925 1451 264 | | 0.6887 +- 0.0135 [33] 2925 1451 265 ----------------------+-----------------+----------------------- 2925 1451 266 2925 1451 267 MF=33 2925 1451 268 MT=107(n,a) cross section cov. matrix- 2925 1451 269 Uncertainties in the evaluated excitation function for the 2925 1451 270 reaction Cu-63(n,a)Co-60m+g are given in the form of relative co- 2925 1451 271 variance matrix for the 25-neutron energy groups (LB=5). Covari- 2925 1451 272 ance matrix of uncertainties was calculated simultaneously with 2925 1451 273 recommended cross section data by means of PADE-2 code. 2925 1451 274 Eigenvalues of the 6-th digits relative covariance matrix 2925 1451 275 given in the 33-file are the following: 2925 1451 276 2925 1451 277 6.72257E-07 6.90982E-07 7.26610E-07 7.80996E-07 2925 1451 278 8.73734E-07 1.00295E-06 1.14889E-06 1.39338E-06 2925 1451 279 1.71680E-06 1.98760E-06 2.46713E-06 3.21657E-06 2925 1451 280 4.04399E-06 4.67325E-06 6.03008E-06 8.12500E-06 2925 1451 281 2.08229E-05 2.99016E-04 1.40310E-03 1.73651E-03 2925 1451 282 2.36498E-03 2.92692E-03 6.39266E-03 1.70593E-02 2925 1451 283 8.28804E-02 2925 1451 284 2925 1451 285 References: 2925 1451 286 1. B.Czapp, H.Vonach, Oesterr. Akad. Wiss, Math, Naturw. 2925 1451 287 Anzeiger, v.97, p.13, January 1960 2925 1451 288 2. A.Paulsen, H.Liskien, Nukleonik, v.10, p.91, July 1967 2925 1451 289 3. A.Paulsen, Zeitschrift f. Phys., v.205, p.226, August 1967 2925 1451 290 4. R.C.Barrall et al., Report AFWL-TR-68-134, March 1969 2925 1451 291 6. G.Winkler, Nucl. Sci. Eng., v.67, n.2, p.260, August 1978 2925 1451 292 8. G.Winkler, D.L.Smith, J.W.Meadows, Nucl. Sci. Eng., v.76, 2925 1451 293 p.30, October 1980 2925 1451 294 9. U.Garuska et al., Prog. Report INDC(POL)-11, p.15, July 1980 2925 1451 295 10. O.I.Artem'ev et al., Atomnaja Energija (Sov.), v.49, n.3, 2925 1451 296 p.195, September 1980 2925 1451 297 11. L.R.Greenwood, Progress Report ASTM-STP-956, p.743, 1987 2925 1451 298 12. Lu Hanlin et al., China Journal of Nuclear Phys., v.12. n.4, 2925 1451 299 p. 373, 1990 2925 1451 300 13. Wang Yongchang et al., Chinese J. High Energy Phys. and Nucl. 2925 1451 301 Phys., v.14, p.919, October 1990 2925 1451 302 14. J.Csikai, C.M.Buczko, R.Pepelnik, H.M.Agrawal Annals of Nucl. 2925 1451 303 Energy, v.18, n.1, p.1, 1991 2925 1451 304 15. C.Konno et al., Report JAERI-1329, October 1993 2925 1451 305 16. J.W.Meadows et al., Annals of Nucl. Energy, v.23, p.877, 1996 2925 1451 306 17. A.A.Filatenkov et al., VANT, Ser.: Yadernye Konstanty, v.2, 2925 1451 307 p.8, Moscow, 1996 2925 1451 308 18. Lu Hanlin et al., Report INDC(CPR)-045, IAEA, October 1998 2925 1451 309 19. A.A.Filatenkov et al., Report RI-252, St.Petersburg, May 1999 2925 1451 310 20. R.Lloret, Progress Report EANDC(E)-57, p.172, February 1965 2925 1451 311 21. A.Fabry, J.P.Deworm, Progress Report EANDC(E)-66, p.125, 2925 1451 312 February 1966 2925 1451 313 22. K.Kobayashi et al., Nucl. Sci. Techn., v.13, p.531, Oct. 1976 2925 1451 314 23. L.P.Geraldo et al., Radiochimica Acta, v.57, pp.63-67, 1992 2925 1451 315 24. W.Mannhart, Progress Report INDC(Ger)-045, pp.40-43, 1999 2925 1451 316 25. G.Winkler et al., Nucl. Sci. Eng., v.78, p.415, August 1981 2925 1451 317 26. W.Mannhart, Proc. of Int. Conf. Nuclear Data for Science and 2925 1451 318 Technology, 6-10 September 1982, Antwerp, Holland, D.Reidel 2925 1451 319 Publishing Company, p.429 2925 1451 320 27. J.Kantele, D.Gardner, Nucl. Phys., v.35, p.353, 1962 2925 1451 321 28. M.Bormann et al., Nucl. Phys., v.A186, p.65, May 1972 2925 1451 322 29. G.N.Maslov, F.Nasyrov, N.F.Pashkin, Yadernye Konstanty, v.9, 2925 1451 323 p.50, Obninsk, 1972 2925 1451 324 30. K.Kayashima et al., Prog. Rep. NEANDC(J)-61U, p.94, Sep. 1979 2925 1451 325 31. