IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 53127.0000 125.814000 0 0 41 15325 1451 1 0.0 0.0 0 0 0 65325 1451 2 1.00000000 60000000.0 0 0 10 25325 1451 3 300.000000 0.0 1 0 132 45325 1451 4 53-I -127 FEI EVAL-Jul07 K.I.Zolotarev 5325 1451 5 DIST-Sep07 5325 1451 6 ----BROND-2 MATERIAL 5325 5325 1451 7 -----INCIDENT NEUTRON DATA 5325 1451 8 ------ENDF-6 FORMAT 5325 1451 9 ******************************************************************5325 1451 10 IAEA, July 2011 (A. Trkov) 5325 1451 11 Extended cross sections and covariances from 20 to 60 MeV 5325 1451 12 by TENDL-2010, renormalised for continuity. 5325 1451 13 ******************************************************************5325 1451 14 *** MF2 ADDed *************************************************** 5325 1451 15 * Extension to the International Reactor Dosimetry Library * 5325 1451 16 * supported partially by the International Atomic Energy Agency * 5325 1451 17 * through IAEA research contract 13335. * 5325 1451 18 * Published as a technical report INDC(NDS)-0526 (2008). * 5325 1451 19 * Available online at * 5325 1451 20 * http://www-nds.iaea.org/reports-new/indc-reports/indc-nds/ * 5325 1451 21 * indc-nds-0526.pdf * 5325 1451 22 ***************************************************************** 5325 1451 23 ------Russian Reactor Dosimetry File RRDF-2007 BEST-06 04509-10 5325 1451 24 ***************************************************************** 5325 1451 25 Author of evaluation: K.I.Zolotarev 5325 1451 26 ***************************************************************** 5325 1451 27 MF=3 5325 1451 28 MT= 16 - (n,2n) cross section 5325 1451 29 ------------------------------------- 5325 1451 30 Microscopic experimental data [1-13] were analyzed in the 5325 1451 31 process of preparation of input data base for the evaluation of 5325 1451 32 cross sections and their uncertainty for the I-127(n,2n)I-126 5325 1451 33 reaction. During this procedure all experimental data if it was 5325 1451 34 possible were corrected to the new recommended cross section data 5325 1451 35 for monitor reactions used in the measurements and to the new re- 5325 1451 36 commended decay data from Ref. [14]. 5325 1451 37 Excitation function for the I-127(n,2n)I-126 reaction in the 5325 1451 38 energy region from threshold to 32 MeV was evaluated by means of 5325 1451 39 statistical analysis of experimental cross section data [5], [6], 5325 1451 40 [8-13] and data obtained from theoretical model calculation by 5325 1451 41 means of modified GNASH code [15]. Experimental data [5], [6], [8-5325 1451 42 13] and results of GNASH calculations agree well in a wide energy 5325 1451 43 range 9.5 - 19.6 MeV. Evaluation of the excitation function from 5325 1451 44 20 to 32 MeV, based on GNASH calculations. 5325 1451 45 Experimental cross section data [1-4] and [7] were rejected 5325 1451 46 due to systematical underestimation of the I-127(n,2n)I-126 reac- 5325 1451 47 tion cross sections in the energy range 12.3 - 18.3 MeV. 5325 1451 48 Statistical analysis of input cross section data was carried 5325 1451 49 out by means of PADE-2 code [16]. Rational function was used as 5325 1451 50 the model function [17]. 5325 1451 51 Evaluated excitation function of the I-127(n,2n)I-126 reaction 5325 1451 52 was tested by comparison with integral experimental data [18] for 5325 1451 53 U-235 thermal fission neutron spectrum and integral experimental 5325 1451 54 data [19] for Cf-252 spontaneous fission neutron spectrum. Calcu- 5325 1451 55 lated and measured average cross section values for U-235 thermal 5325 1451 56 fission neutron spectrum [20] and Cf-252 spontaneous fission neut-5325 1451 57 ron spectrum [21] are given in the Table 1. 5325 1451 58 Table 1 5325 1451 59 ----------------------+-----------------+----------------------- 5325 1451 60 Type of spectrum | ,mb (calc.) | , mb (measured) 5325 1451 61 ----------------------+-----------------+----------------------- 5325 1451 62 U-235 neutron fission | 1.1822 | 1.197 +- 0.041 [18] 5325 1451 63 ----------------------+-----------------+----------------------- 5325 1451 64 CF-252 spont. fission | 2.1068 | 2.069 +- 0.050 [19] 5325 1451 65 ----------------------+-----------------+----------------------- 5325 1451 66 5325 1451 67 MF=33 5325 1451 68 MT= 16 - (n,2n) cross section cov. matrix 5325 1451 69 ----------------------------------------- 5325 1451 70 Uncertainties in the evaluated excitation function for the 5325 1451 71 reaction I-127(n,2n)I-126 are given in the form of relative cova- 5325 1451 72 riance matrix for the 34-neutron energy groups (LB=5). Covariance 5325 1451 73 matrix of uncertainties was calculated simultaneously with 5325 1451 74 recommended cross section data by means of PADE-2 code [16]. 