Russian Reactor Dosimetry File RRDF-98 .290630E+05 6.23894+ 1 0 0 41 02911 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 62911 1451 2 1.00000+ 0 0.00000+ 0 0 0 10 22911 1451 3 0.00000+ 0 0.00000+ 0 0 0 111 32911 1451 4 29-Cu- 63 FEI EVAL-Mar97 K.Zolotarev 2911 1451 5 DIST-Apr97 2911 1451 6 ---RRDF-98 MATERIAL 2911 2911 1451 7 ----INCIDENT NEUTRON DATA 2911 1451 8 -----ENDF-6 FORMAT 2911 1451 9 ***************************************************************** 2911 1451 10 -----Russian Reactor Dosimetry File 2911 1451 11 ***************************************************************** 2911 1451 12 AUTHOR OF EVALUATION: K.I.Zolotarev 2911 1451 13 ***************************************************************** 2911 1451 14 2911 1451 15 ----- MF=3 MT=107 ----- 2911 1451 16 Evaluation of Cu63(n,a)Co60m+g - excitation function was car-2911 1451 17 ried out by means of statistical analisis of cross sections from 2911 1451 18 data base prepared in the energy range 2 - 20 Mev. In the energy 2911 1451 19 range 3.56 - 19.55 MeV input data base was formed with using of 2911 1451 20 experimental data from ref. [1-18]. Cross section data in the 2911 1451 21 interval 2.0 - 3.5 MeV were taken from theoretical model calcula- 2911 1451 22 tion. Experimental data included in the input data base were 2911 1451 23 renormalized using new cross sections standards for monitor reac- 2911 1451 24 tions. 2911 1451 25 The special correction was applied to the experimental data 2911 1451 26 [2],[3],[12],[13]. Cross section data of A.Paulsen and H.Liskien 2911 1451 27 [2-3] measured in the energy region 12.09 - 19.55 MeV with using 2911 1451 28 T(d,n)He4 neutron source were multiplied to the factor 1.20805 . 2911 1451 29 Experimental data of Lu Hanlin et al. [12] and Wang Yongchag et 2911 1451 30 al. [13] were multiplied to the factors 0.88110 and 0.84377 , 2911 1451 31 respectively. The correction factors were derived from prelimi- 2911 1451 32 nary evaluated cross sections integral in the energy interval 2911 1451 33 13 - 15 MeV. 2911 1451 34 Data of A.Paulsen and H.Liskien [2] in the energy range 2911 1451 35 5.76 - 11.48 MeV measured with using D(d,n)He3 , Be9(a,n)C12 , 2911 1451 36 C14(d,n)N15 , N15(d,n)O16 neutron sources were rejected due to 2911 1451 37 their inconsistency with precision measurements of G.Winkler et 2911 1451 38 al. [8] and integral experimental data for U-235 fission neutron 2911 1451 39 spectrum [19-24] and Cf-252 spontaneous fission neutron spectrum 2911 1451 40 [25-26]. Cross sections measured by M.Bormann et al. [27] were 2911 1451 41 also rejected due to the big discrepancy with the main bulk expi- 2911 1451 42 mental data. 2911 1451 43 The final procedure evaluation of (n,a) excitation function 2911 1451 44 was carried out by means of Pade-2 code [28]. 2911 1451 45 Evaluated excitation function for the reaction Cu63(n,a)Co60 2911 1451 46 was tested with using integral experimental data [19-24] for 2911 1451 47 U-235 thermal fission neutron spectrum and evaluated integral ex- 2911 1451 48 perimental data [29] for Cf-252 spontaeous fission neutron spec- 2911 1451 49 trum. Calculated and measured average cross section values for 2911 1451 50 U-235 thermal fission neutron spectrum [30] and Cf-252 sponta- 2911 1451 51 neous fission neutron spectrum [31] are given in the table 1. 2911 1451 52 Table 1 2911 1451 53 ================================================================ 2911 1451 54 TYPE OF SPECTRUM | ,mb (calc.) | , mb (measured) 2911 1451 55 ================================================================ 2911 1451 56 U-235 neutron fission | 0.52280 | 0.5271 +- 0.0139 [ *] 2911 1451 57 ================================================================ 2911 1451 58 CF-252 spont. fission | 0.68029 | 0.6897 +- 0.0130 [29] 2911 1451 59 ================================================================ 2911 1451 60 * -average weighted cross section from experimental data [19-24] 2911 1451 61 2911 1451 62 ----- MF=33 MT=107 ----- 2911 1451 63 The covarience matrix of cross sections uncertainties were 2911 1451 64 obtained simultaneously with (n,a) excitation function by means 2911 1451 65 of Pade-2 code [28]. 