IRDF-ext 777 0 0 0 1.603200+4 3.169740+1 0 0 41 11625 1451 1 0.000000+0 0.000000+0 0 0 0 61625 1451 2 1.000000+0 2.100000+7 0 0 10 21625 1451 3 0.000000+0 0.000000+0 0 0 137 31625 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 * Extension to the International Reactor Dosimetry Library * 1625 1451 11 * supported partially by the International Atomic Energy Agency * 1625 1451 12 * through IAEA research contract 13335. * 1625 1451 13 * Published as a technical report INDC(NDS)-0526 (2008). * 1625 1451 14 * Available online at * 1625 1451 15 * http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/ * 1625 1451 16 * indc-nds-0526.pdf * 1625 1451 17 ***************************************************************** 1625 1451 18 ------Russian Reactor Dosimetry File RRDF-2008 1625 1451 19 ***************************************************************** 1625 1451 20 Author of evaluation: K.I.Zolotarev 1625 1451 21 ***************************************************************** 1625 1451 22 MF=3 1625 1451 23 MT=103 - (n,p) cross section 1625 1451 24 ------------------------------------- 1625 1451 25 Microscopic experimental data [1-17] were analyzed in the 1625 1451 26 process of preparation of input data base for the evaluation of 1625 1451 27 cross sections and their uncertainty for the S-32(n,p)P-32 1625 1451 28 reaction. During this procedure all experimental data if it was 1625 1451 29 possible were corrected to the new recommended cross section data 1625 1451 30 for monitor reactions used in the measurements and to the new re- 1625 1451 31 commended decay data. 1625 1451 32 Excitation function for the S-32(n,p)P-32 reaction in the 1625 1451 33 energy region from threshold to 21 MeV was evaluated by means of 1625 1451 34 statistical analysis of experimental cross section data [1-14]. 1625 1451 35 The energy dependence of cross-section from 1.56 MeV to 1625 1451 36 threshold was extrapolated with L=0 penetrability function for 1625 1451 37 the outgoing p + P-32 channal [18]. 1625 1451 38 Total uncertaity of 15-21 % was assigned to the experimental 1625 1451 39 data of Klema and Hanson [1]. Systematic error of 15 % was added 1625 1451 40 to the experimental data of Recamo et al. [2]. Uncertainty in the 1625 1451 41 standard cross sections was added to the experimental data [6], 1625 1451 42 [8] and [14]. 1625 1451 43 Allan obtained for neutron energy 14 MeV two values of cross 1625 1451 44 section (289+-25) mb and (365+-25) mb [5]. The second value is 1625 1451 45 contradicted to the main bulck of experimental data and did not 1625 1451 46 take into account in the evaluation. 1625 1451 47 Experimental data given in the ref. [15-17] were rejected due 1625 1451 48 to their significant overestimation of the S-32(n,p)P-32 reaction 1625 1451 49 cross sections. In the rejected experimental data [15-17] cross 1625 1451 50 section values were measured only in a one energy point in the 1625 1451 51 interval 14 - 15 MeV. 1625 1451 52 Statistical analysis of input cross section data was carried 1625 1451 53 out by means of PADE-2 code [19]. Rational function was used as 1625 1451 54 the model function [20]. 