IRDFF-v1-05_g.zip separated 31.08.15 by O.Gritzay using div-lib 6000 0 0 0 74186.0000 184.357000 0 0 31 17443 1451 1 0.0 0.0 0 0 0 67443 1451 2 1.00000000 150000000. 0 0 10 37443 1451 3 300.000000 0.0 1 0 511 67443 1451 4 74-W -186 IAEA Eval090806 A. Trkov, R. Capote et al 7443 1451 5 7443 1451 6 ----INDL/V-3 MATERIAL 7443 7443 1451 7 -----INCIDENT NEUTRON DATA 7443 1451 8 ------ENDF-6 FORMAT 7443 1451 9 ******************************************************************7443 1451 10 IAEA, July 2011 (A. Trkov) 7443 1451 11 The ENDF/B-VII.1 cross sections (from an IAEA evaluation) are 7443 1451 12 adopted. The relevant comments from the original evaluation are 7443 1451 13 included. For details see original evaluation. 7443 1451 14 The original covariances include the covariances of the resonance 7443 1451 15 parameters. The file was processed with NJOY in a group structure 7443 1451 16 that was adapted to the resonances of W-186, and to the covariance7443 1451 17 group structure above the resonance range. The processed 7443 1451 18 covariance was converted into ENDF format and added to the 7443 1451 19 dosimetry file. 7443 1451 20 ******************************************************************7443 1451 21 7443 1451 22 *************************************************** 7443 1451 23 FAST ENERGY REGION 7443 1451 24 Authors: R. Capote, A. Trkov, E. Soukhovitskii 7443 1451 25 7443 1451 26 CROSS-SECTION EVALUATION PROCEDURE 7443 1451 27 7443 1451 28 Adopted procedure is based on careful theoretical 7443 1451 29 analysis utilizing available experimental data and 7443 1451 30 nuclear reaction model calculations. 7443 1451 31 7443 1451 32 Available experimental data were interpreted using 7443 1451 33 nuclear reaction model code EMPIRE-2.19b35 by 7443 1451 34 M. Herman et al [He01, He02]. This code integrates 7443 1451 35 into a single system a number of important modules 7443 1451 36 and features: 7443 1451 37 7443 1451 38 - Spherical and deformed Optical Model including 7443 1451 39 coupled-channels (ECIS03 by J. Raynal) 7443 1451 40 - Hauser-Feshbach statistical model including 7443 1451 41 HRTW width fluctuation correction 7443 1451 42 - Quantum-mechanical MSD TUL model (codes ORION & 7443 1451 43 TRISTAN by H. Lenske), and MSC NVWY model 7443 1451 44 - Exciton model with angular momentum coupling 7443 1451 45 (code DEGAS by E. Betak and P. Oblozinsky) that 7443 1451 46 represents a good approximation to the DSD model 7443 1451 47 - Exciton model with Iwamoto-Harada cluster 7443 1451 48 emission and Kalbach systematic angular distr. 7443 1451 49 (code PCROSS by R.Capote et al) 7443 1451 50 - Complete gamma-ray cascade after emission of 7443 1451 51 each particle, including realistic treatment of 7443 1451 52 discrete transitions 7443 1451 53 - Access to OM segment of the RIPL-2 library [Ri03] 7443 1451 54 - Built-in input parameter files, such as masses, 7443 1451 55 level density, discrete levels, fission barriers 7443 1451 56 and gamma strength functions based on the RIPL-2 7443 1451 57 library [Ri03] 7443 1451 58 - Automatic retrieval of experimental data from the 7443 1451 59 EXFOR/CSISRS library 7443 1451 60 - ENDF-6 formatting (code EMPEND by A. Trkov) 7443 1451 61 coupled to graphical presentation capabilities 7443 1451 62 (code ZVView by V. Zerkin) through the chain of 7443 1451 63 PrePro codes by R. Cullen 7443 1451 64 - Checking codes (CHECKR, FIZCON, PSYCHE) 7443 1451 65 - Support for NJOY 7443 1451 66 7443 1451 67 PARAMETERIZATIONS 7443 1451 68 7443 1451 69 Following models and parameters were used in the 7443 1451 70 current evaluation: 7443 1451 71 7443 1451 72 Discrete levels were taken from the RIPL-2 level 7443 1451 73 file, based on the 1998 version of ENSDF. 7443 1451 74 EMPIRE-specific level densities 7443 1451 75 Spin-cut off parameter for dynamic LD reduced by factor 0.500 7443 1451 76 Exciton model calculations with code PCROSS 7443 1451 77 Cluster emission in terms of the Iwamoto-Harada model 7443 1451 78 Kalbach systematics angular distributions (see RIPL-1) 7443 1451 79 Mean free path parameter in PCROSS set to 1.3 (Recommended ~ 1.57443 1451 80 Max hole number in PCROSS set to 0.30*sqrt(g*U) 7443 1451 81 being U the CN excitation energy 7443 1451 82 Width fluctuations calculated within HRTW up to 3.00 MeV 7443 1451 83 Exclusive spectra available up to emission loop # 1 7443 1451 84 Shell corrections according to Myers-Swiatecki 7443 1451 85 PE emission width of ejectile 0 from 187W multiplied by 3.000 7443 1451 86 PE emission width of ejectile 2 from 187W multiplied by 1.100 7443 1451 87 Emission width of ejectile 0 from 187W multiplied by 1.600 7443 1451 88 Emission width of ejectile 2 from 187W multiplied by 1.760 7443 1451 89 Emission width of ejectile 3 from 187W multiplied by 1.600 7443 1451 90 Emission width of ejectile 3 from 186Ta multiplied by 0.200 7443 1451 91 Emission width of ejectile 3 from 185Ta multiplied by 0.050 7443 1451 92 Emission width of ejectile 3 from 184Ta multiplied by 0.050 7443 1451 93 Emission width of ejectile 3 from 183Ta multiplied by 0.050 7443 1451 94 Emission width of ejectile 3 from 182Ta multiplied by 0.050 7443 1451 95 Emission width of ejectile 3 from 181Ta multiplied by 0.050 7443 1451 96 Emission width of ejectile 3 from 180Ta multiplied by 0.050 7443 1451 97 Emission width of ejectile 3 from 179Ta multiplied by 0.050 7443 1451 98 Emission width of ejectile 3 from 178Ta multiplied by 0.050 7443 1451 99 Emission width of ejectile 3 from 177Ta multiplied by 0.050 7443 1451 100 Emission width of ejectile 3 from 176Ta multiplied by 0.050 7443 1451 101 Emission width of ejectile 3 from 186W multiplied by 0.200 7443 1451 102 Emission width of ejectile 3 from 185W multiplied by 0.050 7443 1451 103 Emission width of ejectile 3 from 184W multiplied by 0.030 7443 1451 104 Emission width of ejectile 3 from 183W multiplied by 0.030 7443 1451 105 Emission width of ejectile 3 from 182W multiplied by 0.030 7443 1451 106 Emission width of ejectile 3 from 181W multiplied by 0.030 7443 1451 107 Emission width of ejectile 3 from 