IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 15031.0000 30.7077000 0 0 41 11525 1451 1 0.0 0.0 0 0 0 61525 1451 2 1.00000000 60000000.0 0 0 10 11525 1451 3 300.000000 0.0 1 0 138 41525 1451 4 15-P - 31 FEI EVAL-Apr14 K.I.Zolotarev 1525 1451 5 DIST-Apr14 1525 1451 6 ----BROND-1 MATERIAL 1525 1525 1451 7 -----INCIDENT NEUTRON DATA 1525 1451 8 ------ENDF-6 FORMAT 1525 1451 9 ******************************************************************1525 1451 10 The evaluation was performed by K. Zolotarev under contract with 1525 1451 11 the IAEA, August 2014. 1525 1451 12 ******************************************************************1525 1451 13 ***************************************************************** 1525 1451 14 Author of evaluation: K.Zolotarev RRDF-2014j 1525 1451 15 ***************************************************************** 1525 1451 16 MF=3 1525 1451 17 MT=103 - (n,p) cross section 1525 1451 18 ------------------------------------- 1525 1451 19 Microscopic experimental data [1-19] were analyzed in the 1525 1451 20 process of preparation of input data base for the evaluation of 1525 1451 21 cross sections and their uncertainty for the P-31(n,p)Si-31 reac-1525 1451 22 tion. During this procedure experimental data of works [6], [10], 1525 1451 23 [14-18] were corrected for the new standards of relevant monitor 1525 1451 24 reactions and to the recommended decay data for Si-31 [20]. 1525 1451 25 Special correction was applied to the experimental data [3], 1525 1451 26 [8] and [13]. 1525 1451 27 Experimental data by Ricamo et al. [3] and Cuzzocrea et al. 1525 1451 28 [8] were renormalized to the absolute cross section of 74 mb mea-1525 1451 29 sured by Metzger et al. [1] at 3 MeV. Correction factors for the 1525 1451 30 experimental data [3] and [8] were Fc=1.39623 and Fc=1.07246, res-1525 1451 31 pectively. 1525 1451 32 Cross sections measured by Paulsen and Liskien [13], were re- 1525 1451 33 normalized to the results of corrected data of Ricamo et al. [3] 1525 1451 34 in the overlapping energy range 1.91-2.22 MeV. Correction factor 1525 1451 35 for the experimental data [13] was equal to Fc=1.88603. 1525 1451 36 The results of cross section measurement obtained by Grundl 1525 1451 37 et al. at 1.59, 1.98, 2.08, 2.19, 2.57, 4.54 MeV with T(p,n) He3 1525 1451 38 source [6] were rejected due to a significant inconsistency with 1525 1451 39 experimental data [3], [8], [13], [14]. All the rest results pre- 1525 1451 40 sented in the work [6] are agreed well with the main bulk of expe-1525 1451 41 rimental data 1525 1451 42 Experimental data of Morita [7] were taken into account in 1525 1451 43 the evaluation only for four neutron energies: 4.85, 5.05, 5.08 1525 1451 44 and 5.22 MeV. Data of Morita obtained for the neutron energies: 1525 1451 45 3.18, 3.70, 3.93, 4.23, 4.59 and 4.71 MeV were rejected due to a 1525 1451 46 big underestimation of the P-31(n,p)Si-31 reaction cross sections.1525 1451 47 Experimental data [5], [9], [11], [15], [17] and [19] were re-1525 1451 48 jected completely. 