IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 30067.0000 66.3522000 0 0 41 13034 1451 1 0.0 0.0 0 0 0 63034 1451 2 1.00000000 60000000.0 0 0 10 23034 1451 3 300.000000 0.0 1 0 155 43034 1451 4 30-Zn- 67 FEI EVAL-Jun11 K.I.Zolotarev 3034 1451 5 DIST-Aug11 3034 1451 6 ----BROND-2 MATERIAL 3034 3034 1451 7 -----INCIDENT NEUTRON DATA 3034 1451 8 ------ENDF-6 FORMAT 3034 1451 9 ******************************************************************3034 1451 10 IAEA, November 2011 (A. Trkov) 3034 1451 11 Extended cross sections and covariances from 20 to 60 MeV 3034 1451 12 by TENDL-2010, renormalised for continuity. 3034 1451 13 3034 1451 14 The Zn-67(n,p) reaction is exothermic, therefore the cross 3034 1451 15 section has only a pseudo-threshold due to the Coulomb barrier, 3034 1451 16 but is non-zero below this threshold. Following the example of 3034 1451 17 the EAF-2010 library, the capture cross section from JENDL-4 was 3034 1451 18 re-scaled to give a thermal value of 0.00123 barns and adjusted 3034 1451 19 above 600 keV to join smoothly with the (n,p) evaluation by 3034 1451 20 Zolotarev. A fully correlated uncertainty of 25 was assigned 3034 1451 21 arbitrarily to the cross sections below the pseudo-threshold. 3034 1451 22 ******************************************************************3034 1451 23 ***************************************************************** 3034 1451 24 ------Russian Reactor Dosimetry File 3034 1451 25 ***************************************************************** 3034 1451 26 Author of evaluation: K.I.Zolotarev 3034 1451 27 ***************************************************************** 3034 1451 28 MF=3 3034 1451 29 MT=103 - (n,p) cross section 3034 1451 30 ----------------------------- 3034 1451 31 Microscopic experimental data [1-18] were analyzed in the 3034 1451 32 process of preparation of input data base for the evaluation of 3034 1451 33 cross sections and their uncertainty for the Zn-67(n,p)Cu-67 reac-3034 1451 34 tion. During this procedure experimental data of works [2], [4-5],3034 1451 35 [7-8], [10-18], were corrected to the new standards. 3034 1451 36 Experimental data given in the works [3], [5-8], [10], [11], 3034 1451 37 and [13] were corrected for contribution from the Cu-68(n,x)Cu-67 3034 1451 38 reaction. Data for the Zn-68(n,np+pn+d)Cu-67 excitation function 3034 1451 39 were taken from new evaluation of K.I.Zolotarev [19]. The isoto- 3034 1451 40 pic abundances of Zn-67 and Zn-68 in the natural Zn were taken as 3034 1451 41 equal to (4.10+-0.13) % and (18.75+-0.51) %, respectively [20]. 3034 1451 42 After applied corrections experimental data of Viennot et al. 3034 1451 43 [11] and Kielan et al. [14] were renormalized to the integrals of 3034 1451 44 cross section calculated from the representative measurements by 3034 1451 45 Konno et al. [12] in the overlapping energy intervals. Experimen- 3034 1451 46 tal data [11] and [14] were multiplied to the factors Fc= 0.48676 3034 1451 47 and Fc= 0.787291, respectively. 