5325 1451 75 Eigenvalues of the 6-th digits relative covariance matrix 5325 1451 76 given in the 33-file are the following: 5325 1451 77 5325 1451 78 1.14192E-07 1.15227E-07 1.16982E-07 1.19457E-07 5325 1451 79 1.22735E-07 1.26068E-07 1.31268E-07 1.36450E-07 5325 1451 80 1.43199E-07 1.53115E-07 1.62023E-07 1.82277E-07 5325 1451 81 1.99829E-07 2.49306E-07 2.85824E-07 3.71735E-07 5325 1451 82 4.88297E-07 5.64248E-07 6.77032E-07 8.37697E-07 5325 1451 83 1.01492E-06 1.20140E-06 1.39970E-06 1.61113E-06 5325 1451 84 3.36624E-06 4.51402E-04 5.53163E-04 6.23940E-04 5325 1451 85 8.26524E-04 1.78803E-03 2.15123E-03 1.06557E-02 5325 1451 86 2.51934E-02 6.11561E-02 5325 1451 87 5325 1451 88 References: 5325 1451 89 1. E.B.Paul, R.L.Clarke, Canadian J. Phys., v. 31, p. 267, 1953 5325 1451 90 2. H.C.Martin, R.F.Taschek, Phys. Rev., v.89, p.1302, March 1953 5325 1451 91 3. M.Bormann, S.Cierjacks, R.Langkau, H.Neuert, Zeitschrift fuer 5325 1451 92 Physik, v. 166, p. 477, February 1962 5325 1451 93 4. S.M.Qaim, M.Ejaz, J. Inorg. Nucl. Chem., v. 30, p. 2577, 1968 5325 1451 94 5. R.C.Barrall, J.A.Holmes, M.Silbergeld, Report, AFWL-TR-68-134,5325 1451 95 March 1969 5325 1451 96 6. R.C.Barrall, M.Silbergeld, D.G.Gardner, Nucl. Phys. A, v.138, 5325 1451 97 p.387, December 1969 5325 1451 98 7. W.D.Lu, N.Ranakumar, R.W.Fink, Phys. Rev. C, v. 1, p. 350, 5325 1451 99 January 1970 5325 1451 100 8. E.Havlik, Acta Physica Austriaca, v.34, p.209, September 1971 5325 1451 101 9. G.N.Maslov, F.Nasyrov, N.F.Pashkin Yadernye Konstanty (YK-9),5325 1451 102 Obninsk report, p.50, 1972 5325 1451 103 10. J.Araminowicz, J.Dresler, Progress Report, INR-1464, p. 14, 5325 1451 104 May 1973 5325 1451 105 11. D.C.Santry, Proc. of an Int. Conf. on Nuclear Cross Sections 5325 1451 106 for Technology, Knoxville, Tennessee, USA, 22-26 October 1979 5325 1451 107 (DC-9). NBS Special Publication 594, September 1980. 5325 1451 108 12. R.Pepelnik, B.Anders, B.M.Bahal, Proc. of an Int. Conference 5325 1451 109 on Nuclear Data for Basic and Applied Physic, Santa Fe, New 5325 1451 110 Mexico, 13-17 May 1985, v .1, p. 211 (JA46) 5325 1451 111 13. Lu Hanlin, Wang Dahai, Xia Yijun, Cui Yumfeng, Chen Paolin, 5325 1451 112 Report, INDC(CPR)-16, IAEA, Vienna, August 1989 5325 1451 113 14. Decay Radiation Data Base, version 2/6/2007, 5325 1451 114 http://www.nds.iaea.org/nudat2/dec 5325 1451 115 15. G.Y.Tertychnyj, E.L.Trykov, Modified version of GNASH code. 5325 1451 116 Private communication, IPPE, Obninsk, May 1999 5325 1451 117 16. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 5325 1451 118 17. S.Badikov, N.Rabotnov, K.Zolotarev Proc. of NEANSC Speciali- 5325 1451 119 st's Meeting on Evaluation and Processing of Covariance Data, 5325 1451 120 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 5325 1451 121 18. L.P.Geraldo, M.S.Dias, M.F.Koskinas, Radiochimica Acta, v. 57,5325 1451 122 pp. 63-67, 1992 5325 1451 123 19. W.Mannhart Validation of Differential Cross Sections with 5325 1451 124 Integral Data , Report INDC(NDS)-435, pp.59-64, IAEA, Vienna, 5325 1451 125 September 2002 5325 1451 126 20. L.W.Weston et al., Evaluated Neutron Data for Uranium-235, 5325 1451 127 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 5325 1451 128 21. W.Mannhart Report, INDC(NDS)-220/L,p.158, IAEA, Vienna, 1989 5325 1451 129 ***************************************************************** 5325 1451 130 ***************** Program LINEAR (VERSION 2012-1) ***************5325 1451 131 For All Data Greater than 1.0000D-10 barns in Absolute Value 5325 1451 132 Data Linearized to Within an Accuracy of .100000000 per-cent 5325 1451 133 ***************** Program GROUPIE (VERSION 2012-1) **************5325 1451 134 Unshielded Group Averages Using 640 Groups 5325 1451 135 Weighting Spectrum: Flat (Constant) Spectrum 5325 1451 136 1 451 129 15325 1451 137 2 151 4 15325 1451 138 3 16 50 15325 1451 139 33 16 121 15325 1451 140 5325 1 0 141 5325 0 0 142 53127.0000 125.814000 0 0 1 05325 2151 143 5.312700+4 1.000000+0 0 0 1 05325 2151 144 1.000000-5 1.989000+1 0 0 0 05325 2151 145 2.500000+0 5.700000-1 0 0 0 05325 2151 146 5325 2 0 147 5325 0 0 148 53127.0000 125.814000 0 0 0 05325 3 16 149 -9143470.00-9143470.00 0 0 1 1095325 3 16 150 109 1 5325 3 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