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 2925 1451 326 32. W.Mannhart, Handbook on Nuclear Activation Cross Sections, 2925 1451 327 IAEA Technical Report series No.273, p.413, 1987 2925 1451 328 33. W.Mannhart, Validation of Differential Cross Sections with 2925 1451 329 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 2925 1451 330 September 2002 2925 1451 331 34. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2925 1451 332 Library, MAT=9228, MF=5, MT=18, eval. April 1989 2925 1451 333 35. W.Mannhart, Report INDC(NDS)-220/L, p.158, IAEA, Vienna, 1989 2925 1451 334 ***************************************************************** 2925 1451 335 2925 1451 336 MF=3,33 2925 1451 337 MT=1,2,102 (n,tot), (n,el), (n,g) 2925 1451 338 2925 1451 339 ENDF/B-VI MOD 5 Revision, May 2000, S.C. Frankle, R.C. Reedy, 2925 1451 340 P.G. Young (LANL) 2925 1451 341 2925 1451 342 The secondary gamma-ray spectrum for radiative capture (MF 12, 2925 1451 343 MT 102) has been updated for new experimental data at incident 2925 1451 344 neutron energies up to 1 keV. The Q-value for radiative capture 2925 1451 345 was also updated in File 3. 2925 1451 346 Details of these changes are described in Frankel et al. [Fr01]. 2925 1451 347 2925 1451 348 **************************************************************** 2925 1451 349 2925 1451 350 ENDF/B-VI MOD 4 Evaluation, February 1998, A.J. Koning (ECN), 2925 1451 351 M.B. Chadwick, P.G. Young (LANL) 2925 1451 352 2925 1451 353 Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code 2925 1451 354 in cooperation with ECN Petten. 2925 1451 355 2925 1451 356 This evaluation provides a complete representation of the 2925 1451 357 nuclear data needed for transport, damage, heating, 2925 1451 358 radioactivity, and shielding applications over the incident 2925 1451 359 neutron energy range from 1.0E-11 to 150 MeV. The discussion 2925 1451 360 here is divided into the region below and above 20 MeV. 2925 1451 361 2925 1451 362 INCIDENT NEUTRON ENERGIES < 20 MeV 2925 1451 363 2925 1451 364 Below 20 MeV the evaluation is based completely on the ENDF/B- 2925 1451 365 VI (Mod 3) evaluation by D. Hetrick, C.Y. Fu, and D. Larson. 2925 1451 366 2925 1451 367 INCIDENT NEUTRON ENERGIES > 20 MeV 2925 1451 368 2925 1451 369 The ENDF/B-VI Release 2 evaluation extends to 20 MeV and 2925 1451 370 includes cross sections and energy-angle data for all 2925 1451 371 significant reactions. The present evaluation utilizes a more 2925 1451 372 compact composite reaction spectrum representation above 20 MeV 2925 1451 373 in order to reduce the length of the file. No essential data for 2925 1451 374 applications is lost with this representation. 2925 1451 375 The evaluation above 20 MeV utilizes MF=6, MT=5 to represent 2925 1451 376 all reaction data. Production cross sections and emission 2925 1451 377 spectra are given for neutrons, protons, deuterons, tritons, 2925 1451 378 alpha particles, gamma rays, and all residual nuclides produced 2925 1451 379 (A>5) in the reaction chains. To summarize, the ENDF sections 2925 1451 380 with non-zero data above En = 20 MeV are: 2925 1451 381 2925 1451 382 MF=3 MT= 1 Total Cross Section 2925 1451 383 MT= 2 Elastic Scattering Cross Section 2925 1451 384 MT= 3 Nonelastic Cross Section 2925 1451 