3034 1451 48 Cross sections measured by Bhike et al. [18] for the incident 3034 1451 49 neutron energies 1.60 - 3.70 MeV were renormalized to preliminary 3034 1451 50 evaluated value of (2.27+-0.09) mb at 3.70 MeV. 3034 1451 51 Cross sections that had been determined in Refs. [2], [7] were 3034 1451 52 rejected due to inconsistency with the main bulk of experimental 3034 1451 53 data. For a these reason were rejected also experimental data of 3034 1451 54 Ghorai et al. [13] obtained at 14.2, 15.2, 17.2 and 18.20 MeV. 3034 1451 55 Data obtained by Mirzadeh et al. for 0.0253 eV neutrons [9] are3034 1451 56 needed in confirmation via new accurate measurements. 3034 1451 57 Excitation function for the Zn-67(n,p)Cu-67 reaction in the 3034 1451 58 energy region from 1.0 to 50 MeV was evaluated by means of statis-3034 1451 59 tical analysis of experimental cross section data [1], [3-5], [10-3034 1451 60 12], [14-18] and data obtained from theoretical model calculation 3034 1451 61 carried out by means of GNASH code [21]. 3034 1451 62 Statistical analysis of input cross section data was carried 3034 1451 63 out by means of PADE-2 code [22]. Rational function was used as 3034 1451 64 the model function [23]. 3034 1451 65 The evaluated Zn-67(n,p)Cu-67 reaction excitation function 3034 1451 66 averaged over the U-235 thermal fission neutron spectrum [24] and 3034 1451 67 Cf-252 spontaneous fission neutron spectrum [25] gives the follo- 3034 1451 68 wing integral cross-section values: 3034 1451 69 ----------------------+------------------+---------------------- 3034 1451 70 Type of spectrum | , mb (calc.) | , mb (measured) 3034 1451 71 ----------------------+------------------+---------------------- 3034 1451 72 U-235 neutron fission | 0.97579 | 0.966 +- 0.195 3034 1451 73 ----------------------+------------------+---------------------- 3034 1451 74 CF-252 spont. fission | 1.10830 | 3034 1451 75 ----------------------+------------------+---------------------- 3034 1451 76 3034 1451 77 Experimental integral cross-section of (0.966+-0.195) mb for 3034 1451 78 U-235 thermal fission neutron spectrum was determined as average 3034 1451 79 weighted value from measurements carried out in facilities with 3034 1451 80 90%-enriched U-235 fission plate converter [26-27]. Experiments 3034 1451 81 which had been carried out in Cf-252 spontaneous fission neutron 3034 1451 82 spectrum are absent for today. 3034 1451 83 3034 1451 84 MF=33 3034 1451 85 MT=103 - (n,p) cross section cov. matrix 3034 1451 86 ----------------------------------------- 3034 1451 87 Uncertainties in the evaluated excitation function for the 3034 1451 88 Zn-67(n,p)Cu-67 reaction are given in the form of relative cova- 3034 1451 89 riance matrix for the 49-neutron energy groups (LB=5). Covariance 3034 1451 90 matrix of uncertainties was calculated simultaneously with recom- 3034 1451 91 mended cross section data by means of PADE-2 code [22]. 