IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 16032.0000 31.6974000 0 0 41 11625 1451 1 0.0 0.0 0 0 0 61625 1451 2 1.00000000 60000000.0 0 0 10 21625 1451 3 300.000000 0.0 1 0 152 41625 1451 4 16-S - 32 FEI EVAL-Nov07 K.I.Zolotarev 1625 1451 5 DIST-Feb08 rev. 26.02.2008 1625 1451 6 ----BROND-2 MATERIAL 1625 1625 1451 7 -----INCIDENT NEUTRON DATA 1625 1451 8 ------ENDF-6 FORMAT 1625 1451 9 ******************************************************************1625 1451 10 IAEA, July 2011 (A. Trkov) 1625 1451 11 Extended cross sections and covariances from 21 to 60 MeV 1625 1451 12 by TENDL-2010, renormalised for continuity. 1625 1451 13 ******************************************************************1625 1451 14 ***************************************************************** 1625 1451 15 * Extension to the International Reactor Dosimetry Library * 1625 1451 16 * supported partially by the International Atomic Energy Agency * 1625 1451 17 * through IAEA research contract 13335. * 1625 1451 18 * Published as a technical report INDC(NDS)-0526 (2008). * 1625 1451 19 * Available online at * 1625 1451 20 * http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/ * 1625 1451 21 * indc-nds-0526.pdf * 1625 1451 22 ***************************************************************** 1625 1451 23 ------Russian Reactor Dosimetry File RRDF-2008 1625 1451 24 ***************************************************************** 1625 1451 25 Author of evaluation: K.I.Zolotarev 1625 1451 26 ***************************************************************** 1625 1451 27 MF=3 1625 1451 28 MT=103 - (n,p) cross section 1625 1451 29 ------------------------------------- 1625 1451 30 Microscopic experimental data [1-17] were analyzed in the 1625 1451 31 process of preparation of input data base for the evaluation of 1625 1451 32 cross sections and their uncertainty for the S-32(n,p)P-32 1625 1451 33 reaction. During this procedure all experimental data if it was 1625 1451 34 possible were corrected to the new recommended cross section data 1625 1451 35 for monitor reactions used in the measurements and to the new re- 1625 1451 36 commended decay data. 1625 1451 37 Excitation function for the S-32(n,p)P-32 reaction in the 1625 1451 38 energy region from threshold to 21 MeV was evaluated by means of 1625 1451 39 statistical analysis of experimental cross section data [1-14]. 1625 1451 40 The energy dependence of cross-section from 1.56 MeV to 1625 1451 41 threshold was extrapolated with L=0 penetrability function for 1625 1451 42 the outgoing p + P-32 channal [18]. 1625 1451 43 Total uncertaity of 15-21 % was assigned to the experimental 1625 1451 44 data of Klema and Hanson [1]. Systematic error of 15 % was added 1625 1451 45 to the experimental data of Recamo et al. [2]. Uncertainty in the 1625 1451 46 standard cross sections was added to the experimental data [6], 1625 1451 47 [8] and [14]. 1625 1451 48 Allan obtained for neutron energy 14 MeV two values of cross 1625 1451 49 section (289+-25) mb and (365+-25) mb [5]. The second value is 1625 1451 50 contradicted to the main bulck of experimental data and did not 1625 1451 51 take into account in the evaluation. 1625 1451 52 Experimental data given in the ref. [15-17] were rejected due 1625 1451 53 to their significant overestimation of the S-32(n,p)P-32 reaction 1625 1451 54 cross sections. In the rejected experimental data [15-17] cross 1625 1451 55 section values were measured only in a one energy point in the 1625 1451 56 interval 14 - 15 MeV. 1625 1451 57 Statistical analysis of input cross section data was carried 1625 1451 58 out by means of PADE-2 code [19]. Rational function was used as 1625 1451 59 the model function [20]. 1625 1451 60 The evaluated S-32(n,p)P-32 reaction excitation function ave- 1625 1451 61 raged over U-235 thermal fission neutron spectrum [21] and Cf-252 1625 1451 62 spontaneous fission neutron spectrum [22] gives the following 1625 1451 63 values : 1625 1451 64 1625 1451 65 ----------------------+-----------------+---------------------- 1625 1451 66 Type of spectrum I ,mb (calc.) I , mb (measured) 1625 1451 67 ----------------------+-----------------+---------------------- 1625 1451 68 U-235 neutron fission I 68.195 I 69.080 +- 1.361 [24] 1625 1451 69 ----------------------+-----------------+---------------------- 1625 1451 70 CF-252 spont. fission I 74.106 I 73.240 +- 2.695 [23] 1625 1451 71 I I 72.540 +- 2.532 [24] 1625 1451 72 ----------------------+-----------------+---------------------- 1625 1451 73 1625 1451 74 Experimental data [23] for the Cf-252 neutron field was renorma- 1625 1451 75 lized to the recommended cross section value for the monitor reac-1625 1451 76 tion Al-27(n,a)Na-24 from ref. [24]. 