IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 23051.0000 50.5063000 0 0 34 102328 1451 1 0.0 0.0 0 0 0 62328 1451 2 1.00000000 60000000.0 0 0 10 20022328 1451 3 300.000000 0.0 1 0 170 42328 1451 4 23-V - 51 FEI EVAL-Dec01 K.I.Zolotarev 2328 1451 5 DIST-Feb2004 2328 1451 6 ----IRDF-2002 MATERIAL 2328 2328 1451 7 -----INCIDENT NEUTRON DATA 2328 1451 8 ------ENDF-6 FORMAT 2328 1451 9 ******************************************************************2328 1451 10 IAEA, July 2011 (A. Trkov) 2328 1451 11 Extended cross sections and covariances from 20 to 60 MeV 2328 1451 12 by TENDL-2010, renormalised for continuity. 2328 1451 13 ******************************************************************2328 1451 14 ***************************************************************** 2328 1451 15 23-V-51 FEI EVAL-Dec01 K.I.Zolotarev 2328 1451 16 DIST-Jan02 20020118 2328 1451 17 ----BROND-2 MATERIAL 2328 2328 1451 18 -----INCIDENT NEUTRON DATA 2328 1451 19 ------ENDF-6 FORMAT 2328 1451 20 ------Russian Reactor Dosimetry File RRDF-2002 2328 1451 21 ***************************************************************** 2328 1451 22 Author of evaluation: K.I.Zolotarev 2328 1451 23 ***************************************************************** 2328 1451 24 MF=3 2328 1451 25 MT=107 -(n,a) cross section 2328 1451 26 ------------------------------------- 2328 1451 27 Excitation function for the V-51(n,a)Sc-48 reaction in the 2328 1451 28 energy region from threshold to 20 MeV was evaluated by means of 2328 1451 29 statistical analysis of experimental cross section data [1-21] 2328 1451 30 and data from GNASH calculation [45]. 2328 1451 31 All analysed microscopic experimental data [1-38] and integ- 2328 1451 32 ral experimental data [39-44] were renormalized to the new recom- 2328 1451 33 mended standards for monitor reactions cross sections and decay 2328 1451 34 data. 2328 1451 35 Experimental cross section data from ref. [22-38] were rejec- 2328 1451 36 ted due to their big discrepancy with the main bulk of experimen- 2328 1451 37 al data [1-21], data from theoretical model calculation and data 2328 1451 38 from (n,a) cross section systematics. 2328 1451 39 Statistical analysis of input cross section data was carried 2328 1451 40 out by means of PADE-2 code [46]. Rational function was used as 2328 1451 41 the model function [47]. 2328 1451 42 The evaluated V-51(n,a)Sc-48 excitation function averaged 2328 1451 43 on U-235 neutron fission spectrum [48] and Cf-252 spontaneous 2328 1451 44 fission neutron spectrum [49] gives the next values : 2328 1451 45 ---------------------------------------------------------------- 2328 1451 46 TYPE OF SPECTRUM I ,mb (calc.) I , mb (measured) 2328 1451 47 ---------------------------------------------------------------- 2328 1451 48 U-235 neutron fission I 0.024414 I 0.0235 +-0.0015 [40] 2328 1451 49 I I 0.0215 +-0.0013 [41] 2328 1451 50 I I 0.02438+-0.00056 [42] 2328 1451 51 ---------------------------------------------------------------- 2328 1451 52 CF-252 spont. fission I 0.038514 I 0.03904+-0.00086 [43] 2328 1451 53 ---------------------------------------------------------------- 2328 1451 54 2328 1451 55 MF=33 2328 1451 56 MT=107 -(n,a) cross section cov. matrix 2328 1451 57 --------------------------------------- 2328 1451 58 Uncertainties in the evaluated excitation function for the 2328 1451 59 reaction V-51(n,a)Sc-48 are given in the form of relative covari- 2328 1451 60 ance matrix for the 26-neutron energy groups (LB=5). Covariance 2328 1451 61 matrix of uncertainties was calculated simultaneously