3034 1451 92 Eigenvalues of the 6-digits relative covariance matrix given 3034 1451 93 in the 33-file are the following: 3034 1451 94 3034 1451 95 1.80945E-06 1.83554E-06 1.87233E-06 1.91902E-06 3034 1451 96 1.99404E-06 2.06652E-06 2.16769E-06 2.29597E-06 3034 1451 97 2.40815E-06 2.60848E-06 2.81374E-06 3.04735E-06 3034 1451 98 3.41372E-06 3.77827E-06 4.17896E-06 4.79472E-06 3034 1451 99 5.32611E-06 6.00270E-06 6.97288E-06 7.63897E-06 3034 1451 100 8.97351E-06 9.96698E-06 1.14774E-05 1.30372E-05 3034 1451 101 1.47387E-05 1.68836E-05 1.90351E-05 2.15728E-05 3034 1451 102 2.47607E-05 2.71812E-05 3.22520E-05 3.41220E-05 3034 1451 103 4.03682E-05 4.46659E-05 4.90729E-05 5.81907E-05 3034 1451 104 6.16867E-05 8.56788E-05 1.23153E-04 1.83396E-04 3034 1451 105 2.86058E-04 4.76024E-04 8.73177E-04 1.88558E-03 3034 1451 106 5.53102E-03 3.09634E-02 4.30841E-02 5.67912E-02 3034 1451 107 3.59739E-01 3034 1451 108 3034 1451 109 References: 3034 1451 110 1. D.L.Allan, Nucl. Phys. 24 (1961) 274 3034 1451 111 2. J.J.Van Loef, Nucl. Phys. 24 (1961) 340 3034 1451 112 3. V.N.Levkovskiy, Soviet Physiks-JETP, v.18, p.213, 1966 3034 1451 113 4. G.P.Vinitskaya et al., Yadernaja Fizika (Sov.), v.5, 3034 1451 114 pp.1175-1178, June 1967 3034 1451 115 5. N.Ranakumar, E.Kondaiah, R.W.Fink, Bull. Am. Phys. Soc., v.13,3034 1451 116 p.602 (DE7), April 1968 3034 1451 117 6. M.Valkonen et al., Report JU-RR-1/1976, March 1976 3034 1451 118 7. J.L.Casanova, M.L.Sanchez, Anales de Fisica y Quimica, v.72, 3034 1451 119 issue 3, p.186, 1976 (in Spain) 3034 1451 120 8. M.Viennot at al., Progress Report MOH-5, p.10, 1982 3034 1451 121 9. S.Mirzadeh et al., Applied Radiation and Isotop. 37 (1986) 29 3034 1451 122 10. A.Ercan et al., Proc. of an Intern. Conf. on Nuclear Data for 3034 1451 123 Science and Technology, 13-17 May 1991, Julich, FRG, Springer-3034 1451 124 Verlag, 1992, pp.376-377 3034 1451 125 11. M.Viennot et al., Nucl. Sci. Eng 108 (1991) 289-301 3034 1451 126 12. C.Konno, Y.Ikeda, K.Oishi, K.Kawade, H.Yamamoto, H.Maekawa, 3034 1451 127 Report JAERI-1329, October 1993 3034 1451 128 13. S.K.Ghorai et al., Annals of Nuclear Energy 22 (1995) 11 3034 1451 129 14. D.Kielan, A.Marcinkowski, Zeitschrift fuer Physik A, v.352, 3034 1451 130 pp.137-143, 1995 3034 1451 131 15. C.Nesaraja et al., Radiochimica Acta 86 (1999) 1 3034 1451 132 16. T.Shimizu et al., Annals of Nuclear Energy 31 (2004) 975 3034 1451 133 17. M.Furuta et al., Annals of Nuclear Energy 35 (2008) 1652 3034 1451 134 18. M.Bhike et al., Nucl. Sci. Eng. 163 (2009) 175 3034 1451 135 19. K.I.Zolotarev, Evaluated excitation function for the reaction 3034 1451 136 Zn68(n,x)Cu67 (var.03040-10), IPPE, Obninsk, July 2011 3034 1451 137 20. J.K.Tuli, Nuclear Vallet Cards, BNL, April 2005 3034 1451 138 21. G.Y.Tertychnyj, E.L.Trykov, Modified version of GNASH code. 3034 1451 139 Private communication, IPPE, Obninsk, May 1999 3034 1451 140 22. S.A.Badikov et al., Preprint FEI-1686, Obninsk, 1985 3034 1451 141 23. S.Badikov, N.Rabotnov, K.Zolotarev, Proc. of NEANSC Speciali- 3034 1451 142 st's Meeting on Evaluation and Processing of Covariance Data, 3034 1451 143 Oak Ridge, USA, 7-9 September 1992, OECD, Paris, 1993, p. 105 3034 1451 144 24. L.W.Weston e.a., Evaluated Neutron Data for U-235, ENDF/B-VI 3034 