Zr - 90 fragment from BROND-3 data file 777 0 0 0 4.009000+4 8.913237+1 1 0 0 34025 1451 1 0.000000+0 0.000000+0 0 0 0 64025 1451 2 1.000000+0 2.100000+7 0 0 10 24025 1451 3 0.000000+0 0.000000+0 1 0 98 34025 1451 4 40-Zr- 90 EVAL-Feb2004 Ignatyuk A.V. et al. 4025 1451 5 DIST-Mar2006 4025 1451 6 ----ENDF/B-II MATERIAL 4025 4025 1451 7 -----INCIDENT NEUTRON DATA 4025 1451 8 ------ENDF-6 FORMAT 4025 1451 9 ***************************************************************** 4025 1451 10 Authors of evaluation: Ignatyuk A., Tertychnyj G., Zolotarev K. 4025 1451 11 ***************************************************************** 4025 1451 12 File 3: Neutron cross sections 4025 1451 13 MT=103 Zr-90(n,p)Y-90m+g reaction eval. Zolotarev and Tertychnyj 4025 1451 14 --------------------------------- 4025 1451 15 Excitation function from threshold to 21 MeV was obtained 4025 1451 16 from theoretical model calculation carried out by means of modi- 4025 1451 17 fied GNASH code. GNASH calculation was based on the experimental 4025 1451 18 data [1-7]. Experimental data were corrected to the new standards.4025 1451 19 Data of Bayhurst and Prestwood [1], Mukherjee and Bakhru [2] and 4025 1451 20 Carroll and Stooksberry [3] measured above 12 MeV were corrected 4025 1451 21 to the contribution from Zr-91(n,x)Y-90m+g reaction. After this 4025 1451 22 correction all data from Refs. [1] and [3] were renormalized to 4025 1451 23 the factors Fc= 0.76391 and Fc= 0.77555, respectively. 4025 1451 24 Experimental data of Nemilov and Trofimov [5] were renormali- 4025 1451 25 zed to the preliminary evaluated from GNASH calculation integral 4025 1451 26 of cross sections in the energy range 7.60-9.30 MeV, Fc= 0.49621. 4025 1451 27 4025 1451 28 MT=403 Zr-90(n,p)Y-90m reaction eval. Zolotarev and Tertychnyj 4025 1451 29 --------------------------------- 4025 1451 30 Excitation function from threshold to 21 MeV was obtained 4025 1451 31 from GNASH calculation which was based on the experimental data 4025 1451 32 [8-25]. Experimental data were corrected to the new standards. 4025 1451 33 Data from Refs. [9-10], [12-15], [19-20], [22], [24] were cor-4025 1451 34 rected to the contribution from Zr-91(n,x)Y-90m reaction. 4025 1451 35 Calculated from evaluated Zr-90(n,p)Y-90m reaction excitation 4025 1451 36 function average cross section of 0.0474 mb for Cf-252 spontaneous4025 1451 37 fission spectrum agree well with experimental value (0.043+-0.005)4025 1451 38 mb of Csikai and Dezso [26]. Data for Cf-252 spontaneous fission 4025 1451 39 neutron spectrum were taken from ref.[27]. 4025 1451 40 Full description of the evaluation of neutron data for Zr-90 4025 1451 41 isotope is given in Ref. [28]. 