IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 59141.0000 139.697000 0 0 34 105925 1451 1 0.0 0.0 0 0 0 65925 1451 2 1.00000000 60000000.0 0 0 10 20025925 1451 3 300.000000 0.0 1 0 108 45925 1451 4 59-Pr-141 FEI EVAL-Jan97 K.I.Zolotarev et al. 5925 1451 5 DIST-Feb2004 5925 1451 6 ----IRDF-2002 MATERIAL 5925 5925 1451 7 -----INCIDENT NEUTRON DATA 5925 1451 8 ------ENDF-6 FORMAT 5925 1451 9 ******************************************************************5925 1451 10 IAEA, July 2011 (A. Trkov) 5925 1451 11 Extended cross sections and covariances from 20 to 60 MeV 5925 1451 12 by TENDL-2010, renormalised for continuity. 5925 1451 13 ******************************************************************5925 1451 14 ***************************************************************** 5925 1451 15 59-PR-141 FEI EVAL-Jan97 K.I.Zolotarev et al. 5925 1451 16 DIST-Jan02 20020123 5925 1451 17 ----BROND-2 MATERIAL 5925 5925 1451 18 -----INCIDENT NEUTRON DATA 5925 1451 19 ------ENDF-6 FORMAT 5925 1451 20 ------Russian Reactor Dosimetry File RRDF-2002 5925 1451 21 ***************************************************************** 5925 1451 22 Authors of evaluation: K.Zolotarev, V.Manokhin, A.Pashchenko 5925 1451 23 ***************************************************************** 5925 1451 24 MF= 3 5925 1451 25 MT= 16 - Pr-141(n,2n)Pr-140 reaction 5925 1451 26 -------------------------------------- 5925 1451 27 Excitation function for the Pr-141(n,2n)Pr-140 reaction in 5925 1451 28 the energy region from threshold to 20 MeV was evaluated by means 5925 1451 29 of statistical analysis of experimental cross section data [1-19] 5925 1451 30 and data from systematics of (n,2n) excitation function [20] in 5925 1451 31 the energy regions 9.5 - 12.0 MeV and 18.0 - 20.0 MeV. 5925 1451 32 All experimental data were renormalized to the new standards 5925 1451 33 for monitor reactions cross sections and decay data. 5925 1451 34 The final procedure of evaluation has been carried out within 5925 1451 35 the framework of generalized least squares method. Rational func- 5925 1451 36 tion was used as model function [21]. Calculations was performed 5925 1451 37 by means of Pade-2 code [22]. 5925 1451 38 U-235 thermal fission [23] and Cf-252 spontaneous fission 5925 1451 39 neutron spectra [24] averaged cross-sections calculated from the 5925 1451 40 evaluated Pr141(n,2n)Pr140 excitation function are the following: 5925 1451 41 5925 1451 42 -------------------------------------------- 5925 1451 43 TYPE OF SPECTRUM I CS>, mb (calc.) 5925 1451 44 --------------------------I----------------- 5925 1451 45 U-235 neutron fission I 1.0922 5925 1451 46 CF-252 spontan. fission I 1.9843 5925 1451 47 5925 1451 48 MF=33 5925 1451 49 MT= 16 -(n,2n) cross section cov. matrix 5925 1451 50 ---------------------------------------- 5925 1451 51 Uncertainties in the evaluated excitation function for the re-5925 1451 52 action Pr-141(n,2n)Pr-140 are given in the form of relative cova- 5925 1451 53 riance matrix for the 18-neutron energy groups (LB=5). Covariance 5925 1451 54 matrix of uncertainties was calculated simultaneously with 5925 1451 55 recommended cross section data by means of PADE-2 code. 5925 1451 56 Eigenvalues of the 6-th digits relative covariance matrix 5925 1451 57 given in the 33-file are the following: 5925 1451 58 5925 1451 59 6.47369E-06 6.50089E-06 6.56924E-06 6.70314E-06 5925 1451 60 6.90792E-06 7.20594E-06 7.64163E-06 8.30022E-06 5925 1451 61 9.35563E-06 1.12079E-05 1.49213E-05 2.36154E-05 5925 1451 62 4.48092E-05 3.28699E-04 6.81059E-03 1.70941E-02 5925 1451 63 2.55798E-02 1.53270E-01 5925 1451 64 5925 1451 65 References : 5925 1451 66 1. E.B.Paul, R.L.Clarke Canadian J. Phys., v.31,p.267, 1953 5925 1451 67 2. J.M.Ferguson, W.E.Thompson Phys. Rev., v.118, p.228, 1960 5925 1451 68 3. R.G.Wille, R.W.Fink Phys. Rev., v.118, p.242, 1960 5925 