385 MT= 5 Sum of Binary (n,n') and (n,x) Reactions 2925 1451 386 2925 1451 387 MF=4 MT= 2 Elastic Angular Distributions 2925 1451 388 2925 1451 389 MF=6 MT= 5 Production Cross Sections and Energy-Angle 2925 1451 390 Distributions for Emission Neutrons, Protons, 2925 1451 391 Deuterons, Tritons, and Alphas; and Angle- 2925 1451 392 Integrated Spectra for Gamma Rays and Residual 2925 1451 393 Nuclei That Are Stable Against Particle Emission 2925 1451 394 2925 1451 395 The evaluation is based on nuclear model calculations that 2925 1451 396 have been benchmarked to experimental data, especially for n + 2925 1451 397 Cu65 and p + Cu65 reactions [Ch98]. We use the GNASH code system 2925 1451 398 [Yo92], which utilizes Hauser-Feshbach statistical, preequilib- 2925 1451 399 rium and direct-reaction theories. Spherical optical model 2925 1451 400 calculations are used to obtain particle transmission 2925 1451 401 coefficients for the Hauser-Feshbach calculations, as well as 2925 1451 402 for the elastic neutron angular distributions. 2925 1451 403 Cross sections and spectra for producing individual residual 2925 1451 404 nuclei are included for reactions. The energy-angle-correlations 2925 1451 405 for all outgoing particles are based on Kalbach systematics 2925 1451 406 [Ka88]. 2925 1451 407 A model was developed to calculate the energy distributions of 2925 1451 408 all recoil nuclei in the GNASH calculations [Ch96a]. The recoil 2925 1451 409 energy distributions are represented in the laboratory system in 2925 1451 410 MT=5, MF=6, and are given as isotropic in the lab system. All 2925 1451 411 other data in MT=5,MF=6 are given in the center-of-mass system. 2925 1451 412 This method of representation utilizes the LCT=3 option approved 2925 1451 413 at the November, 1996, CSEWG meeting. 2925 1451 414 Preequilibrium corrections were performed in the course of the 2925 1451 415 GNASH calculations using the exciton model of Kalbach [Ka77, 2925 1451 416 Ka85], validated by comparison with calculations using Feshbach, 2925 1451 417 Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from 2925 1451 418 nuclear data sheets were matched to continuum level densities 2925 1451 419 using the formulation of Ignatyuk et al. [Ig75] and pairing and 2925 1451 420 shell parameters from the Cook [Co67] analysis. Neutron and 2925 1451 421 charged- particle transmission coefficients were obtained from 2925 1451 422 the optical potentials, as discussed below. Gamma-ray 2925 1451 423 transmission coefficients were calculated using the Kopecky-Uhl 2925 1451 424 model [Ko90]. 2925 1451 425 2925 1451 426 SPECIFIC INFORMATION CONCERNING THE 63Cu EVALUATION 2925 1451 427 2925 1451 428 This evaluation is documented in some detail in Ref. [Ko98b]. 2925 1451 429 2925 1451 430 The neutron total cross section above 20 MeV was obtained by 2925 1451 431 evaluating experimental data, with a particular emphasis on the 2925 1451 432 Finlay [Fi93] elemental data. This resulted in an evaluated 2925 1451 433 elemental Cu total cross section; to obtain an isotopic 63Cu total2925 1451 434 cross section, it was assumed that 63Cu and 65Cu have total cross 2925 1451 435 sections in an A**2/3 ratio to one another. The total neutron 2925 1451 436 nonelastic cross section was obtained directly from an optical 2925 1451 437 model calculation (see below), after verifying that it was in good2925 1451 438 agreement with the experimental data [Ko98b]. 