1625 1451 55 The evaluated S-32(n,p)P-32 reaction excitation function ave- 1625 1451 56 raged over U-235 thermal fission neutron spectrum [21] and Cf-252 1625 1451 57 spontaneous fission neutron spectrum [22] gives the following 1625 1451 58 values : 1625 1451 59 1625 1451 60 ----------------------+-----------------+---------------------- 1625 1451 61 Type of spectrum I ,mb (calc.) I , mb (measured) 1625 1451 62 ----------------------+-----------------+---------------------- 1625 1451 63 U-235 neutron fission I 68.195 I 69.080 +- 1.361 [24] 1625 1451 64 ----------------------+-----------------+---------------------- 1625 1451 65 CF-252 spont. fission I 74.106 I 73.240 +- 2.695 [23] 1625 1451 66 I I 72.540 +- 2.532 [24] 1625 1451 67 ----------------------+-----------------+---------------------- 1625 1451 68 1625 1451 69 Experimental data [23] for the Cf-252 neutron field was renorma- 1625 1451 70 lized to the recommended cross section value for the monitor reac-1625 1451 71 tion Al-27(n,a)Na-24 from ref. [24]. 1625 1451 72 1625 1451 73 MF=33 1625 1451 74 MT=103 - (n,p) cross section cov. matrix 1625 1451 75 ---------------------------------------- 1625 1451 76 Uncertainties in the evaluated excitation function for the 1625 1451 77 reaction S-32(n,p)P-32 are given in the form of relative covari-1625 1451 78 ance matrix for the 49-neutron energy groups (LB=5). Covariance 1625 1451 79 matrix of uncertainties was calculated simultaneously with 1625 1451 80 recommended cross section data by means of PADE-2 code [19]. 1625 1451 81 Eigenvalues of the 6-th digits relative covariance matrix 1625 1451 82 given in the 33-file are the following: 1625 1451 83 1625 1451 84 1.12232E-07 1.14729E-07 1.18410E-07 1.23857E-07 1625 1451 85 1.30192E-07 1.37164E-07 1.46109E-07 1.53138E-07 1625 1451 86 1.56481E-07 1.61518E-07 1.84699E-07 1.99948E-07 1625 1451 87 2.24947E-07 2.38904E-07 2.63635E-07 2.90586E-07 1625 1451 88 3.07528E-07 3.96799E-07 5.14078E-07 6.63438E-07 1625 1451 89 8.48014E-07 1.07152E-06 1.33780E-06 1.64978E-06 1625 1451 90 2.01146E-06 2.68104E-06 8.71278E-06 1.41994E-04 1625 1451 91 2.86573E-04 3.27802E-04 3.58509E-04 4.02195E-04 1625 1451 92 4.32464E-04 5.63640E-04 6.98782E-04 8.08989E-04 1625 1451 93 9.55269E-04 1.05650E-03 1.15169E-03 1.28651E-03 1625 1451 94 1.34043E-03 1.42786E-03 1.62758E-03 1.70408E-03 1625 1451 95 1.85140E-03 3.93999E-03 7.38416E-03 1.39707E-02 1625 1451 96 1.66101E-02 1625 1451 97 1625 1451 98 References : 1625 1451 99 1. E.D.Klema, A.O.Hanson Phys. Rev., v.73, p.106, January 1948 1625 1451 100 2. R.Ricamo et al. Nuovo Cimento, v.8, p.383, March 1951 1625 1451 101 3. L.Allen jr, W.A.Biggers, R.J.Prestwood, R.K.Smith 1625 1451 102 Phys. Rev. ,v.107, p.1363, September 1957 1625 1451 103 4. L.Colli et al. Nuovo Cimento, v.17, p.634, September 1960 1625 1451 104 5. D.L.Allan Nucl. Phys., v.24, p.274, April 1961 1625 1451 105 6. D.C.Santry, J.P.Butler Can. J. Chemistry, v.41, p.123, 1963 1625 1451 106 7. V.N.Levkovskij J. Eksperim. i Teor. Fiziki (Sov), v.45, no.2 1625 1451 107 p.305, 1963 1625 1451 108 8. A.Paulsen, H.Liskien Proc. of the 1-st IAEA Conference on 1625 1451 109 Nuclear Data for Reactors, Paris, 17-21 October 1966, p.217 1625 1451 110 9. A.Pasquarelli Nucl. Phys., v.A93, p.218, March 1967 1625 1451 111 