Russian Reactor Dosimetry File RRDF-98 .270590E+05 5.84269+ 1 0 0 41 12712 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 62712 1451 2 1.00000+ 0 0.00000+ 0 0 0 10 22712 1451 3 0.00000+ 0 0.00000+ 0 0 0 127 32712 1451 4 27-Co- 59 FEI EVAL-Dec97 K.Zolotarev 2712 1451 5 DIST-Dec97 2712 1451 6 ----RRDF-98 MATERIAL 2712 2712 1451 7 -----INCIDENT NEUTRON DATA 2712 1451 8 ------ENDF-6 FORMAT 2712 1451 9 ***************************************************************** 2712 1451 10 -----Russian Reactor Dosimetry File 2712 1451 11 ***************************************************************** 2712 1451 12 AUTHOR OF EVALUATION: K.Zolotarev 2712 1451 13 ***************************************************************** 2712 1451 14 MF=3 2712 1451 15 MT=107 -(n,a) cross section 2712 1451 16 ------------------------------------- 2712 1451 17 Excitation function for the Co-59(n,a)Mn-56 reaction in the 2712 1451 18 energy region from 2.5 MeV to 21 MeV was evaluated by means of 2712 1451 19 statistical analysis of experimental cross section data [1-25], 2712 1451 20 and data from STAPRE calculation. 2712 1451 21 All experimental data were renormalized to the new standards 2712 1451 22 for monitor reactions cross sections and decay data. Uncertainty 2712 1451 23 in the monitor reaction cross section was added to the total un- 2712 1451 24 unsertainty for Santry and Butler data [5]. Cross section data 2712 1451 25 measured by Huang Jianzhou et al. [18] were renormalized to the 2712 1451 26 preliminary evaluated integral of excitation function in the 2712 1451 27 energy range 13.0 - 15.0 MeV. Correction factor for this data 2712 1451 28 was equal Kn= 1.0507 . 2712 1451 29 Experimental data from ref.[26-36] were rejected due to their 2712 1451 30 discrepancy with the main bulk of experimental data [1-25] and 2712 1451 31 data from theoretical model calculation. 2712 1451 32 2712 1451 33 The evaluated Co59(n,a)Mn56 excitation function averaged 2712 1451 34 on U-235 neutron fission spectrum [42] and Cf-252 spontaneous 2712 1451 35 fission neutron spectrum [43] gives the next values : 2712 1451 36 ================================================================ 2712 1451 37 TYPE OF SPECTRUM | ,mb (calc.) | , mb (measured) 2712 1451 38 ================================================================ 2712 1451 39 | | 0.150 +- 0.008 [37] 2712 1451 40 U-235 neutron fission | 0.15822 | 0.161 +- 0.007 [38] 2712 1451 41 | | 0.170 +- 0.012 [39] 2712 1451 42 ================================================================ 2712 1451 43 CF-252 spont. fission | 0.22094 | 0.2208 +- 0.0014 [40] 2712 1451 44 | | 0.2221 +- 0.0023 [41] 2712 1451 45 ================================================================ 2712 1451 46 2712 1451 47 Statistical analysis of input cross section data was carried 2712 1451 48 out by means of PADE-2 code [44]. Rational function was used as 2712 1451 49 the model function. 2712 1451 50 2712 1451 51 MF=33 2712 1451 52 MT=107 -(n,a) cross section cov. matrix 2712 1451 53 ------------------------------------------- 2712 1451 54 The covariance matrix of cross section uncertainties were 2712 1451 55 obtained simultaneously with (n,a) excitation function by means 2712 1451 56 of PADE-2 code in the LB=5 representation. 