2925 1451 439 2925 1451 440 To obtain the neutron optical potential we used total cross 2925 1451 441 section data from 1.2 to 4.5 MeV [Gu86] and from 5.3 to 600 MeV 2925 1451 442 [Fi93], and elastic scattering angular distribution data from 1.6 2925 1451 443 to 96 MeV [Br50, Sa60, Ki74, El82, Gu86]. The optical potential 2925 1451 444 parameters were obtained using a combination of a grid search code2925 1451 445 and the interactive optical model viewer ECISVIEW [Ko97], both 2925 1451 446 built around the coupled channels code ECIS96 [Ra94]. The energy 2925 1451 447 dependence of the optical model parameters is as described in 2925 1451 448 [Ko98]. This optical potential was used for the calculation, with 2925 1451 449 ECIS96, of neutron transmission coefficients and DWBA cross 2925 1451 450 sections for the entire energy region above 20 MeV. 2925 1451 451 2925 1451 452 Due to the lack of proton elastic scattering data in numerical 2925 1451 453 form, we used a combination of global optical models for the 2925 1451 454 proton channel. The Becchetti-Greenlees potential [Be69]was 2925 1451 455 adopted below 47 MeV, and the non-relativistic version of the 2925 1451 456 Madland potential [Ma88] above 47 MeV. At this particular energy 2925 1451 457 point the two potentials join smoothly. 2925 1451 458 2925 1451 459 For deuterons, the Lohr-Haeberli global potential [Lo74] was used;2925 1451 460 for alpha particles the Moyen potential (MacFadden-Satchler 2925 1451 461 [Ma66]) was used; and for tritons the Becchetti-Greenlees 2925 1451 462 potential [Be71] was used. The He-3 channel was ignored, due to 2925 1451 463 its small importance. 2925 1451 464 2925 1451 465 Following Delaroche et al. [De82], we adopted the weak-coupling 2925 1451 466 model for direct collective inelastic scattering for Cu-63, using 2925 1451 467 Ni-64 as a basis. For the calculation of the cross sections, 2925 1451 468 ECIS96 was used in DWBA mode. We used the following direct 2925 1451 469 transitions for Cu-63 (ground state 3/2- ) : 2925 1451 470 2925 1451 471 Jpi Ex(MeV) Deformation lengths 2925 1451 472 0.5- 0.669 Delta(2)=0.319 2925 1451 473 2.5- 0.962 Delta(2)=0.552 2925 1451 474 3.5- 1.327 Delta(2)=0.638 2925 1451 475 1.5- 1.547 Delta(2)=0.451 2925 1451 476 1.5- 3.382 Delta(3)=0.313 2925 1451 477 2.5- 3.632 Delta(3)=0.384 2925 1451 478 3.5- 3.882 Delta(3)=0.444 2925 1451 479 4.5- 4.132 Delta(3)=0.496 2925 1451 480 2925 1451 481 No measurements exist for neutron-induced emission spectra above 2925 1451 482 20 MeV for 63Cu. However, for Cu-65 there exists 25.7 MeV (n,xn) 2925 1451 483 data by Marcinkowski et al [Ma83]. This has been used to benchmark2925 1451 484 the Cu-65 data. Without adjusting any of the level density or pre-2925 1451 485 equilibrium parameters the GNASH calculation was in good agreement2925 1451 486 with these data. Hence we also adopted these parameters for the 2925 1451 487 whole energy region for Cu-63. 2925 1451 488 2925 1451 489 **************************************************************** 2925 1451 490 2925 1451 491 REFERENCES 2925 1451 492 2925 1451 493 [Ab93] W. Abfalterer, R.W. Finlay, S.M. Grimes, and V. Mishra, 2925 1451 494 Phys.Rev. C47, 1033 (1993) 2925 1451 495 [Al83] R. Alarcon and J. Rapaport, Nucl.Phys. A458, 502 (1986) 2925 1451 496 [Ar80] E.D. Arthur and P.G. Young, 'Evaluation of Neutron Cross 2925 1451 497 Sections to 40 MeV for 54,56Fe," Proc. Sym. on Neutron Cross 2925 1451 498 Sections from 10 to 50 MeV, 12-14 May 1980, Brookhaven National2925 1451 499 Laboratory [Eds. M. R. Bhat and S. Pearlstein, BNL-NCS- 51245, 2925 1451 500 1980] p. 731. 