RRDF-2010 777 0 0 0 3.90890+ 4 8.81421+ 1 1 0 41 13925 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 63925 1451 2 1.00000+ 0 0.00000+ 0 0 0 10 23925 1451 3 0.00000+ 0 0.00000+ 0 0 0 165 33925 1451 4 39-Y - 89 FEI EVAL-Dec09 K.Zolotarev 3925 1451 5 DIST-Feb10 3925 1451 6 ----BROND-3 MATERIAL 3925 3925 1451 7 -----INCIDENT NEUTRON DATA 3925 1451 8 ------ENDF-6 FORMAT 3925 1451 9 ***************************************************************** 3925 1451 10 ------Russian Reactor Dosimetry File 36159-14 c=0.98 3925 1451 11 ***************************************************************** 3925 1451 12 Author of evaluation: K.I.Zolotarev 3925 1451 13 ***************************************************************** 3925 1451 14 MF=3 3925 1451 15 MT= 16 - (n,2n) cross section 3925 1451 16 ----------------------------- 3925 1451 17 Microscopic experimental data [1-38] were analyzed in the 3925 1451 18 process of preparation of input data base for the evaluation of 3925 1451 19 cross sections and their uncertainty for the Y-89(n,2n)Y-88 reac- 3925 1451 20 tion. During this procedure experimental data of works [1],[3-12],3925 1451 21 [14], [16-19], [21-27], [29-31], [33], [35], [37] and [38] were 3925 1451 22 corrected to the new standards. 3925 1451 23 Speciaal adjustments were also allied to some of the experimen-3925 1451 24 Cross sections measured by Wagner et al. [20], Huang Jianzhou 3925 1451 25 et al. [21], Konno et al. [22], Filatenkov and Chuvaev [25] were 3925 1451 26 used as a reference data in the energy range 13.5 - 15.0 MeV for 3925 1451 27 correction experimental data from works [1], [13] and [24]. 3925 1451 28 Data of Klopries et al. [24] obtained in measurements with 3925 1451 29 D(d,n)He3 source were corrected for a value of energies in the in-3925 1451 30 cident neutrons. The reason for revision of neutron energies was a3925 1451 31 fact that neutron energy at first point is lying below the thresh-3925 1451 32 old of the Y-89(n,2n)Y-88 reaction, whish is equal to 11.6041 MeV.3925 1451 33 Neutron energies of 11.38, 11.86, 12.31 and 13.28 MeV as reported 3925 1451 34 by Klopries et al. were shifted by +0.23 MeV at first two points 3925 1451 35 and by -0.20 MeV at the last point. Neutron energy in the third 3925 1451 36 point is not corrected. 3925 1451 37 Cross sections measured by Abboud et al. for incident neutron 3925 1451 38 energies 14.61, 15.71-17.58 MeV [7] were renormalized to prelimi- 3925 1451 39 nary evaluated value of (968.5+-14.53) mb at 14.61 MeV. 3925 1451 40 The Y-89(n,2n)Y-88 reaction cross sections are not presented 3925 1451 41 directly in Ref. [28]. They were obtained by summing of partial 3925 1451 42 Y-89(n,2n) cross sections measured by Garret et al. in wide ener- 3925 1451 43 gy range 11.9-19.3 MeV. 3925 1451 44 Cross sections that had been determined in Refs. [31-38] were 3925 1451 45 rejected due to their significant overestimation or underestima- 3925 1451 46 tion of the Y-89(n,2n)Y-88 reaction excitation function. 