180W multiplied by 0.030 7443 1451 108 Emission width of ejectile 3 from 179W multiplied by 0.030 7443 1451 109 Emission width of ejectile 3 from 178W multiplied by 0.030 7443 1451 110 Emission width of ejectile 3 from 177W multiplied by 0.030 7443 1451 111 Emission width of ejectile 3 from 176W multiplied by 0.030 7443 1451 112 Emission width of ejectile 1 from 185W multiplied by 1.150 7443 1451 113 Emission width of ejectile 1 from 184W multiplied by 1.150 7443 1451 114 Emission width of ejectile 1 from 183W multiplied by 1.150 7443 1451 115 Emission width of ejectile 1 from 182W multiplied by 1.150 7443 1451 116 Emission width of ejectile 1 from 181W multiplied by 1.150 7443 1451 117 Emission width of ejectile 1 from 180W multiplied by 1.150 7443 1451 118 Emission width of ejectile 1 from 179W multiplied by 1.150 7443 1451 119 Emission width of ejectile 1 from 178W multiplied by 1.150 7443 1451 120 Emission width of ejectile 1 from 177W multiplied by 1.150 7443 1451 121 Coupled Channels (ECIS) used for direct inelastic scattering 7443 1451 122 Coupled Channels (ECIS) used for Tl calculations in inelastic cha7443 1451 123 Total cross section was scaled by factor 1.300 7443 1451 124 E1 strength function set to MLO1 7443 1451 125 GDR parameters from RIPL-2/Exp.data+Plujko systematics 7443 1451 126 7443 1451 127 Use of preequilibrium models 7443 1451 128 ---------------------------- 7443 1451 129 7443 1451 130 Exit channel ECIS MSD MSC DEGAS HMS PCROSS 7443 1451 131 7443 1451 132 n to levels 1 0 0 0 0 0 7443 1451 133 n to continuum 0 0 0 0 0 1 7443 1451 134 p to levels 0 0 0 0 0 0 7443 1451 135 p to continuum 0 0 0 0 0 1 7443 1451 136 g 0 0 0 0 0 1 7443 1451 137 a 0 0 0 0 0 1 7443 1451 138 7443 1451 139 Collective levels used in direct calcualtions 7443 1451 140 74 186 nucleus is treated as deformed 7443 1451 141 7443 1451 142 Ncoll Lmax IDef Kgs (Def(1,j),j=2,IDef,2) 7443 1451 143 68 6 6 0.0 0.197E+00 -0.920E-01 -0.110E-02 7443 1451 144 7443 1451 145 N E[MeV] J pi Nph L K Dyn. Def. 7443 1451 146 1 0.0000 0.0 1. 0 0 0 0.100E-01 7443 1451 147 2 0.1226 2.0 1. 0 0 0 0.200E-01 7443 1451 148 3 0.3966 4.0 1. 0 0 0 0.200E-01 7443 1451 149 4 0.7380 2.0 1. 1 2 0 0.260E-01 7443 1451 150 5 0.8086 6.0 1. 0 0 0 0.200E-01 7443 1451 151 7 0.8820 0.0 1. 2 0 0 0.350E-01 7443 1451 152 5 0.8095 2.0 1. 0 0 0 0.260E-01 7443 1451 153 6 0.8621 3.0 1. 0 0 0 0.200E-01 7443 1451 154 8 0.9527 2.0 -1. 0 0 0 0.290E-01 7443 1451 155 9 1.0067 2.0 1. 0 0 0 0.200E-01 7443 1451 156 10 1.0149 3.0 1. 0 0 0 0.200E-01 7443 1451 157 11 1.0307 4.0 1. 0 0 0 0.200E-01 7443 1451 158 12 1.0453 3.0 -1. 0 0 0 0.560E-01 GOR 7443 1451 159 13 1.0509 2.0 1. 0 0 0 0.250E-01 cont 7443 1451 160 14 1.1358 0.0 1. 0 0 0 0.250E-01 cont 7443 1451 161 15 1.1444 2.0 1. 0 0 0 0.270E-01 cont 7443 1451 162 16 1.2214 2.0 1. 0 0 0 0.250E-01 cont 7443 1451 163 17 1.2574 2.0 1. 0 0 0 0.220E-01 cont 7443 1451 164 18 1.2892 2.0 -1. 0 0 0 0.250E-01 cont 7443 1451 165 19 1.3311 3.0 1. 0 0 0 0.300E-01 cont 7443 1451 166 20 1.3738 2.0 1. 