IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 83209.0000 207.185000 0 0 41 18325 1451 1 0.0 0.0 0 0 0 68325 1451 2 1.00000000 60000000.0 0 0 10 28325 1451 3 300.000000 0.0 1 0 89 48325 1451 4 83-Bi-209 FEI EVAL-Dec09 K.Zolotarev 8325 1451 5 DIST-Feb10 8325 1451 6 ----BROND-2 MATERIAL 8325 8325 1451 7 -----INCIDENT NEUTRON DATA 8325 1451 8 ------ENDF-6 FORMAT 8325 1451 9 ******************************************************************8325 1451 10 IAEA, July 2011 (A. Trkov) 8325 1451 11 The new Zolotarev evaluation was extended from 45 to 60 MeV 8325 1451 12 using the TENDL-2010 library, renormalised for continuity. 8325 1451 13 ******************************************************************8325 1451 14 ***************************************************************** 8325 1451 15 ------Russian Reactor Dosimetry File 07050-13 c=0.93 8325 1451 16 ***************************************************************** 8325 1451 17 Author of evaluation: K.I.Zolotarev 8325 1451 18 ***************************************************************** 8325 1451 19 MF=3 8325 1451 20 MT= 17 - (n,3n) cross section 8325 1451 21 ----------------------------- 8325 1451 22 Microscopic experimental data [1-6] were analyzed in the 8325 1451 23 process of preparation of input data base for the evaluation of 8325 1451 24 cross sections and their uncertainty for the Bi-209(n,3n)Bi-207 8325 1451 25 reaction. During this procedure experimental data of works [2], 8325 1451 26 [4], [5] and [6] were corrected to the new standards. 8325 1451 27 Cross sections that had been determined in Refs. [2], [6] were 8325 1451 28 rejected due to their significant overestimation the (n,3n) exci- 8325 1451 29 tation function near threshold. Experimental data from Ref. [4] 8325 1451 30 at 21.8 and 27.6 MeV were not taken into account in the evalua- 8325 1451 31 tion due to significant contradiction with experimental data from 8325 1451 32 Ref. [1] and data from GNASH calculation. 8325 1451 33 Excitation function for the Bi-209(n,3n)Bi-207 reaction in the 8325 1451 34 energy region from threshold to 45 MeV was evaluated by means of 8325 1451 35 statistical analysis of experimental cross section data [1], [3], 8325 1451 36 [4], [5] and data obtained from theoretical model calculation car-8325 1451 37 ried out by means of modified GNASH code [7]. 8325 1451 38 Statistical analysis of input cross section data was carried 8325 1451 39 out by means of PADE-2 code [8]. Rational function was used as 8325 1451 40 the model function [9]. 8325 1451 41 8325 1451 42 MF=33 8325 1451 43 MT= 17 - (n,3n) cross section cov. matrix 8325 1451 44 ----------------------------------------- 8325 1451 45 Uncertainties in the evaluated excitation function for the 8325 1451 46 reaction Bi-209(n,3n)Bi-207 are given in the form of relative 8325 1451 47 covariance matrix for the 42-neutron energy groups (LB=5). Covari-8325 1451 48 ance matrix of uncertainties was calculated simultaneously with 8325 1451 49 recommended cross section data by means of PADE-2 code [7]. 8325 1451 50 Eigenvalues of the 6-th digits relative covariance matrix 8325 1451 51 given in the 33-file are the following: 8325 1451 52 8325 1451 53 4.30642E-06 4.35518E-06 4.43850E-06 4.54985E-06 8325 1451 54 4.70282E-06 4.88332E-06 5.13505E-06 5.48985E-06 8325 1451 55 5.90356E-06 6.38084E-06 7.14243E-06 8.28912E-06 8325 1451 56 9.39733E-06 1.12639E-05 1.41149E-05 1.67921E-05 8325 1451 57 2.18950E-05 2.75176E-05 3.27436E-05 4.29064E-05 8325 1451 58 5.38157E-05 6.08243E-05 7.12168E-05 8.56898E-05 8325 1451 59 1.01859E-04 1.19537E-04 1.38719E-04 1.57775E-04 8325 1451 60 1.69009E-04 1.89220E-04 5.98933E-04 1.36933E-03 8325 1451 61 2.46051E-03 2.81904E-03 3.56622E-03 5.00042E-03 8325 1451 62 5.45379E-03 6.71757E-03 1.48123E-02 2.25297E-02 8325 1451 63 2.80584E-01 3.74512E-01 8325 1451 64 8325 1451 65 References: 8325 1451 66 1. L.R.Veeser, E.D.Arthur, P.G.Young, Phys. Rev., v. C16, p.1792,8325 