3925 1451 47 Excitation function for the Y-89(n,2n)Y-88 reaction in the 3925 1451 48 energy region from threshold to 40 MeV was evaluated by means of 3925 1451 49 statistical analysis of experimental cross section data [1-30] 3925 1451 50 and data obtained from theoretical model calculation carried out 3925 1451 51 by means of modified GNASH code [39]. 3925 1451 52 Statistical analysis of input cross section data was carried 3925 1451 53 out by means of PADE-2 code [40]. Rational function was used as 3925 1451 54 the model function [41]. 3925 1451 55 Evaluated the Y-89(n,2n)Y-88 excitation function averaged over 3925 1451 56 the U-235 thermal fission spectrum [42] and Cf-252 spontaneous 3925 1451 57 fission neutron spectrum [43] gives the following values: 3925 1451 58 3925 1451 59 ----------------------+-----------------+----------------------- 3925 1451 60 Type of spectrum | ,mb (calc.) | , mb (measured) 3925 1451 61 ----------------------+-----------------+----------------------- 3925 1451 62 U-235 neutron fission | 0.14954 | 0.1502+-0.0050 [ *] 3925 1451 63 ----------------------+-----------------+----------------------- 3925 1451 64 CF-252 spont. fission | 0.34545 | 3925 1451 65 ----------------------+-----------------+----------------------- 3925 1451 66 3925 1451 67 Integral experimental cross section for the U-235 thermal fis- 3925 1451 68 sion spectrum was determined by averaging data from Refs. [44-48].3925 1451 69 Experiments which had been carried out in Cf-252 spontaneous fis- 3925 1451 70 sion neutron spectrum are absent for today. 3925 1451 71 3925 1451 72 MF=33 3925 1451 73 MT= 16 - (n,2n) cross section cov. matrix 3925 1451 74 ----------------------------------------- 3925 1451 75 Uncertainties in the evaluated excitation function for the 3925 1451 76 reaction Y-99(n,2n)Y-88 are given in the form of relative covari- 3925 1451 77 ance matrix for the 42-neutron energy groups (LB=5). Covariance 3925 1451 78 matrix of uncertainties was calculated simultaneously with recom- 3925 1451 79 mended cross section data by means of PADE-2 code [40]. 3925 1451 80 Eigenvalues of the 6-th digits relative covariance matrix 3925 1451 81 given in the 33-file are the following: 3925 1451 82 3925 1451 83 8.06094E-06 8.09518E-06 8.15855E-06 8.24661E-06 3925 1451 84 8.35531E-06 8.49547E-06 8.70638E-06 9.04991E-06 3925 1451 85 9.54483E-06 1.01444E-05 1.13129E-05 1.25114E-05 3925 1451 86 1.32643E-05 1.43223E-05 1.60064E-05 1.86551E-05 3925 1451 87 2.20343E-05 3.19852E-05 4.84211E-05 6.82562E-05 3925 1451 88 8.93968E-05 1.17234E-04 1.31898E-04 1.51179E-04 3925 1451 89 1.54185E-04 1.93535E-04 2.34841E-04 2.76250E-04 3925 1451 90 3.16877E-04 3.56383E-04 3.89006E-04 4.01050E-04 3925 1451 91 5.05488E-04 6.90848E-04 8.95586E-04 1.36883E-03 3925 1451 92 1.57985E-03 4.34718E-03 6.11763E-03 1.18122E-02 3925 1451 93 2.55468E-02 7.84234E-02 3925 1451 94 3925 1451 95 References: 3925 1451 96 1. 