IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 39089.0000 88.1421000 0 0 41 13925 1451 1 0.0 0.0 0 0 0 63925 1451 2 1.00000000 60000000.0 0 0 10 23925 1451 3 300.000000 0.0 1 0 176 43925 1451 4 39-Y - 89 FEI EVAL-Dec09 K.Zolotarev 3925 1451 5 DIST-Feb10 3925 1451 6 ----BROND-2 MATERIAL 3925 3925 1451 7 -----INCIDENT NEUTRON DATA 3925 1451 8 ------ENDF-6 FORMAT 3925 1451 9 ******************************************************************3925 1451 10 IAEA, July 2011 (A. Trkov) 3925 1451 11 Extended cross sections and covariances from 40 to 60 MeV 3925 1451 12 by TENDL-2010, renormalised for continuity. 3925 1451 13 ******************************************************************3925 1451 14 ***************************************************************** 3925 1451 15 ------Russian Reactor Dosimetry File 36159-14 c=0.98 3925 1451 16 ***************************************************************** 3925 1451 17 Author of evaluation: K.I.Zolotarev 3925 1451 18 ***************************************************************** 3925 1451 19 MF=3 3925 1451 20 MT= 16 - (n,2n) cross section 3925 1451 21 ----------------------------- 3925 1451 22 Microscopic experimental data [1-38] were analyzed in the 3925 1451 23 process of preparation of input data base for the evaluation of 3925 1451 24 cross sections and their uncertainty for the Y-89(n,2n)Y-88 reac- 3925 1451 25 tion. During this procedure experimental data of works [1],[3-12],3925 1451 26 [14], [16-19], [21-27], [29-31], [33], [35], [37] and [38] were 3925 1451 27 corrected to the new standards. 3925 1451 28 Speciaal adjustments were also allied to some of the experimen-3925 1451 29 Cross sections measured by Wagner et al. [20], Huang Jianzhou 3925 1451 30 et al. [21], Konno et al. [22], Filatenkov and Chuvaev [25] were 3925 1451 31 used as a reference data in the energy range 13.5 - 15.0 MeV for 3925 1451 32 correction experimental data from works [1], [13] and [24]. 3925 1451 33 Data of Klopries et al. [24] obtained in measurements with 3925 1451 34 D(d,n)He3 source were corrected for a value of energies in the in-3925 1451 35 cident neutrons. The reason for revision of neutron energies was a3925 1451 36 fact that neutron energy at first point is lying below the thresh-3925 1451 37 old of the Y-89(n,2n)Y-88 reaction, whish is equal to 11.6041 MeV.3925 1451 38 Neutron energies of 11.38, 11.86, 12.31 and 13.28 MeV as reported 3925 1451 39 by Klopries et al. were shifted by +0.23 MeV at first two points 3925 1451 40 and by -0.20 MeV at the last point. Neutron energy in the third 3925 1451 41 point is not corrected. 3925 1451 42 Cross sections measured by Abboud et al. for incident neutron 3925 1451 43 energies 14.61, 15.71-17.58 MeV [7] were renormalized to prelimi- 3925 1451 44 nary evaluated value of (968.5+-14.53) mb at 14.61 MeV. 3925 1451 45 The Y-89(n,2n)Y-88 reaction cross sections are not presented 3925 1451 46 directly in Ref. [28]. They were obtained by summing of partial 3925 1451 47 Y-89(n,2n) cross sections measured by Garret et al. in wide ener- 3925 1451 48 gy range 11.9-19.3 MeV. 3925 1451 49 Cross sections that had been determined in Refs. [31-38] were 3925 1451 50 rejected due to their significant overestimation or underestima- 3925 1451 51 tion of the Y-89(n,2n)Y-88 reaction excitation function. 3925 1451 52 Excitation function for the Y-89(n,2n)Y-88 reaction in the 3925 1451 53 energy region from threshold to 40 MeV was evaluated by means of 3925 1451 54 statistical analysis of experimental cross section data [1-30] 3925 1451 55 and data obtained from theoretical model calculation carried out 3925 1451 56 by means of modified GNASH code [39]. 3925 1451 57 Statistical analysis of input cross section data was carried 3925 1451 58 out by means of PADE-2 code [40]. Rational function was used as 3925 1451 59 the model function [41]. 