1451 69 4. L.A.Rayburn Phys. Rev., v.122, p.168, 1961 5925 1451 70 5. C.S.Khurana, H.S.Hans Nucl. Phys., v.28, p.560, 1961 5925 1451 71 6. D.R.Koehler, W.L.Alford Report NP-11667, 1962 5925 1451 72 7. M.Cevolani, S.Petralia Nucl. Sci. Eng., v.26, p.1328, 1962 5925 1451 73 8. L.A.Rayburn Bull. American Phys. Soc., v.8, p.60, Jan. 1963 5925 1451 74 9. M.P.Menon, M.Y.Cuypers Phys. Rev., v.156, p.1340, 1967 5925 1451 75 10. P.Cuzzocrea e.a. Nuovo Cimento, Sec.B, v.52, n.2, p.476, 1967 5925 1451 76 11. M.Bormann e.a. Nucl. Phys., Sec.A, v.115, p.309, July 1968 5925 1451 77 12. G.Peto e.a. Acta Physica Hung., v.24, p.93, April 1968 5925 1451 78 13. A.Chatterjee e.a. Proc. of 12th Nucl. Phys. and Solid State 5925 1451 79 Phys. Sympos., Roorkee, India, 28-31 December 1969, v.2,p.117 5925 1451 80 14. A.Bari Dissertation Abstracts, sec.B, v.32, p.5091, 1972 5925 1451 81 15. J.Araminowicz, J.Dresler Prog. Rep. INR-1464, p.14, May 1973 5925 1451 82 16. R.A.Sigg, P.K.Kuroda Inorg. Nucl. Chem., v.37, p.631, 1975 5925 1451 83 17. M.Valkonen Report JU-RR-1/1976, Jyvaeskylae University, 1976 5925 1451 84 18. S.Murahira et al. Report INDC(JPN)-175/U, p.171, Nov. 1995 5925 1451 85 19. Y.Kasugai, Y.Ikeda, Y.Uno Proc. of Int. Conf. on Nuclear Data 5925 1451 86 for Science and Technology, Trieste, Italy, 19-24 May 1997, 5925 1451 87 v.1, p.635 5925 1451 88 20. V.N.Manokhin Report INDC(CCP)-397, IAEA, Vienna, 1997 5925 1451 89 21. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 5925 1451 90 st's Meeting on Evaluation and Processing of Covariance Data, 5925 1451 91 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p.105 5925 1451 92 22. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 5925 1451 93 23. L.W.Weston et al. Evaluated Neutron Data for U-235, ENDF/B-VI 5925 1451 94 Library, MAT=9228, MF=5, MT=18, eval. April 1989 5925 1451 95 24. W.Mannhart IAEA-TECDOC-410, p.158, Vienna, 1987 5925 1451 96 ******************************************************************5925 1451 97 The Q values and threshold energies were updated prior to pro- 5925 1451 98 cessing through the codes to comply with the values obtained 5925 1451 99 using the NNDC calculation program which is based on the 1995 5925 1451 100 Update to the Atomic mass Evaluation. 5925 1451 101 5925 1451 102 File 2 added to the pointwise file containing only the effective 5925 1451 103 scattering radius with no resonance parameters given. 5925 1451 104 Taken from ENDF/B-VI 5925 1451 105 ******************************************************************5925 1451 106 ***************** Program LINEAR (VERSION 2012-1) ***************5925 1451 107 For All Data Greater than 1.0000D-10 barns in Absolute Value 5925 1451 108 Data Linearized to Within an Accuracy of .100000000 per-cent 5925 1451 109 ***************** Program GROUPIE (VERSION 2012-1) **************5925 1451 110 Unshielded Group Averages Using 640 Groups 5925 1451 111 Weighting Spectrum: Flat (Constant) Spectrum 5925 1451 112 1 451 105 15925 1451 113 2 151 4 15925 1451 114 3 16 107 15925 1451 115 33 16 45 15925 1451 116 5925 1 0 117 5925 0 0 118 59141.0000 139.697000 0 0 1 05925 2151 119 5.914100+4 1.000000+0 0 0 1 05925 2151 120 1.000000-5 1.004920+4 0 0 0 05925 2151 121 2.500000+0 4.930000-1 0 0 0 05925 2151 122 5925 2 0 123 5925 0 0 124 59141.0000 139.697000 0 0 0 05925 3 16 125 -9397000.00-9397000.00 0 0 1 1075925 3 16 126 107 1 5925 3 16 127 9400000.00 1.02030E-4 9500000.00 .004115304 9600000.00 .0164385955925 3 16 128 9700000.00 .038856950 9800000.00 .070499450 9900000.00 .1102883505925 3 16 129 10000000.0 .157013000 10100000.0 .209402000 10200000.0 .2661885005925 3 16 130 10300000.0 .326164000 10400000.0 .388315750 10500000.0 .4513412505925 3 16 131 10600000.0 .514366750 10700000.0 .577392250 10800000.0 .6395045005925 3 16 132 10900000.0 .699850500 11000000.0 .758343500 11100000.0 .8147340005925 3 16 133 