2925 1451 501 [Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182, 2925 1451 502 1190 (1969) 2925 1451 503 [Be71] F.D. Becchetti, Jr., and G.W. Greenlees in "Polarization 2925 1451 504 Phenomena in Nuclear Reactions," (Ed: H.H. Barschall and W. 2925 1451 505 Haeberli, The University of Wisconsin Press, 1971) p.682. 2925 1451 506 [Be92] O. Bersillon, "SCAT2 - A Spherical Optical Model Code," 2925 1451 507 in Proc. ICTP Workshop on Computation and Analysis of Nuclear 2925 1451 508 data Relevant to Nuclear Energy and Safety, February-March, 2925 1451 509 1999 Trieste, Italy, to be published in World Scientific Press,2925 1451 510 and Progress Report of the Nuclear Physics Division, Bruyeres- 2925 1451 511 le-Chatel 1977, CEA-N-2037 (1978) p.111 2925 1451 512 [Br50] S. Bratenahl, S. Fernbach, R.H. Hildebrand et al., 2925 1451 513 Phys.Rev. 77, 597 (1950) 2925 1451 514 [Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) 2925 1451 515 [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. 2925 1451 516 Koning, "High-Energy Nuclear Data Libraries for Accelerator- 2925 1451 517 Driven Technologies: Calculational Method for Heavy Recoils," 2925 1451 518 Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation 2925 1451 519 Technology and Applications, Kalmar, Sweden, 3-7 June 1996 2925 1451 520 [Ch98] M. B. Chadwick and P. G. Young, "GNASH Calculations of 2925 1451 521 n,p + Cu isotopes and Benchmarking of Results" in APT PROGRESS 2925 1451 522 REPORT: 1 February - 1 March 1998, internal Los Alamos National2925 1451 523 Laboratory memo, 6 Mar.1998 from R.E. MacFarlane to L. Waters. 2925 1451 524 [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos 2925 1451 525 National Laboratory report, LA-UR-99-1222 (1999) 2925 1451 526 [Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J. 2925 1451 527 Phys. 20, 477 (1967) 2925 1451 528 [De82] J.P. Delaroche, S.M. El-Kadi, P.P. Guss, C.E. Floyd and 2925 1451 529 R.L. Walter, Nucl. Phys. A390, 541 (1982). 2925 1451 530 [El82] S.M. El-Kadi, C.E. Nelson, F.O. Purser et al., Nucl.Phys. 2925 1451 531 A390, 509 (1982) 2925 1451 532 [Fi93] R. W. Finlay, W. P. Abfalterer, G. Fink et al., Phys.Rev. 2925 1451 533 C 47, 237 (1993) 2925 1451 534 [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos 2925 1451 535 National Laboratory Report, LA-13812 (2001). 2925 1451 536 [Gu86] P. Guenther, D.L. Smith, A.B. Smith, J.F. Whalen, Nucl. 2925 1451 537 Phys. A448, 280 (1986) 2925 1451 538 [Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. 2925 1451 539 Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485 2925 1451 540 (1975) 2925 1451 541 [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) 2925 1451 542 [Ka85] C. Kalbach, Los Alamos National Laboratory report 2925 1451 543 LA-10248-MS (1985) 2925 1451 544 [Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also 2925 1451 545 C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981) 2925 1451 546 [Ki74] W.E. Kinney, F.G. Perey, Oak Ridge report ORNL-4908 (1974)2925 1451 547 [Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990) 2925 1451 548 [Ko97] A.J. Koning, J.J. van Wijk and J.-P. Delaroche, "ECISVIEW:2925 1451 549 A Graphical Interface for ECIS95", Proceedings of the NEA 2925 1451 550 Specialists' Meeting on the Nucleon Nucleus Optical Model up to2925 1451 551 200 MeV, Bruyeres-le-Chatel, November 13-15 1996. Available at 2925 1451 552 http://db.nea.fr/html/science/om200/. 2925 1451 553 [Ko98] A.J. Koning, J.