3925 1451 60 Evaluated the Y-89(n,2n)Y-88 excitation function averaged over 3925 1451 61 the U-235 thermal fission spectrum [42] and Cf-252 spontaneous 3925 1451 62 fission neutron spectrum [43] gives the following values: 3925 1451 63 3925 1451 64 ----------------------+-----------------+----------------------- 3925 1451 65 Type of spectrum | ,mb (calc.) | , mb (measured) 3925 1451 66 ----------------------+-----------------+----------------------- 3925 1451 67 U-235 neutron fission | 0.14954 | 0.1502+-0.0050 [ *] 3925 1451 68 ----------------------+-----------------+----------------------- 3925 1451 69 CF-252 spont. fission | 0.34545 | 3925 1451 70 ----------------------+-----------------+----------------------- 3925 1451 71 3925 1451 72 Integral experimental cross section for the U-235 thermal fis- 3925 1451 73 sion spectrum was determined by averaging data from Refs. [44-48].3925 1451 74 Experiments which had been carried out in Cf-252 spontaneous fis- 3925 1451 75 sion neutron spectrum are absent for today. 3925 1451 76 3925 1451 77 MF=33 3925 1451 78 MT= 16 - (n,2n) cross section cov. matrix 3925 1451 79 ----------------------------------------- 3925 1451 80 Uncertainties in the evaluated excitation function for the 3925 1451 81 reaction Y-99(n,2n)Y-88 are given in the form of relative covari- 3925 1451 82 ance matrix for the 42-neutron energy groups (LB=5). Covariance 3925 1451 83 matrix of uncertainties was calculated simultaneously with recom- 3925 1451 84 mended cross section data by means of PADE-2 code [40]. 3925 1451 85 Eigenvalues of the 6-th digits relative covariance matrix 3925 1451 86 given in the 33-file are the following: 3925 1451 87 3925 1451 88 8.06094E-06 8.09518E-06 8.15855E-06 8.24661E-06 3925 1451 89 8.35531E-06 8.49547E-06 8.70638E-06 9.04991E-06 3925 1451 90 9.54483E-06 1.01444E-05 1.13129E-05 1.25114E-05 3925 1451 91 1.32643E-05 1.43223E-05 1.60064E-05 1.86551E-05 3925 1451 92 2.20343E-05 3.19852E-05 4.84211E-05 6.82562E-05 3925 1451 93 8.93968E-05 1.17234E-04 1.31898E-04 1.51179E-04 3925 1451 94 1.54185E-04 1.93535E-04 2.34841E-04 2.76250E-04 3925 1451 95 3.16877E-04 3.56383E-04 3.89006E-04 4.01050E-04 3925 1451 96 5.05488E-04 6.90848E-04 8.95586E-04 1.36883E-03 3925 1451 97 1.57985E-03 4.34718E-03 6.11763E-03 1.18122E-02 3925 1451 98 2.55468E-02 7.84234E-02 3925 1451 99 3925 1451 100 References: 3925 1451 101 1. R.J.Prestwood, B.P.Bayhurst, Phys. Rev. 121 (1961) 1438 3925 1451 102 2. O.M.Hudson JR, I.L.Morgan, Bull. Am. Phys. Soc. 6 (1961) 506 3925 1451 103 3. R.Rieder, H.Muenzer, Acta Physica Austriaca 23 (1966) 42 3925 1451 104 4. D.G.Vallis, Report AWRE-O-76/66, December 1966 3925 1451 105 5. J.Csikai, G.Peto, Acta Phys. Hung. 23 (1967) 87 3925 1451 106 6. D.S.Mather, L.F.Pain, Report AWRE-O-47/69, August 1969 3925 1451 107 7. A.Abboud et al., Acta Phys. Polonica B 2 (1971) 527 3925 1451 108 8. D.S.Mather et al., Report AWRE-O-72/72, November 1972 3925 1451 109 9. D.R.Nethaway, Nucl. Phys. A190 (1972) 635-644 3925 1451 110 10. B.P.Bayhurst et al., Phys. Rev. C12 (1975) 451 3925 1451 111 11. W.Mannhart, H.Vonach, Zeitschrift f. Physik A272 (1975) 279 3925 1451 112 12. S.K.Ghorai, C.G.Hudson,W.L.Alford, Nucl. Phys. A266 (1976) 53 3925 1451 113 13. M.Bormann et al., Zeitschrift f. Physik A277 (1976) 203 3925 1451 114 14. L.R.Veeser, E.D.Arthur, P.G.Young, Phys. Rev. C16 (1977) 1792 3925 1451 115 15. K.Kayashima et al., Progress Report NEANDC(J)-61U, p.94, Sep- 3925 1451 116 tember 1979 3925 1451 117 16. J.Frehaut et al., Status of (n,2n) Cross Section Measurements 3925 1451 118 at Bruyeres-le-Chatel, Proc. of Symposium on Neutron Cross 3925 1451 119 Sections from 10-50 MeV, Upton, L.I.