11200000.0 .868854500 11300000.0 .920604500 11400000.0 .9699370005925 3 16 134 11500000.0 1.01684800 11600000.0 1.06136500 11700000.0 1.102987505925 3 16 135 11800000.0 1.14290250 11900000.0 1.18068500 12000000.0 1.216335005925 3 16 136 12100000.0 1.25004500 12200000.0 1.28181500 12300000.0 1.311847505925 3 16 137 12400000.0 1.34014250 12500000.0 1.36689000 12600000.0 1.392090005925 3 16 138 12700000.0 1.41561500 12800000.0 1.43746500 12900000.0 1.459315005925 3 16 139 13000000.0 1.47946167 13100000.0 1.49790500 13200000.0 1.516348335925 3 16 140 13300000.0 1.53338000 13400000.0 1.54900000 13500000.0 1.564620005925 3 16 141 13600000.0 1.57889750 13700000.0 1.59183250 13800000.0 1.604767505925 3 16 142 13900000.0 1.61770250 14000000.0 1.62927600 14100000.0 1.639488005925 3 16 143 14200000.0 1.64970000 14300000.0 1.65991200 14400000.0 1.670124005925 3 16 144 14500000.0 1.67916600 14600000.0 1.68703800 14700000.0 1.694910005925 3 16 145 14800000.0 1.70278200 14900000.0 1.71065400 15000000.0 1.717540835925 3 16 146 15100000.0 1.72344250 15200000.0 1.72934417 15300000.0 1.735245835925 3 16 147 15400000.0 1.74114750 15500000.0 1.74704917 15600000.0 1.752039295925 3 16 148 15700000.0 1.75611786 15800000.0 1.76019643 15900000.0 1.764275005925 3 16 149 16000000.0 1.76835357 16100000.0 1.77243214 16200000.0 1.776510715925 3 16 150 16300000.0 1.77971063 16400000.0 1.78203188 16500000.0 1.784353135925 3 16 151 16600000.0 1.78667438 16700000.0 1.78899563 16800000.0 1.791316885925 3 16 152 16900000.0 1.79363813 17000000.0 1.79595938 17100000.0 1.797471675925 3 16 153 17200000.0 1.79817500 17300000.0 1.79887833 17400000.0 1.799581675925 3 16 154 17500000.0 1.80028500 17600000.0 1.80098833 17700000.0 1.800834175925 3 16 155 17800000.0 1.79982250 17900000.0 1.79881083 18000000.0 1.797799175925 3 16 156 18100000.0 1.79678750 18200000.0 1.79577583 18300000.0 1.793587005925 3 16 157 18400000.0 1.79022100 18500000.0 1.78685500 18600000.0 1.783489005925 3 16 158 18700000.0 1.78012300 18800000.0 1.77536333 18900000.0 1.769210005925 3 16 159 19000000.0 1.76305667 19100000.0 1.75515667 19200000.0 1.745510005925 3 16 160 19300000.0 1.73586333 19400000.0 1.72389250 19500000.0 1.709597505925 3 16 161 19600000.0 1.69321500 19700000.0 1.67284000 19800000.0 1.648080005925 3 16 162 19900000.0 1.62316333 20000000.0 0.0 5925 3 16 163 5925 3 0 164 5925 0 0 165 59141.0000 139.697000 0 0 0 1592533 16 166 0.000000+0 0.000000+0 0 16 0 2592533 16 167 0.000000+0 0.000000+0 1 5 36 8592533 16 168 1.000000-5 2.000000+7 2.400000+7 2.800000+7 3.400000+7 4.200000+7592533 16 169 5.000000+7 6.000000+7 0.000000+0 0.000000+0 0.000000+0 0.000000+0592533 16 170 0.000000+0 0.000000+0 0.000000+0 8.183120-3 9.962810-3 9.025800-3592533 16 171 7.793330-3 7.549680-3 5.755920-3 1.929460-2 2.034470-2 1.814590-2592533 16 172 1.763460-2 1.479040-2 2.233900-2 2.019000-2 1.969930-2 1.692630-2592533 16 173 1.842220-2 1.804790-2 1.570340-2 1.776480-2 1.554870-2 1.390610-2592533 16 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2.023420-3 1.905210-3592533 16 200 1.808580-3 1.734270-3 1.685040-3 1.667360-3 1.695630-3 2.469300-3592533 16 201 2.400280-3 2.330770-3 2.251710-3 2.160910-3 2.055290-3 1.930710-3592533 16 202 1.782030-3 1.604310-3 1.399900-3 2.450900-3 2.455830-3 2.435060-3592533 16 203 2.378170-3 2.280110-3 2.133270-3 1.926860-3 1.647670-3 1.288780-3592533 16 204 2.543100-3 2.568940-3 2.550460-3 2.474410-3 2.331110-3 2.106380-3592533 16 205 1.781790-3 1.343610-3 2.656650-3 2.673470-3 2.633140-3 2.518610-3592533 16 206 2.314590-3 2.000500-3 1.558140-3 2.749450-3 2.752370-3 2.692880-3592533 16 207 2.550410-3 2.305410-3 1.937640-3 2.834100-3 2.852250-3 2.816520-3592533 16 208 2.705480-3 2.499580-3 3.001600-3 3.118840-3 3.217400-3 3.275390-3592533 16 209 3.472370-3 3.866030-3 4.312850-3 4.687830-3 5.673930-3 7.407790-3592533 16 210 592533 0 211 5925 0 0 1 0 0 0 2 -1 0 0