2712 1451 57 2712 1451 58 References : 2712 1451 59 1. H.G.Blosser et.al. Phys. Rev., v.110, p.531, 1958 2712 1451 60 2. I.L.Preiss,R.W.Fink Nucl. Phys., v.15, p.326, February 1960 2712 1451 61 3. C.S.Khurana, H.S.Hans Proc.of 4th Nuclear Physics and Solid 2712 1451 62 State Physics Symp., 24-26 Feb. 1960, Waltair, India, p.297 2712 1451 63 4. E.Weigold J,AUJ, v.13, p.186, 1960 2712 1451 64 5. D.C.Santry,J.P.Butler Can. J. Phys., v.42, p.1030, June 1964 2712 1451 65 6. H.Liskien,A.Paulsen J. Nucl. of Energy, v.19, p.73, Feb. 1965 2712 1451 66 7. K.S.Khurana,I.M.Govil Nucl. Phys., v.69, p.153, July 1965 2712 1451 67 8. H.Liskien, A.Paulsen Nucleonics, v.8, p.315, June 1966 2712 1451 68 9. V.N.Levkovskiy et.al. Yadernaja Fizika (Sov.), v.8, n.1, p.7, 2712 1451 69 July 1968 2712 1451 70 10. J.C.Robertson,B.Audric,P.Kolkowski Journ. Nucl. Energ., v.27,2712 1451 71 p.531, August 1973 2712 1451 72 11. S.K.Ghorai, J.E.Gaiser, W.L.Alford Annals of Nucl.energy, 2712 1451 73 v.7, p.41, 1980 2712 1451 74 12. E.Zupranska et.al. Progress Report INR-1821/I/PL/A, 1980 2712 1451 75 E.Zupranska et.al. Acta.Phys.Pol., v.B11, p.853, Nov.1980 2712 1451 76 13. B.M.Bahal,R.Pepelnik Report GKSS-84-E-, 1984 2712 1451 77 14. J.W.Meadows, D.L.Smith et.al. Annals of Nucl.energy, v.14, 2712 1451 78 p.489, 1987 2712 1451 79 15. J.W.Meadows, D.L.Smith, R.D.Lawson Annals of Nucl.energy, 2712 1451 80 v.14, p.603, 1987 2712 1451 81 16. Y.Ikeda,C.Konno,K.Oishi et.al. Report JAERI-1312, 1988 2712 1451 82 17. T.B.Ryves, P.Kolkowski, S.M.Judge Annals of Nuclear Energy, 2712 1451 83 v.15, p.561, Dec.1988 2712 1451 84 18. Huang Jianzhou et al. Report INDC(CPR)-16, Vienna,August 1989 2712 1451 85 19. I.Kimura,K.Kobayashi Nucl.Sci.Eng., v.106, p.332, 1990 2712 1451 86 20. Li Tingyan et al. High Energy Physics and Nuclear Physics, 2712 1451 87 v.14(6), p.542, June 1990 2712 1451 88 21. A.Ercan et al. Proc. of an Intern. Conf. on Nuclear Data for 2712 1451 89 Science and Technology, 13-17 May 1991, Julich, FRG, Springer-2712 1451 90 Verlag, 1992, p.376-377 2712 1451 91 22. Y.Ikeda et al. Progress Report INDC(JPN)-162/U,p.24, Aug.1992 2712 1451 92 23. W.Mannhart et al. Proc.of International Conference on Nuclear 2712 1451 93 Data for Science and Technology, Gatlinburg, Tennessee, May 2712 1451 94 9-13, 1994, v.1, pp.285-287 2712 1451 95 24. A.A.Filatenkov et al. VANT, Ser.:Yadernye Konstanty, v.2, p.8,2712 1451 96 Moscow, 1996 2712 1451 97 25. T.O.Khalda, F.I.Habbani Report INDC(SUD)-001,Distr.L, IAEA, 2712 1451 98 Vienna, October 1996 2712 1451 99 26. E.B.Paul,R.L.Clarke Canad. J. of Phys., v.31, p.267, 1953 2712 1451 100 27. M.Bormann et.al. Journal de Physique, v.22, p.602, Oct. 1961 2712 1451 101 28. F.Gabbard, B.D.Kern Phys. Rev., v.128, n.3, p.1276, 1962 2712 1451 102 29. J.M.F.Jeronymo et.al. Nucl.Phys., v.47(1), p.157, July 1963 2712 1451 103 30. J.E.Strain, W.J.Ross Report ORNL-3672, Janury 1965 2712 1451 104 31. M.Bormann et al. Nucl. Phys., v.63, p.438, March 1965 2712 1451 105 32. U.Garuska,J.Dresler,H.Malecki Progress Report INR-1773/I/PL/A,2712 1451 106 p.16, September 1978 2712 1451 107 33. H.M.Agrawal, K.R.Zasadny, G.F.Knoll Trans. Amer. Nucl. Soc., 2712 1451 108 v.47, p.431, Nov. 1984 2712 1451 109 34. M.Berrada