10. V.N.Levkovskij et al. Jadernaja Fizika (Sov.), v.8(1), p.7, 1625 1451 112 July, 1968 1625 1451 113 11. R.C.Barrall et al. Report AFWL-TR-68-134, March 1969 1625 1451 114 12. R.C.Barrall et al. Nucl. Phys. A, v.138, p.387, December 1969 1625 1451 115 13. W.Schantl Abstract communicated by NDS, IAEA, Vienna, 1970 ; 1625 1451 116 W.Schantl EXFOR 21846020 1625 1451 117 14. J.C.Robertson, B.Audric, P.Kolkowski Journ. Nucl. Energ., 1625 1451 118 v.27, p.531, August 1973 1625 1451 119 15. E.B.Paul, R.L.Clarke Can. J. Phys., v.31, p.267, 1953 1625 1451 120 16. C.S.Khurana, H.S.Hans Proc. of Symp. on Low Energy Nuclear 1625 1451 121 Physics, Waltair, India, 24-26 February 1960, p.297 1625 1451 122 17. C.S.Khurana, I.M.Govil Nucl. Physics, v.69, p.153, July 1965 1625 1451 123 18. S.A.Badikov, A.B.Pashchenko Voprosy Atomnoy Nauki i Tekhniki 1625 1451 124 Ser. Jadernye Konstanty, 2(53), p.70, 1987 1625 1451 125 19. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 1625 1451 126 20. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 1625 1451 127 st's Meeting on Evaluation and Processing of Covariance Data, 1625 1451 128 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 1625 1451 129 21. L.W.Weston et al. Evaluated Neutron Data for Uranium-235, 1625 1451 130 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 1625 1451 131 22. W.Mannhart Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 1625 1451 132 23. K.Kobayashi, I.Kimura, W.Mannhart J. of Nuclear Science and 1625 1451 133 Technology, v.19, p.341, May 1982 ; 1625 1451 134 K.Kobayashi, I.Kimura, H.Gotoh, H.Tominaga Progress Report 1625 1451 135 NEANDC(J)-106/U, p.41, September 1984 1625 1451 136 24. W.Mannhart Validation of Differential Cross Sections with 1625 1451 137 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 1625 1451 138 September 2002 1625 1451 139 ***************************************************************** 1625 1451 140 1625 1451 141 1 451 144 11625 1451 142 3 103 138 11625 1451 143 33 103 224 11625 1451 144 0.000000+0 0.000000+0 0 0 0 01625 1 099999 0.000000+0 0.000000+0 0 0 0 01625 0 0 0 1.603200+4 3.169740+1 0 0 0 01625 3103 1 -9.283000+5-9.283000+5 0 0 1 4051625 3103 2 405 2 1625 3103 3 9.575410+5 0.000000+0 1.200000+6 2.914130-7 1.300000+6 7.533070-61625 3103 4 1.400000+6 5.625470-5 1.500000+6 2.465010-4 1.600000+6 7.534770-41625 3103 5 1.700000+6 2.068810-3 1.720000+6 2.421570-3 1.740000+6 2.820390-31625 3103 6 1.760000+6 3.272090-3 1.780000+6 3.783710-3 1.800000+6 4.362560-31625 3103 7 1.820000+6 5.016180-3 1.840000+6 5.752250-3 1.860000+6 6.578510-31625 3103 8 1.880000+6 7.503040-3 1.900000+6 8.535390-3 1.920000+6 9.690710-31625 3103 9 1.940000+6 1.100200-2 1.960000+6 1.255370-2 1.980000+6 1.456260-21625 3103 10 2.000000+6 1.750150-2 2.020000+6 2.194830-2 2.040000+6 2.750130-21625 3103 11 2.060000+6 3.248810-2 2.080000+6 3.619440-2 2.100000+6 3.910720-21625 3103 12 2.120000+6 4.170090-2 2.140000+6 4.415790-2 2.160000+6 4.650010-21625 3103 13 2.180000+6 4.870070-2 2.200000+6 5.075220-2 2.220000+6 5.274140-21625 3103 14 2.240000+6 5.500380-2 2.260000+6 5.851890-2 2.270000+6 6.143230-21625 3103 15 2.280000+6 6.574920-2 2.300000+6 8.026270-2 2.310000+6 8.939060-21625 3103 16 2.320000+6 