0 0 0 0.240E-01 cont 7443 1451 167 21 1.4500 4.0 1. 0 0 0 0.350E-01 cont 7443 1451 168 22 1.5000 2.0 1. 0 0 0 0.250E-01 cont 7443 1451 169 23 1.6000 2.0 1. 0 0 0 0.260E-01 cont 7443 1451 170 24 1.8000 2.0 1. 0 0 0 0.260E-01 cont 7443 1451 171 25 1.9000 4.0 1. 0 0 0 0.360E-01 cont 7443 1451 172 26 2.0000 2.0 1. 0 0 0 0.260E-01 cont 7443 1451 173 27 2.1500 2.0 1. 0 0 0 0.280E-01 cont 7443 1451 174 28 2.3000 4.0 1. 0 0 0 0.370E-01 cont 7443 1451 175 29 2.4000 2.0 1. 0 0 0 0.280E-01 cont 7443 1451 176 30 2.5500 2.0 1. 0 0 0 0.250E-01 cont 7443 1451 177 31 2.7000 2.0 1. 0 0 0 0.260E-01 cont 7443 1451 178 32 2.8000 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 179 33 2.9000 2.0 1. 0 0 0 0.250E-01 cont 7443 1451 180 34 3.0000 3.0 -1. 0 0 0 0.360E-01 cont 7443 1451 181 35 3.1000 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 182 36 3.2000 3.0 -1. 0 0 0 0.360E-01 cont 7443 1451 183 37 3.3500 3.0 -1. 0 0 0 0.350E-01 cont 7443 1451 184 38 3.5000 3.0 -1. 0 0 0 0.360E-01 cont 7443 1451 185 39 3.7000 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 186 40 3.8000 2.0 1. 0 0 0 0.280E-01 cont 7443 1451 187 41 3.9000 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 188 42 4.0000 3.0 -1. 0 0 0 0.370E-01 cont 7443 1451 189 43 4.2000 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 190 44 4.3500 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 191 45 4.5000 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 192 46 4.6000 3.0 -1. 0 0 0 0.360E-01 cont 7443 1451 193 47 4.8000 2.0 1. 0 0 0 0.300E-01 cont 7443 1451 194 48 5.0000 3.0 -1. 0 0 0 0.360E-01 cont 7443 1451 195 49 5.2000 2.0 1. 0 0 0 0.250E-01 cont 7443 1451 196 50 5.4000 4.0 1. 0 0 0 0.350E-01 cont 7443 1451 197 51 5.4700 3.0 -1. 0 0 0 0.310E-01 lGOR 7443 1451 198 52 5.6000 2.0 1. 0 0 0 0.270E-01 cont 7443 1451 199 53 5.8000 3.0 -1. 0 0 0 0.300E-01 cont 7443 1451 200 54 6.0000 2.0 1. 0 0 0 0.250E-01 cont 7443 1451 201 55 6.2000 4.0 1. 0 0 0 0.300E-01 cont 7443 1451 202 56 6.4000 3.0 -1. 0 0 0 0.250E-01 cont 7443 1451 203 57 6.6000 2.0 1. 0 0 0 0.200E-01 cont 7443 1451 204 58 6.8000 2.0 1. 0 0 0 0.200E-01 cont 7443 1451 205 59 7.0000 3.0 -1. 0 0 0 0.200E-01 cont 7443 1451 206 60 7.3000 2.0 1. 0 0 0 0.120E-01 cont 7443 1451 207 61 7.6000 2.0 1. 0 0 0 0.120E-01 cont 7443 1451 208 62 8.0000 3.0 -1. 0 0 0 0.200E-01 cont 7443 1451 209 63 8.2000 4.0 1. 0 0 0 0.300E-01 cont 7443 1451 210 64 8.4000 3.0 -1. 0 0 0 0.250E-01 cont 7443 1451 211 65 8.6000 2.0 1. 0 0 0 0.170E-01 cont 7443 1451 212 66 8.8000 2.0 1. 0 0 0 0.180E-01 cont 7443 1451 213 67 9.0000 2.0 1. 0 0 0 0.150E-01 cont 7443 1451 214 7443 1451 215 7443 1451 216 Inelastic o. m. parameters: RIPL catalog number 1482 7443 1451 217 Neutron o. m. parameters: RIPL catalog number 1482 7443 1451 218 Proton o. m. parameters: RIPL catalog number 4432 7443 1451 219 Alpha o. m. parameters: RIPL catalog number 9600 7443 1451 220 7443 1451 221 B i n d i n g e n e r g i e s 7443 1451 222 7443 1451 223 Nucleus 1n 1p 4He 7443 1451 224 7443 1451 225 74-W -187 5.467 8.586 -0.954 7443 1451 226 74-W -186 7.194 