4025 1451 42 4025 1451 43 References: 4025 1451 44 1. B.P.Bayhurst, R.J.Prestwood J. Inorg. Nucl. Chem., v.23, 4025 1451 45 p.173, 1961 4025 1451 46 2. S.K.Mukherjee, H.Bakhru C,63BOMBAY, p.244, February 1963 4025 1451 47 3. E.E.Carroll, R.W.Stooksberry Nucl. Sci. Eng.,v.25,p.285,1966 4025 1451 48 4. V.N.Levkovskiy, G.P.Vinitskaya, G.E.Kovel'skaya, V.M.Stepanov 4025 1451 49 Jadernaja Fizika (Sov.), v.10, no.1, p.44, July 1969 4025 1451 50 5. Ju.A.Nemilov, Ju.N.Trofimov Vopr. At. Nauki i Tekhn., Serija:4025 1451 51 Yadernye Konstanty, v.12, p.61, January 1973 4025 1451 52 6. S.M.Qaim, G.Stoecklin Proc. 8-th Symposium on Fusion Techno- 4025 1451 53 logy, Noordwijkerhout, 17 - 21 June 1974. Report, EUR-5182E, 4025 1451 54 p.939, September 1974 4025 1451 55 7. S.M.Qaim, M.Ibn Majah, R.Woelfle, B.Strohmaier Phys. Rev. C, 4025 1451 56 v.42, p.363, July 1990 4025 1451 57 8. W.L.Alford, D.R.Koehler, C.E.Mandeville Phys. Rev., v.123, 4025 1451 58 p.1365, 1961 4025 1451 59 9. L.Husain et al. Phys. Rev. C, v.1, p.1233, April 1970 4025 1451 60 10. W.D.Lu et al. Phys. Rev., v.C1, p.358, January 1970 4025 1451 61 11. R.A.Sigg, P.K.Kuroda J. Inorg. Nucl. Chem., v.37, p.631, 4025 1451 62 March 1975 4025 1451 63 12. R.Spangler et al. Trans. Amer. Nucl. Soc., v.22, p.818, 4025 1451 64 November 1975 4025 1451 65 13. R.Pepelnik et al. Intern. Conf. on Nucl. Data for Basic and 4025 1451 66 Applied Science, Santa Fe, New Mexico, 13-17 May 1985, v.1, 4025 1451 67 p.211 (JA46) 4025 1451 68 14. N.I.Molla et al. Report INDC(BAN)-003, September 1986 4025 1451 69 15. V.V.Ovechkin, A.E.Khokhlov Atomnaya Energiya, v.60, p.143, 4025 1451 70 February 1986 4025 1451 71 16. I.F.Goncalves, Zs.Schram, Z.Papp, S.Daroczy Appl. Radiat. 4025 1451 72 Isot., v.38, n.11, p.989, November 1987 4025 1451 73 17. Y.Ikeda,C.Konno,K.Oishi et al. Report JAERI-1312, March 1988 4025 1451 74 18. M.Ibn Majah, S.M.Qaim Nucl. Sci. Eng., v.104, p.271, 4025 1451 75 March 1990 4025 1451 76 19. A.Marcinkowski, U.Garuska, H.M.Hoang, D.Kielan, B.Zwieglinski 4025 1451 77 Nucl. Phys., v.A510, p.93, 1990 4025 1451 78 20. N.I.Molla et al. Proc. of Int. Conf. on Nucl. Data for 4025 1451 79 Sci. and Technol., Juelich, FRG, 13-17 May 1991, p. 355 4025 1451 80 21. P.Raics, S.Nagy, S.Szegedi, N.V.Kornilov, A.B.Kagalenko 4025 1451 81 Proc. of Int. Conf. on Nucl. Data for Sci. and Technol., 4025 1451 82 Juelich, FRG, May 1991, p. 660 4025 1451 83 22. A.Grallert, J.Csikai, Cs.M.Buczko, I.Shaddad 4025 1451 84 Nucl. Sci. Eng., v.129, p.164, June 1998 4025 1451 85 23. R.Doczi, V.Semkova, A.Fenyvesi, N.Yamamuro, CS.M.Buczko, 4025 1451 86 J.Csikai Nucl. Sci. Eng., v.129, pp.164-174, June 1998 4025 1451 87 24. A.A.Filatenkov, S.V.Chuvaev, V.N.Aksenov et al. 4025 1451 88 Report RI-252, May 1999; 4025 1451 89 A.A.Filatenkov et al. VANT, Ser.:Yadernye Konstanty, v.2, p.8,4025 1451 90 Moscow, 1996 4025 1451 91 25. V.Semkova, V.Avrigeanu, A.J.M.Plompen, P.Reimer, D.L.Smith, 4025 1451 92 S Sudar, A.Koning, R.Forrest Report, EUR-20820-EN, 2003 4025 1451 93 26. J.Csikai, Z.Dezso Proc. of the 4th All Union Conf. on Neut- 4025 1451 94 ron Physics, Kiev, 18-22 April 1977, v.3, p.32, Moskow 1977 4025 1451 95 27. W.Mannhart Report IAEA-TECDOC-410, p.158, 1987 4025 1451 96 28. Ignatyuk A.V., Zolotarev K.I., Lunev V.P., Manokhin V.N., 4025 1451 97 Tertychnyj G.Ya Analysis and