(U.S.A.), May 12-14, 1980 3925 1451 120 17. J.Laurec, A.Adam, T.De Bruyne, Report CEA-R-5109, June 1981 3925 1451 121 18. P.Raics et al., Atomki Kozl. 23 (1981) 45 3925 1451 122 19. L.R.Greenwood, Report ASTM-STP-956, p.743, 1987 3925 1451 123 20. M.Wagner et al., Annals of Nuclear Energy 16 (1989) 623 3925 1451 124 21. Zhao Wenrong, Lu Hanlin et al., Report INDC(CPR)-16, IAEA, 3925 1451 125 Vienna, August 1989 3925 1451 126 22. C.Konno, Y.Ikeda, K.Oishi, K.Kawade, H.Yamamoto, H.Maekawa, 3925 1451 127 Report JAERI-1329, October 1993 3925 1451 128 23. S.Iwasaki et al., Proc of an Int. Conf. on Nucl. Data for Sci.3925 1451 129 and Technology, 9-13 May 1994, Gatlinburg, Tennessee, USA, 3925 1451 130 vol. 1, p.305, 1994 3925 1451 131 24. R.M.Klopries et al., Radiochimica Acta 76 (1997) 3 3925 1451 132 25. A.A.Filatenkov, S.V.Chuvaev, Preprint RI-252, M.: Atominform, 3925 1451 133 May 1999 3925 1451 134 26. S.V.Begun et al., Izvestija Akademii Nauk Russ., Ser. Fiz. 64 3925 1451 135 (2000) 1017 3925 1451 136 27. S.V.Begun et al., Nucl. Sci. Technology 2 (2002) 425 3925 1451 137 28. P.E.Garrett et al., Report UCRL-ID-153190, 2003 3925 1451 138 29. Fengqun Zhou et al., EXFOR 31649002 3925 1451 139 30. H.M.Agrawal et al., Annals of Nuclear Energy 35 (2008) 1713 3925 1451 140 31. H.Vonach, H.Muenzer, Oesterr. Akad. Wiss., Math. und Naturw. 3925 1451 141 Anzeiger 96 (1959) 120 3925 1451 142 32. H.A.Tewes et al., Report UCRL-6028-T, June 1960 3925 1451 143 33. F.Strohal, N.Cindro, B.Eman, Nucl. Phys. 30 (1962) 49 3925 1451 144 34. B.Granger, M.Longueve, Report EANDC(E)-49L, p.83, Oct. 1963 3925 1451 145 35. J.Araminowicz, J.Dresler, Progress Report INR-1464, pp.14-18, 3925 1451 146 May 1973 3925 1451 147 36. S.M.Qaim, G.Stoecklin, Proc. 8th Symposium on Fusion Technolo-3925 1451 148 gy, Noordwijkerhout, 17-21 June 1974, Report EUR-5182E, p.939,3925 1451 149 September 1974 3925 1451 150 37. M.Berrada, Measurement and Analysis of 14 MeV Neutron Nuclear 3925 1451 151 Reaction Cross-Sections by X and Gamma Spectroscopy. Progress 3925 1451 152 on Research Contract-3311.R1/RB, IAEA NDS, Vienna, April 1984 3925 1451 153 38. N.I.Molla et al., Radiochimica Acta 80 (1998) 189-191 3925 1451 154 39. G.Y.Tertychnyj, E.L.Trykov, Modified version of GNASH code. 3925 1451 155 Private communication, IPPE, Obninsk, May 1999 3925 1451 156 40. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 3925 1451 157 41. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 3925 1451 158 st's Meeting on Evaluation and Processing of Covariance Data, 3925 1451 159 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 3925 1451 160 42. L.W.Weston e.a., Evaluated Neutron Data for U-235, ENDF/B-VI 3925 1451 161 Library, MAT=9228, MF=5, MT=18, eval. April 1989 3925 1451 162 43. W.Mannhart, Report INDC(NDS)-220/L, p.158, IAEA, Vienna, 1989 3925 1451 163 44. G.Rau, Progress Report EANDC(E)-89, p. 41, February 1968 3925 1451 164 45. E.Steinnes, Radiochimica Acta 13 (1970) 169 3925 1451 165 46. S.M.Qaim, R.Woelfle, G.Stoecklin, Proc. of Conf. on Chemical 3925 1451 166 Nucl. Data, Measurements and Application, University of Kent, 3925 1451 167 Canterbury, 20-22 September 1971, p. 121 3925 1451 168 47. A.K.Brodskaja, N.I.Ivanova, F.K.Nasyrov, VANT, Ser.:Jadernyje 3925 1451 169 Konstanty, Vol. 4(23), pp. 4-5, 1976 3925 1451 170 48. A.A.Bojtcov, E.I.Grigor'ev, V.S.Troshin, V.P.Jaryna, VANT, 3925 1451 171 Ser.:Jadernyje Konstanty, Vol. 1, pp. 55-56, 1992 3925 1451 172 ***************************************************************** 3925 1451 173 3925 1451 174 ***************** Program LINEAR (VERSION 2012-1) ***************3925 1451 175 For All Data Greater than 1.0000D-10 barns in Absolute Value 3925 1451 176 Data Linearized to Within an Accuracy of .100000000 per-cent 3925 1451 177 ***************** Program GROUPIE (VERSION 2012-1) **************3925 1451 178 Unshielded Group Averages Using 640 Groups 3925 1451 179 Weighting Spectrum: Flat (Constant) Spectrum 3925 1451 180 1 451 173 13925 1451 181 2 151 4 13925 1451 182 3 16 48 13925 1451 183 33 16 165 13925 1451 184 3925 1 0 185 3925 0 0 186 39089.0000 88.1421000 0 0 1 03925 2151 187 3.908900+4 1.000000+0 0 0 1 03925 2151 188 0.000000+0 0.000000+0 0 0 0 03925 2151 189 5.000000-1 6.700000-1 0 0 0 03925 2151 190 3925 2 0 191 3925 0 0 192 39089.0000 88.1421000 0 0 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