9.695800-2 2.330000+6 1.009850-1 2.340000+6 1.025420-11625 3103 17 2.360000+6 9.949130-2 2.380000+6 9.236280-2 2.400000+6 8.694720-21625 3103 18 2.420000+6 8.401930-2 2.440000+6 8.319980-2 2.460000+6 8.401810-21625 3103 19 2.480000+6 8.597950-2 2.500000+6 8.832080-2 2.520000+6 8.976680-21625 3103 20 2.540000+6 8.883180-2 2.560000+6 8.501610-2 2.580000+6 7.953980-21625 3103 21 2.600000+6 7.421880-2 2.620000+6 7.012600-2 2.640000+6 6.751460-21625 3103 22 2.660000+6 6.635180-2 2.680000+6 6.683800-2 2.700000+6 7.016030-21625 3103 23 2.720000+6 8.059220-2 2.730000+6 9.157380-2 2.740000+6 1.077620-11625 3103 24 2.750000+6 1.253120-1 2.760000+6 1.350130-1 2.770000+6 1.334960-11625 3103 25 2.780000+6 1.264800-1 2.800000+6 1.135130-1 2.820000+6 1.066500-11625 3103 26 2.840000+6 1.041150-1 2.860000+6 1.040210-1 2.880000+6 1.055610-11625 3103 27 2.900000+6 1.084520-1 2.920000+6 1.126760-1 2.940000+6 1.183710-11625 3103 28 2.960000+6 1.254150-1 2.980000+6 1.342440-1 3.000000+6 1.447710-11625 3103 29 3.010000+6 1.506880-1 3.020000+6 1.570070-1 3.030000+6 1.636420-11625 3103 30 3.040000+6 1.704210-1 3.050000+6 1.770340-1 3.060000+6 1.829940-11625 3103 31 3.070000+6 1.876050-1 3.080000+6 1.900250-1 3.090000+6 1.894610-11625 3103 32 3.100000+6 1.851750-1 3.110000+6 1.778330-1 3.120000+6 1.684940-11625 3103 33 3.130000+6 1.587430-1 3.140000+6 1.499140-1 3.150000+6 1.427600-11625 3103 34 3.160000+6 1.374840-1 3.170000+6 1.339450-1 3.180000+6 1.318570-11625 3103 35 3.190000+6 1.309160-1 3.200000+6 1.308540-1 3.210000+6 1.314620-11625 3103 36 3.220000+6 1.325930-1 3.230000+6 1.341520-1 3.240000+6 1.361010-11625 3103 37 3.250000+6 1.384570-1 3.260000+6 1.413060-1 3.270000+6 1.448310-11625 3103 38 3.280000+6 1.493600-1 3.290000+6 1.554370-1 3.300000+6 1.639020-11625 3103 39 3.310000+6 1.760600-1 3.320000+6 1.916830-1 3.330000+6 2.109890-11625 3103 40 3.340000+6 2.267830-1 3.350000+6 2.286170-1 3.360000+6 2.199940-11625 3103 41 3.370000+6 2.091420-1 3.380000+6 2.008010-1 3.390000+6 1.953210-11625 3103 42 3.400000+6 1.918980-1 3.410000+6 1.897980-1 3.420000+6 1.885640-11625 3103 43 3.430000+6 1.879730-1 3.440000+6 1.879680-1 3.450000+6 1.886060-11625 3103 44 3.460000+6 1.900210-1 3.470000+6 1.923900-1 3.480000+6 1.959090-11625 3103 45 3.490000+6 2.007660-1 3.500000+6 2.071100-1 3.510000+6 2.149950-11625 3103 46 3.520000+6 2.243110-1 3.530000+6 2.364770-1 3.540000+6 2.486440-11625 3103 47 3.560000+6 2.670830-1 3.580000+6 2.708890-1 3.600000+6 2.600230-11625 3103 48 3.620000+6 2.403890-1 3.640000+6 2.191490-1 3.660000+6 1.999710-11625 3103 49 3.680000+6 1.840430-1 3.700000+6 1.714380-1 3.720000+6 1.618890-11625 3103 50 3.740000+6 1.550970-1 3.760000+6 1.508180-1 3.780000+6 1.488940-11625 3103 51 3.800000+6 1.492350-1 3.820000+6 1.517470-1 3.840000+6 1.560530-11625 3103 52 3.860000+6 1.630670-1 3.880000+6 1.727860-1 3.900000+6 1.851800-11625 3103 53 3.920000+6 2.000740-1 3.940000+6 2.171140-1 3.960000+6 2.357520-11625 3103 54 3.980000+6 2.552680-1 4.000000+6 2.749740-1 4.020000+6 3.028830-11625 3103 55 4.040000+6 3.190770-1 4.060000+6 3.301670-1 4.080000+6 3.384430-11625 3103 56 4.100000+6 3.448500-1 4.120000+6 3.497950-1 4.140000+6 3.534450-11625 3103 57 4.160000+6 3.558540-1 4.180000+6 