-P. Delaroche and O. Bersillon, "Nuclear 2925 1451 554 Data for Accelerator-Driven Systems: Nuclear models, Experiment2925 1451 555 and Data Libraries", to appear in Mucl. Instr. Meth. A (1998). 2925 1451 556 [Ko98b] A.J. Koning, M.B. Chadwick, and P.G. Young, "ENDF/B-VI 2925 1451 557 neutron and proton datafiles up to 150 MeV for 63Cu and 65Cu", 2925 1451 558 Los Alamos National Laboratory report LAUR- (1998); ECN lab and2925 1451 559 JEFF report (1998). 2925 1451 560 [Lo74] J.M. Lohr and W. Haeberli, Nucl.Phys. A232, 381 (1974) 2925 1451 561 [Ma66] Macfadden and Satchler, Nuc.Phys. 84, 177 (1966) 2925 1451 562 [Ma83] A. Marcinkowski, R.W. Finlay, G. Randers-Pehrson et al., 2925 1451 563 Nucl.Phys. A402, 220 (1983) 2925 1451 564 [Ma88] D.G. Madland, "Recent Results in the Development of a 2925 1451 565 Global Medium-Energy Nucleon-Nucleus Optical-Model Potential, 2925 1451 566 "Proc. OECD/NEANDC Specialist's Mtg. on Preequilibrium Nuclear 2925 1451 567 Reactions, Semmering, Austria, 10-12 Feb. 1988, NEANDC-245 'U' 2925 1451 568 (1988). 2925 1451 569 [Pe63] C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963) 2925 1451 570 [Ra94] J. Raynal, Notes on ECIS94, CEA Saclay Report CEA-N-2772 2925 1451 571 (1994) 2925 1451 572 [Sa60] G.L. Salmon, Nucl.Phys. 21, 15 (1960) 2925 1451 573 [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report 2925 1451 574 LA-12343-MS (1992) 2925 1451 575 2925 1451 576 **************************************************************** 2925 1451 577 2925 1451 578 ENDF/B-VI MOD 3 Revision, July 1991 (ORNL) 2925 1451 579 2925 1451 580 MOD 3 changes 2925 1451 581 1) Corrections to MF=6, MT=65 at 17.0 MeV to prevent negative 2925 1451 582 values in the angular distribution. 2925 1451 583 2) Corrections to MF=33, MT=102 2925 1451 584 2925 1451 585 **************************************************************** 2925 1451 586 2925 1451 587 * Note there was no MOD 2 released. 2925 1451 588 2925 1451 589 **************************************************************** 2925 1451 590 2925 1451 591 ENDF/B-VI MOD 1 Evaluation, October 1989, D. Hetrick, F.Y. Fu, 2925 1451 592 D. Larson (ORNL) 2925 1451 593 2925 1451 594 This work employed several nuclear model codes including the 2925 1451 595 optical-model code GENOA [1], the Distorted Wave Born 2925 1451 596 Approximation (DWBA) program DWUCK [2], and the Hauser-Feshbach 2925 1451 597 code TNG [3,4]. The TNG code provides energy and angular 2925 1451 598 distributions of particles emitted in the compound and pre- 2925 1451 599 compound reactions, ensures consistency among all reactions, and 2925 1451 600 maintains energy balance. Details pertinent to the contents of 2925 1451 601 this evaluation and extensive comparisons of calculations with 2925 1451 602 experimental data can be found in reference [5]. 2925 1451 603 2925 1451 604 ----- DESCRIPTION OF FILES 2925 1451 605 (MF-MT) 2925 1451 606 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2925 1451 607 2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB[6]. POINT2925 1451 608 WISE RECONSTRUCTION COMPARED WITH DATA [7] SHOWED POORER 2925 1451 609 FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 2925 1451 610 99.5 KEV. REICH-MOORE PARAMETERS ARE GIVEN. AGREEMENT 2925 1451 611 WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND 2925 1451 612 FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN 2925 1451 613 AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND 2925 1451 614 COMPARED WITH THE BINNED DATA. THIS IS PROBABLY DUE TO 2925 1451 615 TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES 2925 1451 616 SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION. 2925 1451 617 NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION 2925 1451 618 OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE 2925 1451 619 PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON 2925 1451 620 A FINER ENERGY GRID THAN GIVEN IN 4/2. 