IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 42092.0000 91.1172000 0 0 41 14225 1451 1 0.0 0.0 0 0 0 64225 1451 2 1.00000000 60000000.0 0 0 10 24225 1451 3 300.000000 0.0 1 0 182 54225 1451 4 42-Mo- 92 FEI EVAL-Jun11 K.I.Zolotarev 4225 1451 5 DIST-Sep11 4225 1451 6 ----BROND-2 MATERIAL 4225 4225 1451 7 -----INCIDENT NEUTRON DATA 4225 1451 8 ------ENDF-6 FORMAT 4225 1451 9 ******************************************************************4225 1451 10 IAEA, July 2011 (A. Trkov) 4225 1451 11 Extended cross sections and covariances from 20 to 60 MeV 4225 1451 12 by TENDL-2010, renormalised for continuity. 4225 1451 13 In addition, MF2/MT251 was added to define the scattering radius 4225 1451 14 Original MF3/MF33 representation for MT103 was changed to 4225 1451 15 MF10/MF40 representation to explicitly denote the formation 4225 1451 16 of the metastable isomer. 4225 1451 17 ******************************************************************4225 1451 18 The work on the Mo(n,p)Nb-92m evaluation was performed under 4225 1451 19 Research Contract No 16242 with the IAEA 4225 1451 20 ******************************************************************4225 1451 21 ***************************************************************** 4225 1451 22 ------Russian Reactor Dosimetry File BEST-13 33119-14 4225 1451 23 ***************************************************************** 4225 1451 24 Author of evaluation: K.I.Zolotarev 4225 1451 25 ***************************************************************** 4225 1451 26 MF=10 4225 1451 27 MT=103 - Mo-92(n,p)Nb-92m cross section 4225 1451 28 ---------------------------------------- 4225 1451 29 In the section MT=103 are given the Mo-92(n,p) reaction cross 4225 1451 30 sections in the energy range from threshold to 20 MeV with excita-4225 1451 31 tion the 10.15-days isomeric state of Nb-92. The 135.5 keV meta- 4225 1451 32 stable level of Nb-92 has spin and parity 2+ [36]. 4225 1451 33 Microscopic experimental data [1-35] had been analyzed in the 4225 1451 34 process of preparation the input database for evaluation of cross 4225 1451 35 sections and their uncertainties for the Mo-92(n,p)Nb-92m reacti- 4225 1451 36 on. During this procedure data of works [1-3], [5-7], [9-18] and 4225 1451 37 [20-35] were corrected for the new standards. 4225 1451 38 Excitation function for the Mo-92(n,p)Nb-92m reaction in the 4225 1451 39 energy range from 1 to 50 MeV was evaluated by means of statisti- 4225 1451 40 cal analysis of experimental cross section data [1], [3], [6-17], 4225 1451 41 [20], [22-29], [31-32], [34-35] and data from theoretical mode- 4225 1451 42 ling calculation carried out by means of modified GNASH code [37].4225 1451 43 Experimental data of Reimer et al. obtained in the energy range 4225 1451 44 16.2-20.5 MeV were taken from the last publication [32]. Data cal-4225 1451 45 culated by GNASH code were renormalized to the cross-section value4225 1451 46 measured by Zhao Wenrong et al. at 19.09 MeV [25]. 4225 1451 47 Cross sections that had been measured in works [2], [4], [5], 4225 1451 48 [19], [21], [33] were rejected due to inconsistency with the main 4225 1451 49 bulk of experimental data. Cross section of 109.9+-5.6 mb measu- 4225 1451 50 red by Liskien et al. at 12.59 MeV [19] agree well with value of 4225 1451 51 109.52+-6.47 mb determined by Doczi et al. at 12.53 MeV [26], but 4225 1451 52 with increasing the incident neutron energy discrepancy between 4225 1451 53 the representative experimental data and data obtained by Liskien 4225 1451 54 et al. is significantly growing. 4225 1451 55 Statistical analysis of input cross section data was carried 4225 1451 56 out by means of PADE-2 code [38]. Rational function was used as 4225 1451 57 the model function [39]. 4225 1451 58 The evaluated Mo-92(n,p)Nb-92m reaction excitation function 4225 1451 59 averaged over the U-235 thermal fission neutron spectrum [40] and 4225 1451 60 Cf-252 spontaneous fission neutron spectrum [41] gives the follo- 4225 1451 61 wing integral cross-section values: 4225 1451 62 ----------------------+-----------------+----------------------- 4225 1451 63 TYPE OF SPECTRUM | ,mb (calc.) | , mb (measured) 4225 1451 64 ----------------------+-----------------+----------------------- 4225 1451 65 U-235 neutron fission | 6.7337 | 6.687 +- 0.169 4225 1451 66 ----------------------+-----------------+----------------------- 4225 1451 67 Cf-252 spont. fission | 7.8349 | 15.170 +- 0.667 [47] 4225 1451 68 ----------------------+-----------------+----------------------- 4225 1451 69 4225 1451 70 Experimental integral cross section of (6.687+-0.169) mb for 4225 1451 71 U-235 thermal fission neutron spectrum was determined as average 4225 1451 72 weighted value from measurements carried out in facilities with 4225 1451 73 90%-enriched U-235 fission plate converter [42-46].Integral cross 4225 1451 74 section for Cf-252 spontaneous fission neutron spectrum was measu-4225 1451 75 red only by Csikai and Dezso [47]. 