with recom- 2328 1451 62 mended cross section data by means of PADE-2 code. 2328 1451 63 Eigenvalues of the 6-th digits relative covariance matrix 2328 1451 64 given in the 33-file are the following: 2328 1451 65 2328 1451 66 4.46067E-09 4.97872E-09 5.09809E-09 5.50951E-09 2328 1451 67 6.22582E-09 6.26808E-09 6.80068E-09 7.58613E-09 2328 1451 68 9.63723E-09 1.29149E-08 1.82432E-08 2.72742E-08 2328 1451 69 4.31460E-08 7.37989E-08 1.54144E-07 3.75108E-07 2328 1451 70 2.13791E-06 1.13740E-04 6.78127E-04 9.37900E-04 2328 1451 71 1.40076E-03 2.54577E-03 4.01102E-03 5.22789E-03 2328 1451 72 1.00172E-02 1.34609E-02 2328 1451 73 2328 1451 74 References : 2328 1451 75 1. H.Vonach, H.Muenzer Oesterr. Akad. Wiss., Math + Naturw. 2328 1451 76 Anzeiger, v.95, p.199, November 1958 2328 1451 77 2. H.K.Vonach et al. Proc. 2nd Conf. on Nuclear Cross-Sections 2328 1451 78 and Technology, Washington D.C., 4-7 March 1968, v.2, p.885 2328 1451 79 3. V.N.Levkovskiy et al. Yadernaja Fizika (Sov.), v.10, n.1, 2328 1451 80 p.44, July 1968 2328 1451 81 4. J.C.Robertson,B.Audric,P.Kolkowski J. of Nucl. Energy, v.27, 2328 1451 82 p.531, August 1973 2328 1451 83 5. A.Paulsen et al. Atomkernenergie, v.22, p.291, Sep. 1974 2328 1451 84 6. W.Mannhart, H.Vonach Zeitschrift fuer Physik, Section A, 2328 1451 85 v.272, p.279, March 1975 2328 1451 86 7. S.M.Qaim, N.I.Molla Proc. of 9th Symposium on Fusion Techno- 2328 1451 87 logy, Garmisch, 14-18 June 1976, FRG, Pergamon Press, p.589 2328 1451 88 8. O.Schwerer et al. Oesterr. Akad. Wiss., Math + Naturw. 2328 1451 89 Anzeiger, v.113, p.153, June 1976 2328 1451 90 9. E.Zupranska et al. Progress Report INR-1821/I/PL/A, 1980 2328 1451 91 E.Zupranska et al. Acta. Phys. Pol., v.B11, p.853, Nov. 1980 2328 1451 92 10. I.Kanno, J.W.Meadows, D.L.Smith Annals of Nuclear Energy, 2328 1451 93 v.11, p.623, December 1984 2328 1451 94 11. J.W.Meadows, D.L.Smith et al. Annals of Nuclear Energy, v.14, 2328 1451 95 p.489, September 1987 2328 1451 96 12. Y.Ikeda et al. Report JAERI-1312, March 1988 2328 1451 97 13. K.Kobayashi, I.Kimura Proc. of an Intern. Conf. on Nuclear 2328 1451 98 Data for Science and Technology, 30 May - 3 June 1988, Mito, 2328 1451 99 Japan, Saikon Publishing Co., LTD, pp.261-265, 1989 ; 2328 1451 100 14. Lu Hanlin et al. Report INDC(CPR)-16, August 1989 2328 1451 101 15. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v.106, p.332, 1990 2328 1451 102 16. N.I.Molla et al. Proc. of International Conference on Nuclear 2328 1451 103 Data for Science and Technology, Gatlinburg, Tennessee, USA, 2328 1451 104 9-13 May 1994, v.2, pp.938-940 2328 1451 105 17. A.A.Filatenkov et al. VANT, Ser.: Yadernye Konstanty, v.2, 2328 1451 106 p.8, Moscow, 1996 2328 1451 107 18. D.Subasi et al. Nucl. Sci. Eng., to be published in 1997 2328 1451 108 19. A.D.Majdeddin "Measurement and analysis of excitation func- 2328 1451 109 tions for fast neutron induced reactions from threshold to 2328 1451 110 20 MeV". PHD dissertation, Inst. of Experimental Physics , 2328 1451 111 Kossuth University, Hungary, June 1998 2328 1451 112 20. A.A.Filatenkov et al. Report RI-252, St.Petersburg, May 1999 2328 1451 113 21. P.Reimer et al. Progress Report On Nuclear Data Research in 2328 1451 114 the FRG, INDC(Ger)-047, July 2001 2328 1451 115 22. I.Kumabe J. Phys. Soc. Jap., v.13, p.325, 1958 2328 1451 116 23. E.B.Paul, R.L.Clarke Canadian J. of Phys., v.31, p.267, 1953 2328 1451 117 24. A.Poularikas, R.W.Fink Progress Report A-ARK-60, p.3, 1960 2328 1451 118 25. F.Gabbard et al. Bull. Amer. Phys. Soc., v.5, p.42(C8), 1960 2328 1451 119 