2925 1451 621 3-1 THE TOTAL CROSS SECTION IS GIVEN BY RESONANCE PARAMETERS 2925 1451 622 FROM 1.E-5 EV TO 99.5 KEV. FROM 1.E-5 TO 1 EV, -0.9B IS 2925 1451 623 GIVEN TO REDUCE THE ELASTIC AND GIVE THE CORRECT TOTAL 2925 1451 624 THERMAL CROSS SECTION (9.6 B). FROM 1 EV TO 170 EV THIS 2925 1451 625 GOES LINEARLY TO ZERO. A SMALL CONTRIBUTION FROM 3/102 IS2925 1451 626 REQUIRED FROM 60 TO 99.5 KEV, WHICH WHEN ADDED TO 2/151 2925 1451 627 REPRODUCES THE CAPTURE DATA. FROM 99.5 KEV TO 1.12 MEV 2925 1451 628 CU63 DATA FROM [7] IS USED, AFTER APPROPRIATE AVERAGING. 2925 1451 629 ABOVE THIS, NO ISOTOPIC DATA IS AVAILABLE. FROM 1.12 TO 2925 1451 630 4.0 MEV,NAT CU DATA OF PEREY [8] USED IN V5 IS RETAINED. 2925 1451 631 FROM 4.0 TO 20 MEV, NAT CU DATA OF LARSON ET.AL [9] IS 2925 1451 632 AVERAGED AND USED. COMPARISONS FROM 1.2 TO 4.5 2925 1451 633 MEV WITH AVERAGED ARGONNE DATA FOR NAT CU [10] SHOW 2925 1451 634 1% AGREEMENT. 2925 1451 635 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY 2925 1451 636 SUBTRACTING THE NONELASTIC (3-3) FROM THE TOTAL. THE 2925 1451 637 THERMAL VALUE OF 5.1 B IS REPRODUCED. 2925 1451 638 3-102 (N,G) DATA TAKEN FROM RESONANCE PARAMETERS FROM 1.E-5 EVTO2925 1451 639 99.5 KEV. A SMALL BACKGROUND IS GIVEN HERE WHICH WHEN 2925 1451 640 ADDED TO THE RESONACE CONTRIBUTION REPRODUCES EXPERIMENTAL2925 1451 641 DATA,INCLUDING THE THERMAL VALUE OF 4.50B. V5 DATA FROM 2925 1451 642 99.5 KEV TO 20.0 MEV WERE REPLACED BY POINTS ON A CURVE 2925 1451 643 DRAWN THROUGH DATA FROM THE CSISRS LIBRARY [5,13]; RESULTS2925 1451 644 COMPARABLE TO EYE GUIDE IN REF [14]. 2925 1451 645 ---------------------------------------------------------------- 2925 1451 646 UNCERTAINTY FILES 2925 1451 647 ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS 2925 1451 648 REQUIRED BY ENDF/B-VI FORMATS 2925 1451 649 2925 1451 650 33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 200 EV 2925 1451 651 EXPLICIT FROM 200 EV TO 20 MEV, USING LB=0,1 AND 8. 2925 1451 652 33-2 EXPLICIT FROM 1E-5 T0 200 EV, DERIVED FROM 200EV TO 20 MEV2925 1451 653 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW 2925 1451 654 ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CSISRS 2925 1451 655 DATA [5,13,14] FROM 99.5 KEV TO 20 MEV. 2925 1451 656 **************************************************************** 2925 1451 657 2925 1451 658 REFERENCES: 2925 1451 659 2925 1451 660 [1] F.G. Perey, computer code GENOA, ORNL, unpublished (1967) 2925 1451 661 [2] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of 2925 1451 662 Colorado, unpublished (1972) 2925 1451 663 [3] C.Y. Fu, report ORNL/TM-7042 (1980); also, C.Y Fu, 2925 1451 664 Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, NY,2925 1451 665 May 1980, Brookhaven National Lab. report BNL-NCS-51245 2925 1451 666 (1980) p.675 2925 1451 667 [4] K. Shibata and C.Y. Fu, report ORNL/TM-10093 (1986) 2925 1451 668 [5] D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge report 2925 1451 669 ORNL/TM-9083 [ENDF-337] (1984) 2925 1451 670 [6] S.F. Mughabghab, M. Divadeenam, and N.E. Holden, "Neutron 2925 1451 671 Cross Sections, Vol. 1, Neutron Resonance Parameters and 2925 1451 672 Thermal Cross Sections, Part A, Z=1-60," (Academic Press, 2925 1451 673 1981) 2925 1451 674 [7] M.S. Pandey, J.B. Garg and J.A. Harvey, Phys.Rev. C 15, 600 2925 1451 675 (1977), and private communication. 