1525 1451 49 Excitation function for the P-31(n,p)Si-31 reaction in the 1525 1451 50 energy region from threshold to 60.0 MeV was evaluated by means 1525 1451 51 of statistical analysis of experimental cross section data [1-4], 1525 1451 52 [6-8], [10], [12-14], [16] and [18]. 1525 1451 53 Statistical analysis of input cross section data was carried 1525 1451 54 out by means of PADE-2 code [21]. Rational function was used as 1525 1451 55 the model function [22]. 1525 1451 56 Evaluated P-31(n,p)Si-31 reaction excitation function was tes-1525 1451 57 ted with using integral experimental data [23-25] for U-235 ther-1525 1451 58 mal fission neutron spectrum. Data for U-235 thermal fission and 1525 1451 59 Cf-252 spontaneous fission neutron spectra were taken from Refs. 1525 1451 60 [26] and [27]. Experimental data [23-25] were corrected to a new 1525 1451 61 standards. Calculated and measured integral cross-section values 1525 1451 62 are given below. 1525 1451 63 1525 1451 64 ----------------------+-----------------+----------------------- 1525 1451 65 TYPE OF SPECTRUM | ,mb (calc.) | , mb (measured) 1525 1451 66 ----------------------+-----------------+----------------------- 1525 1451 67 U-235 neutron fission | 35.553 | 35.860 +- 0.961 [ *] 1525 1451 68 ----------------------+-----------------+----------------------- 1525 1451 69 CF-252 spont. fission | 38.059 | 1525 1451 70 ----------------------+-----------------+----------------------- 1525 1451 71 * - averaged value obtained from experimental data [23-25] 1525 1451 72 1525 1451 73 MF=33 1525 1451 74 MT=103 - (n,p) cross section cov. matrix 1525 1451 75 ---------------------------------------- 1525 1451 76 Uncertainties in the evaluated excitation function for the 1525 1451 77 reaction P-31(n,p)Si-31 are given in the form of relative covari- 1525 1451 78 ance matrix for the 49-neutron energy groups (LB=5). Covariance 1525 1451 79 matrix of uncertainties was calculated simultaneously with 1525 1451 80 recommended cross section data by means of PADE-2 code [79]. 1525 1451 81 Eigenvalues of the 6-th digits relative covariance matrix 1525 1451 82 given in the 33-file are the following: 1525 1451 83 1525 1451 84 5.38552E-06 5.42546E-06 5.49295E-06 5.58236E-06 1525 1451 85 5.68435E-06 5.77416E-06 5.88076E-06 5.99372E-06 1525 1451 86 6.10786E-06 6.27080E-06 6.44260E-06 6.62665E-06 1525 1451 87 6.78016E-06 6.95439E-06 7.15837E-06 7.39258E-06 1525 1451 88 7.65034E-06 7.93518E-06 8.33963E-06 9.09499E-06 1525 1451 89 9.90255E-06 1.20506E-05 1.41999E-05 1.65407E-05 1525 1451 90 1.98650E-05 2.46131E-05 3.08057E-05 3.85476E-05 1525 1451 91 4.97276E-05 7.11644E-05 1.04551E-04 1.43529E-04 1525 1451 92 2.00228E-04 2.52363E-04 2.82557E-04 3.99537E-04 1525 1451 93 5.05723E-04 5.57454E-04 5.96886E-04 6.56820E-04 1525 1451 94 7.65270E-04 1.33891E-03 2.75159E-03 3.50366E-03 1525 1451 95 5.27493E-03 1.70350E-02 2.92498E-02 1.06080E-01 1525 1451 96 1.66145E-01 1525 1451 97 1525 1451 98 References: 1525 1451 99 1. F.Metzger, F.Alder, P.Huber, Helvetica Physica Acta 21 (1948) 1525 1451 100 278 (in German). 