Evaluation of the Spectra and 4025 1451 98 Production Cross-Sections of Gamma-Rays. VANT, Ser. Yadernye 4025 1451 99 Konstanty, Issue 1-2, 2002, pp.3-44 4025 1451 100 ***************************************************************** 4025 1451 101 4025 1451 102 1 451 105 34025 1451 103 3 103 18 34025 1451 104 3 403 17 34025 1451 105 0.000000+0 0.000000+0 0 0 0 04025 1 099999 0.000000+0 0.000000+0 0 0 0 04025 0 0 0 4.009000+4 8.913237+1 0 0 0 04025 3103 1 -1.499700+6-1.499700+6 0 0 1 454025 3103 2 45 2 4025 3103 3 1.516500+6 0.000000+0 3.000000+6 2.509700-7 3.200000+6 1.490700-64025 3103 4 3.400000+6 5.910200-6 3.500000+6 1.056100-5 4.000000+6 1.062100-44025 3103 5 4.500000+6 5.041100-4 5.000000+6 1.181000-3 5.500000+6 2.151300-34025 3103 6 6.000000+6 3.256700-3 6.500000+6 4.501800-3 7.000000+6 5.798700-34025 3103 7 7.500000+6 7.112200-3 7.600000+6 7.645700-3 8.000000+6 8.428500-34025 3103 8 8.500000+6 9.882000-3 8.800000+6 1.072400-2 9.000000+6 1.157100-24025 3103 9 9.300000+6 1.256000-2 9.500000+6 1.361500-2 1.000000+7 1.597500-24025 3103 10 1.050000+7 1.854900-2 1.100000+7 2.130500-2 1.150000+7 2.419900-24025 3103 11 1.200000+7 2.708300-2 1.250000+7 2.976200-2 1.300000+7 3.215000-24025 3103 12 1.350000+7 3.377100-2 1.400000+7 3.455100-2 1.450000+7 3.452900-24025 3103 13 1.470000+7 3.424700-2 1.480000+7 3.391500-2 1.500000+7 3.378100-24025 3103 14 1.550000+7 3.253300-2 1.600000+7 3.105100-2 1.650000+7 2.953700-24025 3103 15 1.700000+7 2.810000-2 1.750000+7 2.683200-2 1.800000+7 2.574200-24025 3103 16 1.850000+7 2.480600-2 1.900000+7 2.400800-2 1.950000+7 2.331600-24025 3103 17 2.000000+7 2.270500-2 2.050000+7 2.216400-2 2.100000+7 2.172400-24025 3103 18 0.000000+0 0.000000+0 0 0 0 04025 3 099999 4.009000+4 8.913237+1 0 0 0 04025 3403 1 -2.181730+6-2.181730+6 0 0 1 404025 3403 2 40 2 4025 3403 3 2.206170+6 0.000000+0 4.000000+6 3.774200-8 4.500000+6 1.086900-64025 3403 4 5.000000+6 1.025100-5 5.500000+6 5.343500-5 6.000000+6 1.608400-44025 3403 5 6.500000+6 3.637300-4 7.000000+6 6.630600-4 7.500000+6 1.042300-34025 3403 6 7.600000+6 1.167300-3 8.000000+6 1.475700-3 8.500000+6 1.937100-34025 3403 7 8.800000+6 2.201100-3 9.000000+6 2.430800-3 9.300000+6 2.732700-34025 3403 8 9.500000+6 3.017900-3 1.000000+7 3.707700-3 1.050000+7 4.503000-34025 3403 9 1.100000+7 5.416400-3 1.150000+7 6.443600-3 1.200000+7 7.556400-34025 3403 10 1.250000+7 8.709800-3 1.300000+7 9.835600-3 1.350000+7 1.083700-24025 3403 11 1.400000+7 1.160900-2 1.450000+7 1.213300-2 1.470000+7 1.228000-24025 3403 12 1.480000+7 1.233000-2 1.500000+7 1.235500-2 1.550000+7 1.230800-24025 3403 13 1.600000+7 1.208600-2 1.650000+7 1.176100-2 1.700000+7 1.137700-24025 3403 14 1.750000+7 1.099700-2 1.800000+7 1.063900-2 1.900000+7 9.991700-34025 3403 15 1.950000+7 9.714600-3 2.000000+7 9.459200-3 2.050000+7 9.225900-34025 3403 16 2.100000+7 9.032500-3 4025 3403 17 0.000000+0 0.000000+0 0 0 0 04025 3 099999 0.000000+0 0.000000+0 0 0 0 04025 0 0 0 0.000000+0 0.000000+0 0 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0