1451 145 Library, MAT=9228, MF=5, MT=18, eval. April 1989 3034 1451 146 25. W.Mannhart, Report INDC(NDS)-220/L, p.158, IAEA, Vienna, 1989 3034 1451 147 26. J.W.Boldeman, J. of Nuclear Energy AB, v.18, p.417, 1964 3034 1451 148 27. O.Horibe et al.,Proc. of Conf.: 50 Years with Nuclear Fission,3034 1451 149 Washington D.C., 25-28 April 1989, American Nuclear Society 3034 1451 150 Inc., 1989, v.2, p.927 3034 1451 151 ***************************************************************** 3034 1451 152 3034 1451 153 ***************** Program LINEAR (VERSION 2012-1) ***************3034 1451 154 For All Data Greater than 1.0000D-10 barns in Absolute Value 3034 1451 155 Data Linearized to Within an Accuracy of .100000000 per-cent 3034 1451 156 ***************** Program GROUPIE (VERSION 2012-1) **************3034 1451 157 Unshielded Group Averages Using 640 Groups 3034 1451 158 Weighting Spectrum: Flat (Constant) Spectrum 3034 1451 159 1 451 143 13034 1451 160 2 151 4 13034 1451 161 3 103 16429 13034 1451 162 33 103 231 13034 1451 163 3034 1 0 164 3034 0 0 165 30067.0000 66.3522000 0 0 1 03034 2151 166 3.006700+4 1.000000+0 0 0 1 03034 2151 167 1.000000-5 7.000000+4 0 0 0 03034 2151 168 2.500000+0 6.500000-1 0 0 0 03034 2151 169 3034 2 0 170 3034 0 0 171 30067.0000 66.3522100 0 0 0 03034 3103 172 220690.000 220690.000 0 0 1 6413034 3103 173 641 1 3034 3103 174 1.00000E-4 .019328655 1.05000E-4 .018880170 1.10000E-4 .0184494383034 3103 175 1.15000E-4 .018056585 1.20000E-4 .017592736 1.27500E-4 .0170870693034 3103 176 1.35000E-4 .016612634 1.42500E-4 .016187585 1.50000E-4 .0157200993034 3103 177 1.60000E-4 .015236616 1.70000E-4 .014797526 1.80000E-4 .0143874273034 3103 178 1.90000E-4 .014019118 2.00000E-4 .013666757 2.10000E-4 .0133510153034 3103 179 2.20000E-4 .013044758 2.30000E-4 .012770097 2.40000E-4 .0124399463034 3103 180 2.55000E-4 .012083098 2.70000E-4 .011798773 2.80000E-4 .0114957753034 3103 181 3.00000E-4 .011116854 3.20000E-4 .010773389 3.40000E-4 .0104642883034 3103 182 3.60000E-4 .010173564 3.80000E-4 .009912571 4.00000E-4 .0096363083034 3103 183 4.25000E-4 .009356969 4.50000E-4 .009102241 4.75000E-4 .0088629663034 3103 184 5.00000E-4 .008647227 5.25000E-4 .008440301 5.50000E-4 .0082536403034 3103 185 5.75000E-4 .008073818 6.00000E-4 .007892731 6.30000E-4 .0077061023034 3103 186 6.60000E-4 .007533143 6.90000E-4 .007371913 7.20000E-4 .0071942843034 3103 187 7.60000E-4 .007008194 8.00000E-4 .006834764 8.40000E-4 .0066742733034 3103 188 8.80000E-4 .006523452 9.20000E-4 .006384696 9.60000E-4 .0062503813034 3103 189 .001000000 .006114568 .001050000 .005967914 .001100000 .0058365183034 3103 190 .001150000 .005708265 .001200000 .005564913 .001275000 .0054016913034 3103 191 .001350000 .005255105 .001425000 .005117298 .001500000 .0049713343034 3103 192 .001600000 .004819230 .001700000 .004677861 .001800000 .0045512153034 3103 193 .001900000 .004431549 .002000000 .004323332 .002100000 .0042202743034 3103 194 .002200000 .004126906 .002300000 .004036360 .002400000 .0039349203034 3103 195 .002550000 .003819835 .002700000 .003732681 .002800000 .0036345223034 3103 196 .003000000 .003515046 .003200000 .003407802 .003400000 .0033079763034 3103 197 .003600000 .003217819 .003800000 .003134022 .004000000 .0030471653034 3103 198 .004250000 .002959596 .004500000 .002877418 .004750000 .0028037623034 3103 199 .005000000 .002733372 .005250000 .002670186 .005500000 .0026089273034 3103 200 .005750000 .002554009 .006000000 .002495188 .006300000 .0024374443034 3103 201 .006600000 .002381693 .006900000 .002331235 .007200000 .0022749763034 3103 202 .007600000 .002216454 .008000000 .002161001 .008400000 .0021108593034 3103 203 .008800000 .002062770 .009200000 .002018867 .009600000 .0019772773034 3103 204 .010000000 .001933062 .010500000 .001887997 .011000000 .0018449773034 3103 205 .011500000 .001806033 .012000000 .001759370 .012750000 .0017086793034 3103 206 .013500000 .001661924 .014250000 .001618568 .015000000 .0015727383034 3103 207 .016000001 .001523911 .017000001 .001480079 .017999999 .0014393293034 3103 208 .018999999 .001401905 .020000000 .001367454 .021000000 .0013351243034 3103 209 .022000000 .001305173 .023000000 .001277175 .024000000 .0012438163034 3103 210 .025500000 .001208551 .027000001 .001180346 .028000001 .0011498263034 3103 211 .029999999 .001111796 .032000002 .001077691 .034000002 .0010465163034 3103 212 .035999998 .001017615 .037999999 9.91542E-4 .039999999 9.63821E-43034 3103 213 .042500000 9.36171E-4 .045000002 9.10310E-4 .047499999 8.86757E-43034 3103 214 .050000001 8.64801E-4 .052499998 8.44475E-4 .055000000 8.25373E-43034 3103 215 .057500001 8.07794E-4 .059999999 7.89242E-4 .063000001 7.70926E-43034 3103 216 .066000000 7.53263E-4 .068999998 7.37401E-4 .071999997 7.19467E-43034 3103 217 .075999998 7.01067E-4 .079999998 6.83496E-4 .083999999 6.67723E-43034 3103 218 .088000000 6.52436E-4 .092000000 6.38708E-4 .096000001 6.25245E-43034 3103 219 .100000001 6.11587E-4 .104999997 5.96986E-4 .109999999 5.83695E-43034 3103 220 .115000002 5.71059E-4 .119999997 5.56484E-4 .127499998 5.40224E-43034 3103 221 .135000005 5.25587E-4 .142499998 5.11721E-4 .150000006 4.97298E-43034 3103 222 .159999996 4.81953E-4 .170000002 4.67955E-4 .180000007 4.55256E-43034 3103 223 .189999998 4.43231E-4 .200000003 4.32442E-4 .209999993 4.22051E-43034 3103 224 .219999999 4.12732E-4 .230000004 4.03672E-4 .239999995 3.93485E-43034 3103 225 .254999995 3.81929E-4 .270000011 3.73273E-4 .280000001 3.63387E-43034 3103 226 .300000012 3.51515E-4 .319999993 3.40760E-4 .340000004 3.30819E-43034 3103 227 .360000014 3.21856E-4 .379999995 3.13349E-4 .400000006 3.04759E-43034 3103 228 .425000012 2.95868E-4 .449999988 2.87711E-4 .474999994 2.80293E-43034 3103 229 .500000000 2.73265E-4 .524999976 2.66909E-4 .550000012 2.60813E-43034 3103 230 .574999988 2.55265E-4 .600000024 2.49494E-4 .629999995 2.43665E-43034 3103 231 .660000026 2.38269E-4 .689999998 2.32987E-4 .720000029 2.27500E-43034 3103 232 .759999990 2.21478E-4 .800000012 2.16080E-4 .839999974 2.10889E-43034 3103 233 .879999995 2.06228E-4 .920000017 2.01679E-4 .959999979 1.97598E-43034 3103 234 1.00000000 1.93132E-4 1.04999995 1.88624E-4 1.10000002 