2925 1451 676 [8] F.G. Perey, private communication (1977) 2925 1451 677 [9] D.C. Larson, Symp. on Neutron Cross Sections from 10 to 50 2925 1451 678 MeV, Upton, NY, May 1980, Brookhaven National Lab. report 2925 1451 679 BNL-NCS-51245 (1980) p.277 2925 1451 680 [10] P. Guenther, D.L. Smith, A.B. Smith and J.F. Whalen, Nucl. 2925 1451 681 Phys. A, 448, 280 (1986) [CSISRS data set 12869/002], and 2925 1451 682 W.P. Poenitz and J.F. Whalen, Argonne report ANL/NDM-80 2925 1451 683 (1983) [CSISRS data set 12853] 2925 1451 684 [11] D.M. Hetrick and C.Y. Fu, Oak Ridge report ORNL/TM-7341 2925 1451 685 [ENDF-303] (1980) 2925 1451 686 [12] C.Y. Fu and D.M. Hetrick, Proc. Fourth ASTM-Euratom Symp. 2925 1451 687 on Reactor Dosimetry, Gaithersburg, Maryland, March 22-26, 2925 1451 688 1982 (U.S. National Bureau of Standards) p.877 2925 1451 689 [13] CSISRS Library, National Nuclear Data Center, Brookhaven 2925 1451 690 National Laboratory, Upton, N.Y. 11973. 2925 1451 691 [14] V. McLane, C.L. Dunford and P.F. Rose, "Neutron Cross 2925 1451 692 Sections, Vol. 2, Neutron Cross Section Curves" (Academic 2925 1451 693 Press, 1988) 2925 1451 694 [15] S.M. Qaim, Radiochimica Acta, 25, 13 (1978) 2925 1451 695 [16] M.G. Delfini, J. Kopecky, R.E. Chrien et al., Nucl.Phys. 2925 1451 696 A404, 250 (1983) 2925 1451 697 2925 1451 698 **************************************************************** 2925 1451 699 ***************** Program LINEAR (VERSION 2012-1) ***************2925 1451 700 For All Data Greater than 1.0000D-10 barns in Absolute Value 2925 1451 701 Data Linearized to Within an Accuracy of .100000000 per-cent 2925 1451 702 ***************** Program GROUPIE (VERSION 2012-1) **************2925 1451 703 Unshielded Group Averages Using 640 Groups 2925 1451 704 Weighting Spectrum: Flat (Constant) Spectrum 2925 1451 705 1 451 709 12925 1451 706 2 151 4 12925 1451 707 3 1 7243 12925 1451 708 3 2 6998 12925 1451 709 3 16 72 12925 1451 710 3 102 10278 12925 1451 711 3 107 72 12925 1451 712 33 16 115 12925 1451 713 33 102 30 12925 1451 714 33 107 73 12925 1451 715 2925 1 0 716 2925 0 0 717 29063.0000 62.3890000 0 0 1 02925 2151 718 2.906300+4 1.000000+0 0 0 1 02925 2151 719 1.000000-5 9.950000+4 0 0 0 02925 2151 720 1.500000+0 6.700000-1 0 0 0 02925 2151 721 2925 2 0 722 2925 0 0 723 29063.0000 62.3890000 0 0 0 02925 3 1 724 0.0 0.0 0 0 1 6412925 3 1 725 641 1 2925 3 1 726 1.00000E-4 82.7755756 1.05000E-4 80.8883742 1.10000E-4 79.09615642925 3 1 727 1.15000E-4 77.4456720 1.20000E-4 75.5172155 1.27500E-4 73.37899062925 3 1 728 1.35000E-4 71.4268793 1.42500E-4 69.6342418 1.50000E-4 67.69544552925 3 1 729 1.60000E-4 65.6775293 1.70000E-4 63.8432183 1.80000E-4 62.16097352925 3 1 730 1.90000E-4 60.5970348 2.00000E-4 59.1706318 2.10000E-4 57.82959132925 3 1 731 2.20000E-4 56.5851222 2.30000E-4 55.4299594 2.40000E-4 54.07517532925 3 1 732 2.55000E-4 52.5881732 2.70000E-4 51.4419632 2.80000E-4 50.16742962925 3 1 733 3.00000E-4 48.6151979 3.20000E-4 47.2119047 3.40000E-4 45.92855342925 3 1 734 3.60000E-4 44.7481578 3.80000E-4 43.6723264 4.00000E-4 42.55223392925 3 1 735 4.25000E-4 41.4078025 4.50000E-4 40.3643568 4.75000E-4 39.42123482925 3 1 736 5.00000E-4 38.5220907 5.25000E-4 37.7013546 5.50000E-4 36.93758292925 3 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