IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 14029.0000 28.7276000 0 1 0 31428 1451 1 0.0 0.0 0 0 0 61428 1451 2 1.00000000 60000000.0 3 0 10 61428 1451 3 300.000000 0.0 1 0 74 51428 1451 4 14-Si- 29 FEI EVAL-Apr2014 Zolotarev K.I. 1428 1451 5 DIST-May2014 1428 1451 6 ----ENDF/B-VI MATERIAL 1428 1428 1451 7 -----INCIDENT NEUTRON DATA 1428 1451 8 ------ENDF-6 FORMAT 1428 1451 9 ******************************************************************1428 1451 10 The evaluation was performed by K. Zolotarev under contract with 1428 1451 11 the IAEA, August 2014. 1428 1451 12 IAEA, August 2014 (A. Trkov) 1428 1451 13 Cross sections were extended from 20 to 60 MeV by the data from 1428 1451 14 the TENDL-2013 library, summing MT28 and MT104 and renormalizing 1428 1451 15 for continuity. A constant uncertainty of 20 was assigned 1428 1451 16 arbitrarily to the data above 21 MeV. 1428 1451 17 ******************************************************************1428 1451 18 ***************************************************************** 1428 1451 19 Authors of evaluation: Zolotarev K. 1428 1451 20 ***************************************************************** 1428 1451 21 *** Reaction changed to MF10/MT5 Si-29(n,x)Al-28 and NDS IAEA *** 1428 1451 22 ***************************************************************** 1428 1451 23 MF=3 1428 1451 24 MT= 28 - (n,d) + (n,n+p) + (n,p+n) cross sections 1428 1451 25 ------------------------------------------------- 1428 1451 26 Microscopic experimental data [1-3] were analyzed in the pro- 1428 1451 27 cess of preparation of input data base for the evaluation of exci-1428 1451 28 tation function for the sum of reactions: (n,d)+(n,n+p)+(n,p+n) 1428 1451 29 on Si-29. 1428 1451 30 During this procedure experimental data were corrected to the 1428 1451 31 new standards. Recommended decay data for Al-28 were taken from 1428 1451 32 Ref. [4]. 1428 1451 33 Excitation function for the Si-29(n,x)Al-28 reaction in the 1428 1451 34 energy region from threshold to 21.0 MeV was evaluated by means 1428 1451 35 of statistical analysis of experimental cross section data [1-3]. 1428 1451 36 Statistical analysis of input cross section data was carried 1428 1451 37 out by means of PADE-2 code [5]. Rational function was used as a 1428 1451 38 model function [6]. 1428 1451 39 1428 1451 40 MF=33 1428 1451 41 MT= 28 - (n,x) cross section cov. matrix 1428 1451 42 ---------------------------------------- 1428 1451 43 Uncertainties in the evaluated excitation function for the 1428 1451 44 reaction Si-29(n,x)Al-28 are given in the form of relative covari-1428 1451 45 ance matrix for the 34-neutron energy groups (LB=5). Covariance 1428 1451 46 matrix of uncertainties was calculated simultaneously with 1428 1451 47 recommended cross section data by means of PADE-2 code [79]. 1428 1451 48 Eigenvalues of the 6-th digits relative covariance matrix 1428 1451 49 given in the 33-file are the following: 1428 1451 50 1428 1451 51 1.38291E-07 1.45684E-07 1.53619E-07 1.57350E-07 1428 1451 52 1.71760E-07 1.84010E-07 2.01824E-07 2.25668E-07 1428 1451 53 2.60062E-07 3.06234E-07 3.73236E-07 4.70728E-07 1428 1451 54 6.15920E-07 8.37681E-07 1.18498E-06 1.73929E-06 1428 1451 55 2.64435E-06 4.14810E-06 6.66763E-06 1.08958E-05 1428 1451 56 1.79482E-05 2.95511E-05 4.84674E-05 7.93909E-05 1428 1451 57 1.31738E-04 2.26979E-04 4.57402E-04 7.85638E-04 1428 1451 58 1.36194E-03 1.64593E-02 3.07932E-02 3.87625E-02 1428 1451 59 7.11910E-02 8.25915E-02 1428 1451 60 1428 1451 61 References: 1428 1451 62 1. Y.Ikeda et al., Report JAERI-1312, March 1988 1428 1451 63 2. A.Fessler et al., Nucl. Sci. Eng. 134 (2000) 171-200. 1428 1451 64 3. H.Sakane et al., Annals of Nuclear Energy 29 (2002) 53-66 1428 1451 65 4. M.S.Basunia, Nuclear Data Sheets v. 114, p.1189, 2013 1428 1451 66 5. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 1428 1451 67 6. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 1428 1451 68 st's Meeting on Evaluation and Processing of Covariance Data, 1428 1451 69 Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105 1428 1451 70 1428 1451 71 ***************************************************************** 1428 1451 72 ***************** Program LINEAR (VERSION 2012-1) ***************1428 1451 73 For All Data Greater than 1.0000D-10 barns in Absolute Value 1428 1451 74 Data Linearized to Within an Accuracy of .100000000 per-cent 1428 1451 75 ***************** Program GROUPIE (VERSION 2012-1) **************1428 1451 76 Unshielded Group Averages Using 640 Groups 1428 1451 77 Weighting Spectrum: Flat (Constant) Spectrum 1428 1451 78 1 451 68 31428 1451 79 2 151 4 31428 1451 80 8 5 2 11428 1451 81 10 5 44 11428 1451 82 40 5 115 11428 1451 83 1428 1 0 84 1428 0 0 85 14029.0000 28.7276000 0 0 1 01428 2151 86 1.402900+4 1.000000+0 0 0 1 01428 2151 87 1.000000-5 1.300000+6 0 0 0 01428 2151 88 5.000000-1 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