3.570300-1 4.200000+6 3.569820-11625 3103 58 4.220000+6 3.557430-1 4.240000+6 3.533910-1 4.260000+6 3.500450-11625 3103 59 4.280000+6 3.458640-1 4.300000+6 3.410330-1 4.320000+6 3.357430-11625 3103 60 4.340000+6 3.301820-1 4.360000+6 3.245150-1 4.380000+6 3.188800-11625 3103 61 4.400000+6 3.133880-1 4.420000+6 3.081170-1 4.440000+6 3.031190-11625 3103 62 4.460000+6 2.984260-1 4.480000+6 2.940500-1 4.500000+6 2.899910-11625 3103 63 4.520000+6 2.862420-1 4.540000+6 2.827870-1 4.560000+6 2.796070-11625 3103 64 4.580000+6 2.766830-1 4.600000+6 2.739950-1 4.620000+6 2.715230-11625 3103 65 4.640000+6 2.692460-1 4.660000+6 2.671490-1 4.680000+6 2.652140-11625 3103 66 4.700000+6 2.634280-1 4.720000+6 2.617770-1 4.740000+6 2.602500-11625 3103 67 4.760000+6 2.588360-1 4.780000+6 2.575280-1 4.800000+6 2.563170-11625 3103 68 4.820000+6 2.551990-1 4.840000+6 2.541670-1 4.860000+6 2.532180-11625 3103 69 4.880000+6 2.523490-1 4.900000+6 2.515580-1 4.920000+6 2.508440-11625 3103 70 4.940000+6 2.502060-1 4.960000+6 2.496440-1 4.980000+6 2.491600-11625 3103 71 5.000000+6 2.487550-1 5.020000+6 2.484320-1 5.040000+6 2.481940-11625 3103 72 5.060000+6 2.480440-1 5.080000+6 2.479880-1 5.100000+6 2.480290-11625 3103 73 5.120000+6 2.481730-1 5.140000+6 2.484250-1 5.160000+6 2.487910-11625 3103 74 5.180000+6 2.492780-1 5.200000+6 2.498910-1 5.220000+6 2.506370-11625 3103 75 5.240000+6 2.515210-1 5.260000+6 2.525500-1 5.280000+6 2.537270-11625 3103 76 5.300000+6 2.550560-1 5.320000+6 2.565420-1 5.340000+6 2.581840-11625 3103 77 5.360000+6 2.599850-1 5.380000+6 2.619400-1 5.400000+6 2.640480-11625 3103 78 5.420000+6 2.663020-1 5.440000+6 2.686940-1 5.460000+6 2.712130-11625 3103 79 5.480000+6 2.738460-1 5.500000+6 2.765790-1 5.520000+6 2.793950-11625 3103 80 5.540000+6 2.822750-1 5.560000+6 2.851990-1 5.580000+6 2.881460-11625 3103 81 5.600000+6 2.910950-1 5.620000+6 2.940250-1 5.640000+6 2.969160-11625 3103 82 5.660000+6 2.997460-1 5.680000+6 3.025000-1 5.700000+6 3.051600-11625 3103 83 5.720000+6 3.077110-1 5.740000+6 3.101440-1 5.760000+6 3.124460-11625 3103 84 5.780000+6 3.146130-1 5.800000+6 3.166380-1 5.820000+6 3.185190-11625 3103 85 5.840000+6 3.202560-1 5.860000+6 3.218490-1 5.880000+6 3.233020-11625 3103 86 5.900000+6 3.246180-1 5.920000+6 3.258030-1 5.940000+6 3.268620-11625 3103 87 5.960000+6 3.278020-1 5.980000+6 3.285950-1 6.000000+6 3.294140-11625 3103 88 6.100000+6 3.319400-1 6.200000+6 3.325520-1 6.300000+6 3.321150-11625 3103 89 6.400000+6 3.312550-1 6.500000+6 3.303690-1 6.600000+6 3.296750-11625 3103 90 6.700000+6 3.291600-1 6.800000+6 3.289260-1 6.900000+6 3.290050-11625 3103 91 7.000000+6 3.296820-1 7.100000+6 3.311830-1 7.200000+6 3.336930-11625 3103 92 7.300000+6 3.369960-1 7.400000+6 3.408230-1 7.500000+6 3.440120-11625 3103 93 7.600000+6 3.445980-1 7.700000+6 3.425990-1 7.800000+6 3.392420-11625 3103 94 7.900000+6 3.369290-1 8.000000+6 3.360720-1 8.100000+6 3.362770-11625 3103 95 8.200000+6 3.370770-1 8.300000+6 3.382620-1 8.400000+6 3.393860-11625 3103 96 8.500000+6 3.408960-1 8.600000+6 3.425630-1 8.700000+6 3.443650-11625 3103 97 8.800000+6 3.462860-1 8.900000+6 3.483180-1 9.000000+6 3.504570-11625 3103 98 9.100000+6 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