2911 1451 66 2911 1451 67 References : 2911 1451 68 1. B.Czapp, H.Vonach Oesterr. Akad. Wiss, Math, Naturw. 2911 1451 69 Anzeiger, v.97, p.13, January 1960 2911 1451 70 2. A.Paulsen, H.Liskien Nukleonik, v.10, p.91, July 1967 2911 1451 71 3. A.Paulsen J, Z. Phys., v.205, p.226, August 1967 2911 1451 72 4. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 2911 1451 73 5. G.N.Maslov, F.Nasyrov, N.F.Pashkin Yadernye Konstanty, v.9, 2911 1451 74 p.50, Obninsk, 1972 2911 1451 75 6. G.Winkler Nucl. Sci. Eng., v.67, n.2, p.260, August 1978 2911 1451 76 7. K.Kayashima et al. Prog. Rep. NEANDC(J)-61U, p.94, Sep. 1979 2911 1451 77 8. G.Winkler, D.L.Smith, J.W.Meadows Nucl. Sci. Eng., v.76, 2911 1451 78 p.30, October 1980 2911 1451 79 9. U.Garuska et al. Prog. Report INDC(POL)-11, p.15, July 1980 2911 1451 80 10. O.I.Artem'ev et al. Atomnaja Energija (Sov.), v.49, n.3, 2911 1451 81 p.195, September 1980 2911 1451 82 11. L.R.Greenwood Progress Report ASTM-STP-956, p.743, 1987 2911 1451 83 12. Lu Hanlin et al. Chin. Journ. of Nucl. Phys., v.12. n.4, 2911 1451 84 p. 373, 1990 2911 1451 85 13. Wang Yongchang et al. Chinese J. High Energy Phys. and Nucl. 2911 1451 86 Phys., v.14, p.919, October 1990 2911 1451 87 14. J.Csikai, C.M.Buczko, R.Pepelnik, H.M.Agrawal Annals of Nucl. 2911 1451 88 Energy, v.18, n.1, p.1, 1991 2911 1451 89 15. A.Ercan et al. Proc. of an Intern. Conf. on Nuclear Data for 2911 1451 90 Science and Technology, 13-17 May 1991, Julich, FRG, Springer-2911 1451 91 Verlag, 1992 2911 1451 92 16. C.Konno et al. Report JAERI-1329, October 1993 2911 1451 93 17. J.W.Meadows et al. Annals of Nucl. Energy, v.23, p.877, 1996 2911 1451 94 18. A.A.Filatenkov et al. VANT, Ser.: Yadernye Konstanty, v.2, 2911 1451 95 p.8, Moscow, 1996 2911 1451 96 19. D.M.Clare, D.H.Martin J. Nucl. Energy, v.AB18, p.703, 1964 2911 1451 97 20. R.Lloret Progress Report EANDC(E)-57, p.172, February 1965 2911 1451 98 21. A.Fabry, J.P.Deworm Prog. Report EANDC(E)-66, p.125, 1966 2911 1451 99 22. F.Nasyrov, B.D.Sciborskij Atomnaja Energija (Sov.), v.25, 2911 1451 100 no.5, p.437, November 1968 2911 1451 101 23. K.Kobayashi et al. Nucl. Sci. Techn., v.13, p.531, Oct. 1976 2911 1451 102 24. L.P.Geraldo et al. Radiochimica Acta, v.57, pp.63-67, 1992 2911 1451 103 25. G.Winkler et al. Nucl. Sci. Eng., v.78, p.415, August 1981 2911 1451 104 26. W.Mannhart C,82ANTWER,, p.429, September 1982 2911 1451 105 27. M.Bormann et al. Nucl. Phys., v.A186, p.65, May 1972 2911 1451 106 28. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 2911 1451 107 29. W.Mannhart Handbook on Nuclear Actovation Data . IAEA 2911 1451 108 Technical Report series No.273, p.413, 1987 2911 1451 109 30. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 2911 1451 110 Library, MAT=9228, MF=5, MT=18, eval.apr. 1989 2911 1451 111 31. W.Mannhart IAEA-TECDOC-410, p.158, IAEA, Vienna, 1987 2911 1451 112 2911 1451 113 ***************************************************************** 2911 1451 114 2911 1451 115 1 451 118 02911 1451 116 3 107 57 02911 1451 117 33 107 127 02911 1451 118 2911 1 0 119 2911 0 0 120 2.90630+ 4 6.23894+ 1 0 0 0 02911 3107 121 1.71440+ 6 1.71440+ 6 0 0 1 1622911 3107 122 162 2 2911 3107 123 1.00000- 5 0.00000+ 0 2.00000+ 6 7.11840- 8 2.50000+ 6 1.12105- 62911 3107 124 3.00000+ 6 1.07622- 5 3.50000+ 6 6.02437- 5 4.00000+ 6 2.20925- 42911 3107 125 4.50000+ 6 6.35726- 4 4.60000+ 6 7.68539- 4 4.70000+ 6 9.23148- 42911 3107 126 4.80000+ 6 1.10197- 3 4.90000+ 6 1.30743- 3 5.00000+ 6 1.54190- 32911 3107 127 5.10000+ 6 1.80760- 3 5.20000+ 6 2.10650- 3 5.30000+ 6 2.44025- 32911 3107 128 5.40000+ 6 2.81002- 3 5.50000+ 6 3.21644- 3 5.60000+ 6 3.65950- 32911 3107 129 5.70000+ 6 4.13849- 3 5.80000+ 6 4.65201- 3 5.90000+ 6 5.19794- 32911 3107 130 6.00000+ 6 5.77351- 3 6.10000+ 6 6.37544- 3 6.20000+ 6 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