Progress Report to the IAEA NDS on Research 2712 1451 110 Contract -3311.R1/RB, 15 April 1984 2712 1451 111 35. I.Garlea et al. Revue Roumaine de Physique, v.30, p.673, 1985 2712 1451 112 36. N.I.Molla et al. Proc.of International Conference on Nuclear 2712 1451 113 Data for Science and Technology, Gatlinburg, Tennessee, May 2712 1451 114 9-13, 1994, v.2, pp.938-940 2712 1451 115 37. K.Kobayashi,I.Kimura Report NEANDC(J)-61U, p.81, Sep.1979 2712 1451 116 38. W.Mannhart Proc. 5-th ASTM-EURATOM Symposium on Reactor 2712 1451 117 Dosimetry. Geesthacht, Sep.24-28, 1984, Vol.2, p.813, 1985 2712 1451 118 39. O.Horibe et al. Proc. of Conf.:50 Years with Nuclear Fission, 2712 1451 119 Washington D.C., 25-28 April 1989, v.2, p.923 2712 1451 120 40. K.Kobayashi,I.Kimura,W.Mannhart Nucl. Sci. Technology.,v.19, 2712 1451 121 n.5, p.341, May 1982 2712 1451 122 41. W.Mannhart Handbook on Nuclear Actovation Data . IAEA 2712 1451 123 Technical Report series No.273, p.413, 1987 2712 1451 124 42. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2712 1451 125 Library, MAT=9228, MF=5, MT=18, eval.apr. 1989 2712 1451 126 43. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 2712 1451 127 44. S.A.Badikov et.al. Preprint FEI-1686, Obninsk, 1985 2712 1451 128 2712 1451 129 ***************************************************************** 2712 1451 130 2712 1451 131 1 451 134 12712 1451 132 3 107 62 12712 1451 133 33 107 121 12712 1451 134 2712 1 0 135 2712 0 0 136 2.70590+ 4 5.84269+ 1 0 0 0 02712 3107 137 3.29000+ 5 3.29000+ 5 0 0 1 1762712 3107 138 176 2 2712 3107 139 1.00000- 5 0.00000+ 0 2.50000+ 6 1.20000-12 3.00000+ 6 2.20000-102712 3107 140 3.50000+ 6 3.40831- 8 3.75000+ 6 2.26148- 7 4.00000+ 6 1.10139- 62712 3107 141 4.10000+ 6 1.98739- 6 4.20000+ 6 3.42734- 6 4.30000+ 6 5.66785- 62712 3107 142 4.40000+ 6 9.04062- 6 4.50000+ 6 1.39886- 5 4.60000+ 6 2.10944- 52712 3107 143 4.70000+ 6 3.11109- 5 4.80000+ 6 4.49899- 5 4.90000+ 6 6.39003- 52712 3107 144 5.00000+ 6 8.92229- 5 5.10000+ 6 1.22513- 4 5.20000+ 6 1.65423- 42712 3107 145 5.30000+ 6 2.19582- 4 5.40000+ 6 2.86458- 4 5.50000+ 6 3.67224- 42712 3107 146 5.60000+ 6 4.62678- 4 5.70000+ 6 5.73250- 4 5.80000+ 6 6.99079- 42712 3107 147 5.90000+ 6 8.40159- 4 6.00000+ 6 9.96490- 4 6.10000+ 6 1.16821- 32712 3107 148 6.20000+ 6 1.35566- 3 6.30000+ 6 1.55941- 3 6.40000+ 6 1.78022- 32712 3107 149 6.50000+ 6 2.01896- 3 6.60000+ 6 2.27656- 3 6.70000+ 6 2.55388- 32712 3107 150 6.80000+ 6 2.85165- 3 6.90000+ 6 3.17035- 3 7.00000+ 6 3.51019- 32712 3107 151 7.10000+ 6 3.87101- 3 7.20000+ 6 4.25227- 3 7.30000+ 6 4.65300- 32712 3107 152 7.40000+ 6 5.07180- 3 7.50000+ 6 5.50687- 3 7.60000+ 6 5.95609- 32712 3107 153 7.70000+ 6 6.41701- 3 7.80000+ 6 6.88700- 3 7.90000+ 6 7.36333- 32712 3107 154 8.00000+ 6 7.84325- 3 8.10000+ 6 8.32411- 3 8.20000+ 6 8.80345- 32712 3107 155 8.30000+ 6 9.27906- 3 8.40000+ 6 9.74906- 3 8.50000+ 6 1.02119- 22712 3107 156 8.60000+ 6 1.06665- 2 8.70000+ 6 1.11120- 2 8.80000+ 6 1.15481- 22712 3107 157 8.90000+ 6 1.19746- 2 9.00000+ 6 1.23917- 2 9.10000+ 6 1.27999- 22712 3107 158 9.20000+ 6 1.31998- 2 9.30000+ 6 1.35922- 2 9.40000+ 6 1.39781- 22712 3107 159 9.50000+ 6 1.43585- 2 9.60000+ 6 1.47343- 2 9.70000+ 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