1625 1451 77 1625 1451 78 MF=33 1625 1451 79 MT=103 - (n,p) cross section cov. matrix 1625 1451 80 ---------------------------------------- 1625 1451 81 Uncertainties in the evaluated excitation function for the 1625 1451 82 reaction S-32(n,p)P-32 are given in the form of relative covari-1625 1451 83 ance matrix for the 49-neutron energy groups (LB=5). Covariance 1625 1451 84 matrix of uncertainties was calculated simultaneously with 1625 1451 85 recommended cross section data by means of PADE-2 code [19]. 1625 1451 86 Eigenvalues of the 6-th digits relative covariance matrix 1625 1451 87 given in the 33-file are the following: 1625 1451 88 1625 1451 89 1.12232E-07 1.14729E-07 1.18410E-07 1.23857E-07 1625 1451 90 1.30192E-07 1.37164E-07 1.46109E-07 1.53138E-07 1625 1451 91 1.56481E-07 1.61518E-07 1.84699E-07 1.99948E-07 1625 1451 92 2.24947E-07 2.38904E-07 2.63635E-07 2.90586E-07 1625 1451 93 3.07528E-07 3.96799E-07 5.14078E-07 6.63438E-07 1625 1451 94 8.48014E-07 1.07152E-06 1.33780E-06 1.64978E-06 1625 1451 95 2.01146E-06 2.68104E-06 8.71278E-06 1.41994E-04 1625 1451 96 2.86573E-04 3.27802E-04 3.58509E-04 4.02195E-04 1625 1451 97 4.32464E-04 5.63640E-04 6.98782E-04 8.08989E-04 1625 1451 98 9.55269E-04 1.05650E-03 1.15169E-03 1.28651E-03 1625 1451 99 1.34043E-03 1.42786E-03 1.62758E-03 1.70408E-03 1625 1451 100 1.85140E-03 3.93999E-03 7.38416E-03 1.39707E-02 1625 1451 101 1.66101E-02 1625 1451 102 1625 1451 103 References : 1625 1451 104 1. E.D.Klema, A.O.Hanson Phys. Rev., v.73, p.106, January 1948 1625 1451 105 2. R.Ricamo et al. Nuovo Cimento, v.8, p.383, March 1951 1625 1451 106 3. L.Allen jr, W.A.Biggers, R.J.Prestwood, R.K.Smith 1625 1451 107 Phys. Rev. ,v.107, p.1363, September 1957 1625 1451 108 4. L.Colli et al. Nuovo Cimento, v.17, p.634, September 1960 1625 1451 109 5. D.L.Allan Nucl. Phys., v.24, p.274, April 1961 1625 1451 110 6. D.C.Santry, J.P.Butler Can. J. Chemistry, v.41, p.123, 1963 1625 1451 111 7. V.N.Levkovskij J. Eksperim. i Teor. Fiziki (Sov), v.45, no.2 1625 1451 112 p.305, 1963 1625 1451 113 8. A.Paulsen, H.Liskien Proc. of the 1-st IAEA Conference on 1625 1451 114 Nuclear Data for Reactors, Paris, 17-21 October 1966, p.217 1625 1451 115 9. A.Pasquarelli Nucl. Phys., v.A93, p.218, March 1967 1625 1451 116 10. V.N.Levkovskij et al. Jadernaja Fizika (Sov.), v.8(1), p.7, 1625 1451 117 July, 1968 1625 1451 118 11. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 1625 1451 119 12. R.C.Barrall et al. Nucl. Phys. A, v.138, p.387, December 1969 1625 1451 120 13. W.Schantl Abstract communicated by NDS, IAEA, Vienna, 1970 ; 1625 1451 121 W.Schantl EXFOR 21846020 1625 1451 122 14. J.C.Robertson, B.Audric, P.Kolkowski Journ. Nucl. Energ., 1625 1451 123 v.27, p.531, August 1973 1625 1451 124 15. E.B.Paul, R.L.Clarke Can. J. Phys., v.31, p.267, 1953 1625 1451 125 16. C.S.Khurana, H.S.Hans Proc. of Symp. on Low Energy Nuclear 1625 1451 126 Physics, Waltair, India, 24-26 February 1960, p.297 1625 1451 127 17. C.S.Khurana, I.M.Govil Nucl. Physics, v.69, p.153, July 1965 1625 1451 128 18. S.A.Badikov, A.B.Pashchenko Voprosy Atomnoy Nauki i Tekhniki 1625 1451 129 Ser. Jadernye Konstanty, 2(53), p.70, 1987 1625 1451 130 19. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 1625 1451 131 20. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 1625 1451 132 st's Meeting on Evaluation and Processing of Covariance Data, 1625 1451 133 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 1625 1451 134 21. L.W.Weston et al. Evaluated Neutron Data for Uranium-235, 1625 1451 135 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 1625 1451 136 22. W.Mannhart Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 1625 1451 137 23. K.Kobayashi, I.Kimura, W.Mannhart J. of Nuclear Science and 1625 1451 138 Technology, v.19, p.341, May 1982 ; 1625 1451 139 K.Kobayashi, I.Kimura, H.Gotoh, H.Tominaga Progress Report 1625 1451 140 NEANDC(J)-106/U, p.41, September 1984 1625 1451 141 24. W.Mannhart Validation of Differential Cross Sections with 1625 1451 142 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 1625 1451 143 September 2002 1625 1451 144 ***************************************************************** 1625 1451 145 1625 1451 146 ***************** Program SIGMA1 (VERSION 2010-1) ***************1625 1451 147 Data Doppler Broadened to 300.000000 Kelvin 1625 1451 148 for All Data Greater than 1.0000E-10 barns in Absolute Value 1625 1451 149 Data Linearized to Within an Accuracy of .010000000 per-cent 1625 1451 150 ***************** Program LINEAR (VERSION 2012-1) ***************1625 1451 151 For All Data Greater than 1.0000D-10 barns in Absolute Value 1625 1451 152 Data Linearized to Within an Accuracy of .100000000 per-cent 1625 1451 153 ***************** Program GROUPIE (VERSION 2012-1) **************1625 1451 154 Unshielded Group Averages Using 640 Groups 1625 1451 155 Weighting Spectrum: Flat (Constant) Spectrum 1625 1451 156 1 451 149 11625 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