IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 82204.0000 202.220000 0 0 34 108225 1451 1 0.0 0.0 0 0 0 68225 1451 2 1.00000000 60000000.0 0 0 10 20028225 1451 3 300.000000 0.0 1 0 137 58225 1451 4 82-Pb-204 FEI EVAL-Oct01 K.I.Zolotarev 8225 1451 5 DIST-Feb2004 8225 1451 6 ----IRDF-2002 MATERIAL 8225 8225 1451 7 -----INCIDENT NEUTRON DATA 8225 1451 8 ------ENDF-6 FORMAT 8225 1451 9 ******************************************************************8225 1451 10 IAEA, June 2012 (A. Trkov) 8225 1451 11 Original Zolotarev evaluation was edited manually to transform 8225 1451 12 the MF3/MT57 representation into MF=10/MT=4/LFS=1 to conform to 8225 1451 13 ENDF-6 format rules. 8225 1451 14 The cross sections were extended from 20 MeV to 60 MeV, based on8225 1451 15 the TENDL-2011 library, but covariances were not because they are 8225 1451 16 not present in the library for this reaction. 8225 1451 17 ******************************************************************8225 1451 18 ***************************************************************** 8225 1451 19 82-Pb-204 FEI EVAL-Oct01 K.I.Zolotarev 8225 1451 20 DIST-Oct01 20011014 8225 1451 21 ----BROND-2 MATERIAL 8225 8225 1451 22 ------Russian Reactor Dosimetry File RRDF-2002 8225 1451 23 ***************************************************************** 8225 1451 24 ----- MF=3 MT=71 ----- 8225 1451 25 For the IRDF-2002 file this reaction was converted at IAEA/NDS 8225 1451 26 The reaction MF/MT=3/71 was converted to MF/MT=10/ 4 8225 1451 27 The corresponding co-variance files were also converted 8225 1451 28 The reaction MF/MT=33/71 was converted to MF/MT=40/ 4 8225 1451 29 ***************************************************************** 8225 1451 30 Author of evaluation: K.I.Zolotarev 8225 1451 31 ***************************************************************** 8225 1451 32 8225 1451 33 ----- MF=3 MT=71 ----- 8225 1451 34 8225 1451 35 In the section MT= 71 are given evaluated cross section data 8225 1451 36 of neutron inelastic excitation of the 67.2-min isomeric state in 8225 1451 37 in the lead-204 in the energy range from threshold to 20 MeV. 8225 1451 38 The isomeric state is the 21-excited level in Pb-204. This level 8225 1451 39 has energy 2185.79 keV with spin and parity 9- [1]. 8225 1451 40 Data base for the evaluation Pb-204(n,n')Pb-204m excitation 8225 1451 41 function was formed from microscopic experimental data [2-9] and 8225 1451 42 data received from theoretical model calculations. Experimental 8225 1451 43 data [3-9] were corrected to the new standards. Data of Decowski 8225 1451 44 et al. [6] were renormalized also to the result of precise measu- 8225 1451 45 rements of Ryves et al. at 14.3 MeV [8]. Uncertainty for cross 8225 1451 46 section value measured by Bornemisza-Pauspertl et al. at 2.80 MeV 8225 1451 47 [2] was evaluated as +-35 %. Theoretical model calculations was 8225 1451 48 done by means of GNASH code [10]. New modified version of GNASH 8225 1451 49 was used for calculations [11]. 8225 1451 50 The evaluation Pb-204(n,n')Pb-204m excitation function from 8225 1451 51 threshold to 20 MeV has been carried out within the framework of 8225 1451 52 generalized least squares method , rational function was used as 8225 1451 53 model function [12]. Procedure of calculation recommended cross 8225 1451 54 section data was performed by means of PADE-2 code [13]. 8225 1451 55 Integral experimental data for U-235 neutron fission spectrum 8225 1451 56 [14,15] and Cf-252 spontaneous fission neutron spectrum [16,17] 8225 1451 57 was used for testing evaluated Pb-204(n,n')Pb-204m excitation fun-8225 1451 58 ction. Data for U-235 thermal fission neutron spectrum and Cf-252 8225 1451 59 spontaneous fission neutron spectrum were taken from ref.[18] and 8225 1451 60 [19], respectively. The results of testing are given in the 8225 1451 61 table 1. 8225 1451 62 Table 1. 