26. M.Bormann et al. Phys. Rev., v.22, p.602, October 1961 2328 1451 120 27. M.Hillman Nucl. Phys., v.37, p.78, 1962 2328 1451 121 28. E.T.Bramlitt, R.W.Fink Phys. Rev., v.131, p.2649, Sep. 1963 2328 1451 122 29. J.E.Strain, W.J.Ross Report ORNL-3672, January 1965 2328 1451 123 30. D.Crumpton J. Inorg. Nucl. Chem., v.31, p.3727, Dec. 1969 2328 1451 124 31. R.Spangler et al. Transactions of the American Nuclear 2328 1451 125 Society, v.22, p.818, November 1975 2328 1451 126 32. U.Garuska et al. Progress Report INDC(POL)-9, p.16, Sep. 1978 2328 1451 127 33. W.H.Warren, W.L.Alford Annals of Nucl. Energy, v.9,p.369,1982 2328 1451 128 34. G.Helfer et al. Czechoslovak Journal of Physics, Part B, 2328 1451 129 v.34, p.30, 1984 2328 1451 130 35. R.Pepelnik et al. Int. Conf. on Nuclear Data for Basic and 2328 1451 131 Applied Science, Santa Fe, N.M., 13-17 May 1985, v.1, p.211 2328 1451 132 36. N.I.Molla et al. Progress Report INDC(BAN)-003 , Sep. 1986 2328 1451 133 37. Y.Ikeda et al. Progress Report INDC(JPN)-162/U,p.24,Aug. 1992 2328 1451 134 38. J.Cezar Suita et al. Nucl. Sci. Eng., v.126, p.101, 1997 2328 1451 135 39. F.Nasyrov,B.D.Sciborskij Atomnaya Energija (Sov.), v.25, n.5,2328 1451 136 p.437, November 1968 2328 1451 137 40. I.Kimura, K.Kobayashi, T.Shibata Nucl. Sci. Technology., v.8,2328 1451 138 p.59, February 1971 2328 1451 139 41. K.Kobayashi, I.Kimura et al. Nucl. Sci. Technology., v.13, 2328 1451 140 p.531, October 1976 2328 1451 141 42. W.Mannhart Progress Report INDC(Ger)-045, pp.40-43, 1999 2328 1451 142 43. W.Mannhart Proc. of 5-th ASTM-EURATOM Symposium on Reactor 2328 1451 143 Dosimetry. Geesthacht, Sep.24-28, 1984, Vol.2, p.813, 1985 2328 1451 144 44. J.Csikai, Z.Dezso Proc. of 4th All Union Conf. on Neutron 2328 1451 145 Physics, Kiev, 18-22 April 1977, v.3, p.32 2328 1451 146 45. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 2328 1451 147 Model Code for Calculation of Cross Section and Emission 2328 1451 148 Spectra. Report LA-6947, Los Alamos, 1977 ; 2328 1451 149 E.L.Trykiv, G.Ya.Tertychnyi Private communication, IPPE, 2328 1451 150 Obninsk, May 1999 2328 1451 151 46. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 2328 1451 152 47. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 2328 1451 153 st's Meeting on Evaluation and Processing of Covariance Data, 2328 1451 154 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 2328 1451 155 48. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2328 1451 156 Library, MAT=9228, MF=5, MT=18, eval. April 1989 2328 1451 157 49. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 2328 1451 158 ***************************************************************** 2328 1451 159 The Q values and threshold energies were updated prior to pro- 2328 1451 160 cessing through the codes to comply with the values obtained 2328 1451 161 using the NNDC calculation program which is based on the 1995 2328 1451 162 Update to the Atomic mass Evaluation. 2328 1451 163 2328 1451 164 File 2 added to the pointwise file containing only the effective 2328 1451 165 scattering radius with no resonance parameters given. 2328 1451 166 Taken from ENDF/B-VI 2328 1451 167 ***************************************************************** 2328 1451 168 ***************** Program LINEAR (VERSION 2012-1) ***************2328 1451 169 For All Data Greater than 1.0000D-10 barns in Absolute Value 2328 1451 170 Data Linearized to Within an Accuracy of .100000000 per-cent 2328 1451 171 ***************** Program GROUPIE (VERSION 2012-1) 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