1451 67 November 1977 8325 1451 68 2. P.Bornemisza-Pauspertl, I.Toeroek, I.Uray, Radiochemical and 8325 1451 69 Radioanalytical letters, v. 32, p. 277, February 1978 8325 1451 70 3. G.A.Prokopets, Nucl. Phys. (Sov.), v. 32, issue 1, p. 37, 8325 1451 71 July 1980 8325 1451 72 4. E.Kim, T.Nakamura, A.Konno, Y.Uwamino, N.Nakanishi, M.Imamura,8325 1451 73 N.Nakao, S.Shibata, S.Tanaka, Nucl. Sci. Eng., v. 129, p. 209,8325 1451 74 1998 8325 1451 75 5. A.A.Filatenkov, S.V.Chuvaev, Preprint RI-252, M., Atominform, 8325 1451 76 May 1999 8325 1451 77 6. Gongping Li, Zhongsheng Pu, Xiangzhong Kong, Feng Zhang, 8325 1451 78 Xuebin Zhu, Appl. Rad. Isot., v. 56, p. 731, 2002 8325 1451 79 7. G.Y.Tertychnyj, E.L.Trykov, Modified version of GNASH code. 8325 1451 80 Private communication, IPPE, Obninsk, May 1999 8325 1451 81 8. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 8325 1451 82 9. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 8325 1451 83 st's Meeting on Evaluation and Processing of Covariance Data, 8325 1451 84 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 8325 1451 85 ***************************************************************** 8325 1451 86 8325 1451 87 ***************** Program LINEAR (VERSION 2012-1) ***************8325 1451 88 For All Data Greater than 1.0000D-10 barns in Absolute Value 8325 1451 89 Data Linearized to Within an Accuracy of .100000000 per-cent 8325 1451 90 ***************** Program GROUPIE (VERSION 2012-1) **************8325 1451 91 Unshielded Group Averages Using 640 Groups 8325 1451 92 Weighting Spectrum: Flat (Constant) Spectrum 8325 1451 93 1 451 86 18325 1451 94 2 151 4 18325 1451 95 3 17 59 18325 1451 96 33 17 168 18325 1451 97 8325 1 0 98 8325 0 0 99 83209.0000 207.185000 0 0 1 08325 2151 100 8.320900+4 1.000000+0 0 0 1 08325 2151 101 1.000000-5 5.000000+4 0 0 0 08325 2151 102 0.000000+0 9.650000-1 0 0 0 08325 2151 103 8325 2 0 104 8325 0 0 105 83209.0100 207.185000 0 0 0 08325 3 17 106 -14346700.0-14346700.0 0 0 1 578325 3 17 107 57 1 8325 3 17 108 14400000.0 3.37320E-5 14500000.0 1.27911E-4 14600000.0 3.07448E-48325 3 17 109 14700000.0 7.45056E-4 14800000.0 .001620770 14900000.0 .0030955208325 3 17 110 15000000.0 .005298380 15100000.0 .008337920 15200000.0 .0123088008325 3 17 111 15300000.0 .017295600 15400000.0 .023375050 15500000.0 .0306173008325 3 17 112 15600000.0 .039086600 15700000.0 .048841400 15800000.0 .0599341508325 3 17 113 15900000.0 .072410950 16000000.0 .086311100 16100000.0 .1016667508325 3 17 114 16200000.0 .118501500 16300000.0 .136831000 16400000.0 .1566615008325 3 17 115 16500000.0 .177989000 16600000.0 .200799500 16700000.0 .2250690008325 3 17 116 16800000.0 .250762000 16900000.0 .277832000 17000000.0 .3062225008325 3 17 117 17100000.0 .335866000 17200000.0 .366685500 17300000.0 .3985935008325 3 17 118 17400000.0 .431495500 17500000.0 .465289500 17600000.0 .4998660008325 3 17 119 17700000.0 .535111500 17800000.0 .570909500 17900000.0 .6071400008325 3 17 120 18000000.0 .643682500 18100000.0 .680418000 18200000.0 .7172290008325 3 17 121 18300000.0 .754002000 18400000.0 .790627000 18500000.0 .8270000008325 3 17 122 18600000.0 .863024000 18700000.0 .898608950 18800000.0 .9336729508325 3 17 123 18900000.0 .968141500 19000000.0 1.00194900 19100000.0 1.035040008325 3 17 124 19200000.0 1.06736500 19300000.0 1.09888500 19400000.0 1.129575008325 3 17 125 19500000.0 1.15940500 19600000.0 1.18835000 19700000.0 1.216415008325 3 17 126 19800000.0 1.24359500 19900000.0 1.26557667 20000000.0 0.0 8325 3 17 127 8325 3 0 128 8325 0 0 129 83209.0000 207.185000 0 0 0 1832533 17 130 0.000000+0 0.000000+0 0 17 0 1832533 17 131 0.000000+0 0.000000+0 1 5 990 44832533 17 132 1.000000-5 1.441590+7 1.550000+7 1.600000+7 1.650000+7 1.700000+7832533 17 133 1.750000+7 1.800000+7 1.850000+7 1.900000+7 1.950000+7 2.000000+7832533 17 134 2.050000+7 2.100000+7 2.150000+7 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