1.84320E-43034 3103 235 1.14999998 1.80370E-4 1.20000005 1.75740E-4 1.27499998 1.70645E-43034 3103 236 1.35000002 1.65948E-4 1.42499995 1.61680E-4 1.50000000 1.57022E-43034 3103 237 1.60000002 1.52151E-4 1.70000005 1.47768E-4 1.79999995 1.43647E-43034 3103 238 1.89999998 1.39947E-4 2.00000000 1.36425E-4 2.09999990 1.33248E-43034 3103 239 2.20000005 1.30185E-4 2.29999995 1.27429E-4 2.40000010 1.24112E-43034 3103 240 2.54999995 1.20533E-4 2.70000005 1.17722E-4 2.79999995 1.14699E-43034 3103 241 3.00000000 1.10862E-4 3.20000005 1.07418E-4 3.40000010 1.04291E-43034 3103 242 3.59999990 1.01422E-4 3.79999995 9.87517E-5 4.00000000 9.60365E-53034 3103 243 4.25000000 9.32034E-5 4.50000000 9.06377E-5 4.75000000 8.82740E-53034 3103 244 5.00000000 8.60613E-5 5.25000000 8.40519E-5 5.50000000 8.21657E-53034 3103 245 5.75000000 8.03447E-5 6.00000000 7.85668E-5 6.30000019 7.66534E-53034 3103 246 6.59999990 7.49245E-5 6.90000010 7.32789E-5 7.19999981 7.15347E-53034 3103 247 7.59999990 6.96463E-5 8.00000000 6.79130E-5 8.39999962 6.63122E-53034 3103 248 8.80000019 6.48066E-5 9.19999981 6.33905E-5 9.60000038 6.20900E-53034 3103 249 10.0000000 6.06771E-5 10.5000000 5.92691E-5 11.0000000 5.79205E-53034 3103 250 11.5000000 5.66492E-5 12.0000000 5.52230E-5 12.7500000 5.35973E-53034 3103 251 13.5000000 5.21272E-5 14.2500000 5.07716E-5 15.0000000 4.93121E-53034 3103 252 16.0000000 4.77984E-5 17.0000000 4.64120E-5 18.0000000 4.51449E-53034 3103 253 19.0000000 4.39965E-5 20.0000000 4.29070E-5 21.0000000 4.19364E-53034 3103 254 22.0000000 4.10038E-5 23.0000000 4.01294E-5 24.0000000 3.91473E-53034 3103 255 25.5000000 3.80466E-5 27.0000000 3.71945E-5 28.0000000 3.62884E-53034 3103 256 30.0000000 3.51568E-5 32.0000000 3.41523E-5 34.0000000 3.32597E-53034 3103 257 36.0000000 3.24239E-5 38.0000000 3.16784E-5 40.0000000 3.09385E-53034 3103 258 42.5000000 3.01749E-5 45.0000000 2.94989E-5 47.5000000 2.88887E-53034 3103 259 50.0000000 2.83621E-5 52.5000000 2.78510E-5 55.0000000 2.74277E-53034 3103 260 57.5000000 2.70274E-5 60.0000000 2.66520E-5 63.0000000 2.62816E-53034 3103 261 66.0000000 2.59769E-5 69.0000000 2.57028E-5 72.0000000 2.54505E-53034 3103 262 76.0000000 2.52291E-5 80.0000000 2.50720E-5 84.0000000 2.49813E-53034 3103 263 88.0000000 2.49503E-5 92.0000000 2.49975E-5 96.0000000 2.50960E-53034 3103 264 100.000000 2.52921E-5 105.000000 2.56062E-5 110.000000 2.60268E-53034 3103 265 115.000000 2.65704E-5 120.000000 2.74607E-5 127.500000 2.88747E-53034 3103 266 135.000000 3.07364E-5 142.500000 3.32324E-5 150.000000 3.73345E-53034 3103 267 160.000000 4.43962E-5 170.000000 5.62055E-5 180.000000 7.82530E-53034 3103 268 190.000000 1.27865E-4 200.000000 2.88164E-4 210.000000 .0019833253034 3103 269 220.000000 .040026112 230.000000 6.78403E-4 240.000000 1.62802E-43034 3103 270 255.000000 7.59952E-5 270.000000 5.72433E-5 280.000000 5.14303E-53034 3103 271 300.000000 1.07009E-4 320.000000 1.17671E-4 340.000000 8.55194E-53034 3103 272 360.000000 1.27360E-4 380.000000 2.21654E-4 400.000000 6.12254E-43034 3103 273 425.000000 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