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A.A.Bojtcov, E.I.Grigor'ev, V.S.Troshin, V.P.Jaryna, VANT, 3925 1451 166 Ser.:Jadernyje Konstanty, Vol. 1, pp. 55-56, 1992 3925 1451 167 ***************************************************************** 3925 1451 168 3925 1451 169 1 451 172 13925 1451 170 3 16 45 13925 1451 171 33 16 161 13925 1451 172 3925 1 0 173 3925 0 0 174 3.90890+ 4 8.81421+ 1 0 0 0 03925 3 16 175 -1.14739+ 7-1.14739+ 7 0 0 1 1243925 3 16 176 124 2 3925 3 16 177 1.16041+ 7 0.00000+ 0 1.18000+ 7 4.06766- 2 1.19000+ 7 6.52139- 23925 3 16 178 1.20000+ 7 9.17841- 2 1.21000+ 7 1.20488- 1 1.22000+ 7 1.51403- 13925 3 16 179 1.23000+ 7 1.84568- 1 1.24000+ 7 2.19966- 1 1.25000+ 7 2.57505- 13925 3 16 180 1.26000+ 7 2.97001- 1 1.27000+ 7 3.38164- 1 1.28000+ 7 3.80604- 13925 3 16 181 1.29000+ 7 4.23840- 1 1.30000+ 7 4.67333- 1 1.31000+ 7 5.10529- 13925 3 16 182 1.32000+ 7 5.52907- 1 1.33000+ 7 5.94019- 1 1.34000+ 7 6.33526- 13925 3 16 183 1.35000+ 7 6.71200- 1 1.36000+ 7 7.06930- 1 1.37000+ 7 7.40694- 13925 3 16 184 1.38000+ 7 7.72543- 1 1.39000+ 7 8.02570- 1 1.40000+ 7 8.30890- 13925 3 16 185 1.41000+ 7 8.57624- 1 1.42000+ 7 8.82890- 1 1.43000+ 7 9.06790- 13925 3 16 186 1.44000+ 7 9.29416- 1 1.45000+ 7 9.50843- 1 1.46000+ 7 9.71134- 13925 3 16 187 1.47000+ 7 9.90343- 1 1.48000+ 7 1.00851+ 0 1.49000+ 7 1.02568+ 03925 3 16 188 1.50000+ 7 1.04189+ 0 1.51000+ 7 1.05717+ 0 1.52000+ 7 1.07154+ 03925 3 16 189 1.53000+ 7 1.08505+ 0 1.54000+ 7 1.09771+ 0 1.55000+ 7 1.10958+ 03925 3 16 190 1.56000+ 7 1.12067+ 0 1.57000+ 7 1.13102+ 0 1.58000+ 7 1.14066+ 03925 3 16 191 1.59000+ 7 1.14964+ 0 1.60000+ 7 1.15799+ 0 1.61000+ 7 1.16573+ 03925 3 16 192 1.62000+ 7 1.17292+ 0 1.63000+ 7 1.17957+ 0 1.64000+ 7 1.18574+ 03925 3 16 193 1.65000+ 7 1.19144+ 0 1.66000+ 7 1.19672+ 0 1.67000+ 7 1.20161+ 03925 3 16 194 1.68000+ 7 1.20613+ 0 1.69000+ 7 1.21031+ 0 1.70000+ 7 1.21419+ 03925 3 16 195 1.71000+ 7 1.21779+ 0 1.72000+ 7 1.22114+ 0 1.73000+ 7 1.22425+ 03925 3 16 196 1.74000+ 7 1.22715+ 0 1.75000+ 7 1.22987+ 0 1.76000+ 7 1.23241+ 03925 3 16 197 1.77000+ 7 1.23480+ 0 1.78000+ 7 1.23705+ 0 1.79000+ 7 1.23918+ 03925 3 16 198 1.80000+ 7 1.24120+ 0 1.81000+ 7 1.24312+ 0 1.82000+ 7 1.24495+ 03925 3 16 199 1.83000+ 7 1.24671+ 0 1.84000+ 7 1.24839+ 0 1.85000+ 7 1.25000+ 03925 3 16 200 1.86000+ 7 1.25156+ 0 1.87000+ 7 1.25305+ 0 1.88000+ 7 1.25450+ 03925 3 16 201 1.89000+ 7 1.25588+ 0 1.90000+ 7 1.25722+ 0 1.91000+ 7 1.25851+ 03925 3 16 202 1.92000+ 7 1.25973+ 0 1.93000+ 7 1.26090+ 0 1.94000+ 7 1.26201+ 03925 3 16 203 1.95000+ 7 1.26305+ 0 1.96000+ 7 1.26402+ 0 1.97000+ 7 1.26490+ 03925 3 16 204 1.98000+ 7 1.26570+ 0 1.99000+ 7 1.26640+ 0 2.00000+ 7 1.26700+ 03925 3 16 205 2.05000+ 7 1.26800+ 0 2.10000+ 7 1.26449+ 0 2.15000+ 7 1.25460+ 03925 3 16 206 2.20000+ 7 1.23637+ 0 2.25000+ 7 1.20813+ 0 2.30000+ 7 1.16888+ 03925 3 16 207 2.35000+ 7 1.11862+ 0 2.40000+ 7 1.05851+ 0 2.45000+ 7 9.90769- 13925 3 16 208 2.50000+ 7 9.18315- 1 2.55000+ 7 8.44261- 1 2.60000+ 7 7.71456- 13925 3 16 209 2.65000+ 7 