1525 1451 101 2. W.J.Knox, Phys. Rev. 75 (1949) 537 1525 1451 102 3. R.Ricamo et al., Nuovo Cimento 8 (1951) 383-402 1525 1451 103 4. S.G.Forbes, Phys. Rev. 88 (1952) 1309 1525 1451 104 5. E.B.Paul, R.L.Clarke, Canadian J. Phys. 31 (1953) 267 1525 1451 105 6. J.A.Grundl et al., Phys. Rev. 109 (1958) 425-428 1525 1451 106 7. W.Morita, J. Phys. Soc. Japan 13 (1958) 431-433 1525 1451 107 8. P.Cuzzocrea et al., Nuovo Cimento 16 (1960) 450 1525 1451 108 9. D.L.Allan, Nucl. Phys. 24 (1961) 274 1525 1451 109 10. J.Kantele, D.G.Gardner, Nucl. Phys. 35 (1962) 353 1525 1451 110 11. F.L.Hassler, R.A.Peck JR, Phys. Rev. 125 (1962) 1011 1525 1451 111 12. B.Grimeland, E.Kjellsby, J.Vines, Phys. Rev. B137 (1965) 878 1525 1451 112 13. A.Paulsen, H.Liskien, Proc. of the 1-st IAEA Conf. on Nuclear 1525 1451 113 Data for Reactors, Paris, 17-21 October 1966, STI/PUB/140, 1525 1451 114 1967, p.217 1525 1451 115 14. J.A.Grundl, Nucl. Sci. Eng. 30 (1967) 39 1525 1451 116 15. A.Pasquarelli, Nucl. Phys. A93 (1967) 218-222 1525 1451 117 16. W.Schantl, EXFOR 21846.019, Abstract communicated by Nuclear 1525 1451 118 Data Section, IAEA, Vienna, 1970 1525 1451 119 17. R.Prasad, D.C.Sarkar, Nuovo Cimento A3 (1971) 467 1525 1451 120 18. J.C.Robertson, B.Audric, P.Kolkowski, J. of Nuclear Energy 27 1525 1451 121 (1973) 531 1525 1451 122 19. D.V.Aleksandrov et al., Atomnaja Energija 39 (1975) 137 1525 1451 123 20. C.Ouellet, B.Singh, Nuclear Data Sheets 114 (2013) 209 1525 1451 124 21. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 1525 1451 125 22. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 1525 1451 126 st's Meeting on Evaluation and Processing of Covariance Data, 1525 1451 127 Oak Ridge, USA, 1992, OECD, Paris, 1993, p.105 1525 1451 128 23. J.W.Boldeman, Nuclear Energy AB 18 (1964) 417 1525 1451 129 24. J.A.Grundl Nucl. Sci. Eng., v.31, p.191, 1968 1525 1451 130 25. K.Kobayashi, I.Kimura, Report EUR-6813, p.1004, 1980 1525 1451 131 26. P.G.Young et al., Evaluated Neutron Data for Uranium-235, 1525 1451 132 ENDF/B-VII.1 Library, MAT=9228, MF=5, MT=18, eval. Sept. 2006 1525 1451 133 27. W.Mannhart, Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 1525 1451 134 ***************************************************************** 1525 1451 135 1525 1451 136 ***************** Program LINEAR (VERSION 2012-1) ***************1525 1451 137 For All Data Greater than 1.0000D-10 barns in Absolute Value 1525 1451 138 Data Linearized to Within an Accuracy of .100000000 per-cent 1525 1451 139 ***************** Program GROUPIE (VERSION 2012-1) **************1525 1451 140 Unshielded Group Averages Using 640 Groups 1525 1451 141 Weighting Spectrum: Flat (Constant) Spectrum 1525 1451 142 1 451 136 11525 1451 143 2 151 4 11525 1451 144 3 103 122 11525 1451 145 33 103 224 11525 1451 146 1525 1 0 147 1525 0 0 148 15031.0000 30.7077000 0 0 1 01525 2151 149 1.503100+4 1.000000+0 0 0 1 01525 2151 150 1.000000+0 2.000000+7 0 0 0 01525 2151 151 5.000000-1 4.100000-1 0 0 0 01525 2151 152 1525 2 0 153 1525 0 0 154 15031.0000 30.7077000 0 0 0 01525 3103 155 -709160.000-709160.000 0 0 1 1981525 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