8225 1451 63 --------------------------------------------------------------- 8225 1451 64 TYPE OF SPECTRUM I ,MB (calc.) I , MB (measured) 8225 1451 65 ----------------------I-----------------I---------------------- 8225 1451 66 I I 8225 1451 67 U-235 neutron fission I 17.770 I 18.900 +- 2.000 [14] 8225 1451 68 I I 19.010 +- 1.536 [15] 8225 1451 69 I I 8225 1451 70 ----------------------I-----------------I---------------------- 8225 1451 71 I I 8225 1451 72 CF-252 spont. fission I 20.373 I 20.900 +- 1.202 [16] 8225 1451 73 I I 20.850 +- 0.920 [17] 8225 1451 74 --------------------------------------------------------------- 8225 1451 75 8225 1451 76 ----- MF=33 MT=71 ----- 8225 1451 77 Uncertainties in the evaluated excitation function for the 8225 1451 78 reaction Pb-204(n,n')Pb-204m are given in the form of relative 8225 1451 79 covariance matrix for the 32-neutron energy groups (LB=5). Cova- 8225 1451 80 riance matrix of uncertainties was calculated simultaneously with 8225 1451 81 recommended cross section data by means of PADE-2 code. 8225 1451 82 Eigenvalues of the 6-th digits relative covariance matrix 8225 1451 83 given in the 33-file are the following: 8225 1451 84 2.56972E-09 3.22598E-09 3.49414E-09 4.00985E-09 8225 1451 85 4.91484E-09 5.78671E-09 6.70005E-09 8.71427E-09 8225 1451 86 1.03160E-08 1.33154E-08 1.55381E-08 2.07583E-08 8225 1451 87 2.40281E-08 3.05913E-08 4.05801E-08 4.76532E-08 8225 1451 88 5.93691E-08 9.33863E-08 1.58183E-07 2.72581E-06 8225 1451 89 1.76176E-04 7.87730E-04 1.22783E-03 2.11803E-03 8225 1451 90 3.22408E-03 4.16999E-03 4.89344E-03 1.08231E-02 8225 1451 91 2.01870E-02 3.34051E-02 7.41942E-02 8225 1451 92 8225 1451 93 References : 8225 1451 94 1. R.B.Firestone Table of Isotopes, Eighth edition, Vol. 1, 8225 1451 95 John Wiley & Sons, Inc., New York, 1995 8225 1451 96 2. P.Bornemisza-Pauspertl, J.Karolyi, G.Peto Atomki Kozl., v.10, 8225 1451 97 no.2, p.112, July 1968 8225 1451 98 3. J.Csikai, G.Peto Acta Phys. Hung., v.23, p.87, May 1967 8225 1451 99 4. A.K.Hankla, R.W.Fink, J.H.Hamilton Nucl. Phys., v.A180, 8225 1451 100 p.157, January 1972 8225 1451 101 5. G.N.Maslov, F.Nasyrov, N.F.Pashkin Yadernye Konstanty, v.9, 8225 1451 102 p.50, Obninsk, 1972 8225 1451 103 6. P.Decowski et al. Nucl. Phys., v.A204, p.121, April 1973 8225 1451 104 7. D.L.Smith, J.W.Meadows Report ANL-NDM-37, December 1977 8225 1451 105 8. T.B.Ryves, P.Kolkowski, A.C.Hooley Annals Nucl. Energy, 8225 1451 106 v.17, p.107, 1990 8225 1451 107 9. I.Kimura, K.Kobayashi Nucl. Sci. Eng., v.106, p.332, 1990 8225 1451 108 10. P.G.Young, E.D.Arthur A Preequilibrium Statistical Nuclear 8225 1451 109 Model Code for Calculation of Cross Section and Emission 8225 1451 110 Spectra. Report LA-6947, Los Alamos, 1977 8225 1451 111 11. E.L.Trykov, G.Ya.Tertychnyi Private communication, IPPE, 8225 1451 112 Obninsk, May 1999 8225 1451 113 12. S.Badikov,N.Rabotnov,K.Zolotarev Proc. of NEANSC Specialist's 8225 1451 114 Meeting on Evaluation and Processing of Covariance Data, Oak 8225 1451 115 Ridge , USA, 7-9 September 1992, OECD, Paris, 1993, p.105 8225 1451 116 13. S.A.Badikov et al. Preprint FEI-1686, Obninsk, 1985 8225 1451 117 14. I.Kimura, K.Kobayashi, T.Shibata Nucl. Sci. Technol., v.8, 8225 1451 118 p.59, February 1971 8225 1451 119 15. A.K.Brodskaja et al. Jadernyje Konstanty, no.23, v.4, 8225 1451 120 October 1976 8225 1451 121 16. J.Csikai, Z.Dezso Proc. Educational Seminar on the use of 8225 1451 122 Cf-252, Karlsruhe, 14-18 April 1975, p.29 8225 1451 123 17. K.Kobayashi et al. Report KURRI-AR-17, p.15, 1984 ; 8225 1451 124 K.Kobayashi et al. Progress Report NEANDC(J)-106/U, p.41, 8225 1451 125 September 1984 8225 1451 126 18. L.W.Weston et al. Evaluated Neutron Data File for U-235, 8225 1451 127 ENDF/B-VI Library, MAT=9228, MF=5, MT=18, eval. April 1989 8225 1451 128 19. W.Mannhart Report IAEA-TECDOC-410, IAEA, Vienna, 1987, p158 8225 1451 129 ***************************************************************** 8225 1451 130 File 2 added to the pointwise file containing only the effective 8225 1451 131 scattering radius with no resonance parameters given. 8225 1451 132 Taken from JENDL-3.2 8225 1451 133 8225 1451 134 ***************************************************************** 8225 1451 135 ***************** Program LINEAR (VERSION 2012-1) ***************8225 1451 136 For All Data Greater than 1.0000D-10 barns in Absolute Value 8225 1451 137 Data Linearized to Within an Accuracy of .100000000 per-cent 8225 1451 138 ***************** Program GROUPIE (VERSION 2012-1) **************8225 1451 139 Unshielded Group Averages Using 640 Groups 8225 1451 140 Weighting Spectrum: Flat (Constant) Spectrum 8225 1451 141 1 451 131 18225 1451 142 2 151 4 18225 1451 143 8 4 2 18225 1451 144 10 4 45 18225 1451 145 40 4 98 18225 1451 146 8225 1 0 147 8225 0 0 148 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