7.02160- 1 2.70000+ 7 6.37913- 1 2.75000+ 7 5.79568- 13925 3 16 210 2.80000+ 7 5.27412- 1 2.85000+ 7 4.81326- 1 2.90000+ 7 4.40932- 13925 3 16 211 2.95000+ 7 4.05714- 1 3.00000+ 7 3.75100- 1 3.05000+ 7 3.48521- 13925 3 16 212 3.10000+ 7 3.25442- 1 3.15000+ 7 3.05378- 1 3.20000+ 7 2.87899- 13925 3 16 213 3.25000+ 7 2.72632- 1 3.30000+ 7 2.59256- 1 3.35000+ 7 2.47497- 13925 3 16 214 3.40000+ 7 2.37123- 1 3.45000+ 7 2.27936- 1 3.50000+ 7 2.19768- 13925 3 16 215 3.55000+ 7 2.12479- 1 3.60000+ 7 2.05949- 1 3.65000+ 7 2.00075- 13925 3 16 216 3.70000+ 7 1.94773- 1 3.75000+ 7 1.89968- 1 3.80000+ 7 1.85598- 13925 3 16 217 3.85000+ 7 1.81609- 1 3.90000+ 7 1.77955- 1 3.95000+ 7 1.74597- 13925 3 16 218 4.00000+ 7 1.71500- 1 3925 3 16 219 3925 3 0 220 3925 0 0 221 3.90890+ 4 8.81421+ 1 0 0 0 1392533 16 222 0.00000+ 0 0.00000+ 0 0 16 0 1392533 16 223 0.00000+ 0 0.00000+ 0 1 5 946 43392533 16 224 1.00000- 5 1.16041+ 7 1.19000+ 7 1.22000+ 7 1.25000+ 7 1.30000+ 7392533 16 225 1.35000+ 7 1.40000+ 7 1.42000+ 7 1.44000+ 7 1.46000+ 7 1.48000+ 7392533 16 226 1.50000+ 7 1.55000+ 7 1.60000+ 7 1.65000+ 7 1.70000+ 7 1.75000+ 7392533 16 227 1.80000+ 7 1.85000+ 7 1.90000+ 7 1.95000+ 7 2.00000+ 7 2.10000+ 7392533 16 228 2.20000+ 7 2.30000+ 7 2.40000+ 7 2.50000+ 7 2.60000+ 7 2.70000+ 7392533 16 229 2.80000+ 7 2.90000+ 7 3.00000+ 7 3.10000+ 7 3.20000+ 7 3.30000+ 7392533 16 230 3.40000+ 7 3.50000+ 7 3.60000+ 7 3.70000+ 7 3.80000+ 7 3.90000+ 7392533 16 231 4.00000+ 7 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0392533 16 232 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0392533 16 233 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0392533 16 234 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0392533 16 235 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0392533 16 236 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0392533 16 237 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0 0.00000+ 0392533 16 238 0.00000+ 0 2.43463- 2 4.61808- 3 7.76192- 4-3.23360- 5 3.59253- 4392533 16 239 -3.66509- 6-3.48141- 5 4.40897- 5 1.07435- 4 1.27123- 4 9.69460- 5392533 16 240 -3.44479- 5-2.24149- 4-2.97989- 4-2.43194- 4-1.16129- 4 2.20060- 5392533 16 241 1.30827- 4 1.93712- 4 2.12301- 4 1.99334- 4 1.60714- 4 1.51061- 4392533 16 242 2.25797- 4 3.24832- 4 3.44909- 4 2.48567- 4 1.00194- 4 2.06625- 6392533 16 243 1.77089- 5 1.48297- 4 3.52618- 4 5.77412- 4 7.77376- 4 9.23685- 4392533 16 244 1.00368- 3 1.01676- 3 9.69927- 4 8.73949- 4 7.40628- 4 5.81542- 4392533 16 245 5.12424- 3 2.47650- 3 4.52771- 4-1.29929- 4 9.84794- 5 7.88590- 5392533 16 246 3.95234- 5 2.22014- 5 3.14043- 5 6.20479- 5 1.34642- 4 2.09123- 4392533 16 247 2.17866- 4 1.77671- 4 1.20388- 4 6.95935- 5 3.62766- 5 2.17472- 5392533 16 248 2.17068- 5 2.95742- 5 4.15748- 5 3.98853- 5 1.94606- 5 8.50553- 6392533 16 249 3.27757- 5 8.76099- 5 1.43056- 4 1.71518- 4 1.65522- 4 1.35352- 4392533 16 250 9.78493- 5 6.72248- 5 5.14358- 5 5.22895- 5 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