4225 1451 76 4225 1451 77 MF=40 4225 1451 78 MT=103 - Mo-92(n,p)Nb-92m cross section cov. matrix 4225 1451 79 ---------------------------------------------------- 4225 1451 80 Uncertainties in the evaluated excitation function for the 4225 1451 81 Mo-92(n,p)Nb-92m reaction are given in the form of relative cova- 4225 1451 82 riance matrix for the 49-neutron energy groups (LB=5). Covariance 4225 1451 83 matrix of uncertainties was calculated simultaneously with recom- 4225 1451 84 mended cross section data by means of PADE-2 code [22]. 4225 1451 85 Eigenvalues of the 6-digits relative covariance matrix given 4225 1451 86 in the 33-file are the following: 4225 1451 87 4225 1451 88 6.69193E-06 7.28092E-06 8.09184E-06 9.04294E-06 4225 1451 89 1.01202E-05 1.13789E-05 1.28633E-05 1.49382E-05 4225 1451 90 1.74953E-05 2.10032E-05 2.47084E-05 3.02532E-05 4225 1451 91 3.60682E-05 4.17556E-05 4.66232E-05 5.21772E-05 4225 1451 92 6.03931E-05 6.44122E-05 6.92972E-05 7.73120E-05 4225 1451 93 8.42908E-05 9.25466E-05 1.06442E-04 1.24425E-04 4225 1451 94 1.27774E-04 1.44328E-04 1.61751E-04 1.78296E-04 4225 1451 95 1.94021E-04 2.09027E-04 2.23394E-04 2.37120E-04 4225 1451 96 2.49813E-04 2.59087E-04 2.72743E-04 2.97448E-04 4225 1451 97 3.20078E-04 3.34536E-04 3.55338E-04 7.99532E-04 4225 1451 98 1.12947E-03 3.12196E-03 4.71536E-03 7.91728E-03 4225 1451 99 9.27525E-03 1.51048E-02 3.44107E-02 6.36581E-02 4225 1451 100 2.55476E-01 4225 1451 101 4225 1451 102 References: 4225 1451 103 1. 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A.A.Filatenkov, S.V.Chuvaev, Preprit RI-252, M.: CNIIAtom- 4225 1451 146 inform, Moscow 1999 4225 1451 147 28. T.Shimitsu et al., Report JAERI-C-2001-006, pp.194-199, 2000 4225 1451 148 29. A.A.Filatenkov, S.V.Chuvaev, Preprit RI-258, June 2001 4225 1451 149 30. P.Reimer et al., Report JUEL-3986, Juelich, 2001 4225 1451 150 31. T.Shimizu et al., Annals of Nuclear Energy 31 (2004) 975 4225 1451 151 32. P.Reimer et al., Phys. Rev. C 71 (2005) 044617 4225 1451 152 33. M.Bhike et al., Proc. of Conference on Nuclear Data for Adv. 4225 1451 153 Nuclear Systems, Mangalore, India, 2006, p.TP15 4225 1451 154 34. M.Furuta et al., Annals of Nuclear Energy 35 (2008) 1652 4225 1451 155 35. M.Bhike et al., Nucl. Sci. Eng. 163 (2009) 175 4225 1451 156 36. R.B.Firestone, Table of Isotopes CD-ROM, Eighth Edition, Ver- 4225 1451 157 sion 1.0, March 1996, S.Y.Frank Chu, CD-ROM Ed., V.S.Shirley, 4225 1451 158 Ed., Wiley-Interscience, 1996 4225 1451 159 37. G.Y.Tertychnyj, E.L.Trykov, Modified version of GNASH code. 4225 1451 160 Private communication, IPPE, Obninsk, May 1999 4225 1451 161 38. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 4225 1451 162 39. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 4225 1451 163 st's Meeting on Evaluation and Processing of Covariance Data, 4225 1451 164 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 4225 1451 165 40. L.W.Weston e.a., Evaluated Neutron Data for U-235, ENDF/B-VI 4225 1451 166 Library, MAT=9228, MF=5, MT=18, eval. April 1989 4225 1451 167 41. W.Mannhart, Report INDC(NDS)-220/L, p.158, IAEA, Vienna, 1989 4225 1451 168 42. J.W.Boldeman, J. of Nuclear Energy AB 18 (1964) 417 4225 1451 169 43. A.Fabry, J.P.Deworm, Progress Report EANDC(E)-66, p.125, 4225 1451 170 February 1966 4225 1451 171 44. A.M.Bresesti et al., Nucl. Sci. Eng. 29 (1967) 7-14 4225 1451 172 45. I.Kimura et al., Nucl. Science and Technology 8 (1971) 59 4225 1451 173 46. 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J.Csikai, Z.Dezso, Proc. of the 4th All Union Conference on 4225 1451 177 Neutron Physics, Kiev, 18-22 April 1977, v.3, p.32 4225 1451 178 ***************************************************************** 4225 1451 179 4225 1451 180 ***************** Program LINEAR (VERSION 2012-1) ***************4225 1451 181 For All Data Greater than 1.0000D-10 barns in Absolute Value 4225 1451 182 Data Linearized to Within an Accuracy of .100000000 per-cent 4225 1451 183 ***************** Program GROUPIE (VERSION 2012-1) **************4225 1451 184 Unshielded Group Averages Using 640 Groups 4225 1451 185 Weighting Spectrum: Flat (Constant) Spectrum 4225 1451 186 1 451 173 14225 1451 187 2 151 4 14225 1451 188 8 103 2 14225 1451 189 10 103 88 14225 1451 190 40 103 225 14225 1451 191 4225 1 0 192 4225 0 0 193 42092.0000 91.1172000 0 0 1 04225 2151 194 4.209200+4 1.000000+0 0 0 1 04225 2151 195 1.000000-5 5.000000+4 0 0 0 04225 2151 196 0.000000+0 7.000000-1 0 0 0 04225 2151 197 4225 2 0 198 4225 0 0 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