8.404 -1.124 7443 1451 227 74-W -185 5.753 7.837 -1.601 7443 1451 228 74-W -184 7.411 7.699 -1.659 7443 1451 229 74-W -183 6.191 7.222 -1.682 7443 1451 230 74-W -182 < 8.064 7.094 -1.774 7443 1451 231 74-W -181 < 6.681 6.607 -2.212 7443 1451 232 74-W -180 < 8.412 6.570 -2.516 7443 1451 233 74-W -179 < 6.931 6.058 -2.763 7443 1451 234 74-W -178 < 8.790 6.007 -2.985 7443 1451 235 74-W -177 < 7.111 5.538 -3.136 7443 1451 236 74-W -176 < 9.171 5.482 -3.287 7443 1451 237 74-W -175 < 7.502 4.865 -3.425 7443 1451 238 74-W -174 < 9.629 4.847 -3.639 7443 1451 239 73-Ta-186 5.285 7.503 -0.687 7443 1451 240 73-Ta-185 6.627 7.185 -0.919 7443 1451 241 73-Ta-184 5.615 6.843 -1.422 7443 1451 242 73-Ta-183 6.934 6.525 -1.346 7443 1451 243 73-Ta-182 < 6.063 6.308 -1.488 7443 1451 244 73-Ta-181 < 7.577 5.940 -1.526 7443 1451 245 73-Ta-180 < 6.644 5.751 -2.031 7443 1451 246 73-Ta-179 < 7.900 5.206 -2.387 7443 1451 247 73-Ta-178 < 6.880 4.932 -2.621 7443 1451 248 73-Ta-177 < 8.321 4.429 -2.740 7443 1451 249 73-Ta-176 < 7.055 4.273 -2.846 7443 1451 250 73-Ta-175 < 8.554 3.927 -2.922 7443 1451 251 73-Ta-174 < 7.484 4.012 -2.881 7443 1451 252 73-Ta-173 < 9.190 3.488 -3.061 7443 1451 253 72-Hf-185 < 4.967 9.515 -0.025 7443 1451 254 72-Hf-184 < 6.285 9.266 -0.479 7443 1451 255 72-Hf-183 5.297 8.853 99.000 7443 1451 256 72-Hf-182 < 6.717 8.609 -1.216 7443 1451 257 72-Hf-181 < 5.695 8.016 -1.154 7443 1451 258 72-Hf-180 < 7.388 8.012 -1.282 7443 1451 259 72-Hf-179 < 6.099 7.416 -1.806 7443 1451 260 72-Hf-178 < 7.626 7.342 -2.083 7443 1451 261 72-Hf-177 < 6.377 6.788 -2.245 7443 1451 262 72-Hf-176 < 8.165 6.699 -2.255 7443 1451 263 72-Hf-175 < 6.709 6.200 -2.400 7443 1451 264 72-Hf-174 < 8.639 6.252 -2.495 7443 1451 265 72-Hf-173 < 6.960 5.828 -2.664 7443 1451 266 72-Hf-172 < 9.033 5.847 -2.757 7443 1451 267 71-Lu-184 < 4.718 7.269 -0.485 7443 1451 268 71-Lu-183 < 5.872 6.712 0.347 7443 1451 269 71-Lu-182 < 5.053 8.165 0.031 7443 1451 270 71-Lu-181 < 6.124 7.625 -0.304 7443 1451 271 71-Lu-180 < 5.691 7.560 -0.265 7443 1451 272 71-Lu-179 < 6.792 6.655 -0.827 7443 1451 273 71-Lu-178 < 6.025 6.642 -1.102 7443 1451 274 71-Lu-177 < 7.072 6.184 -1.445 7443 1451 275 71-Lu-176 < 6.288 5.976 -1.568 7443 1451 276 71-Lu-175 < 7.666 5.510 -1.620 7443 1451 277 71-Lu-174 < 6.761 5.308 -1.800 7443 1451 278 71-Lu-173 < 8.215 4.914 -1.968 7443 1451 279 71-Lu-172 < 6.979 4.719 -2.150 7443 1451 280 71-Lu-171 < 8.595 4.354 -2.289 7443 1451 281 72-Hf-171 < 7.288 5.409 -2.739 7443 1451 282 72-Hf-170 < 9.477 5.425 -2.950 7443 1451 283 71-Lu-170 < 7.304 4.229 -2.157 7443 1451 284 71-Lu-169 < 9.049 3.792 -2.434 7443 1451 285 70-Yb-181 < 4.513 9.055 0.767 7443 1451 286 70-Yb-180 < 6.059 10.092 0.524 7443 1451 287 70-Yb-179 < 4.786 9.589 0.338 7443 1451 288 70-Yb-178 < 6.779 9.521 0.279 7443 1451 289 70-Yb-177 < 5.567 8.905 -0.236 7443 1451 290 70-Yb-176 < 6.864 8.467 -0.571 7443 1451 291 70-Yb-175 < 5.822 8.120 -0.600 7443 1451 292 70-Yb-174 < 7.464 7.980 -0.740 7443 1451 293 70-Yb-173 < 6.367 7.465 -0.946 7443 1451 294 70-Yb-172 < 8.020 7.334 -1.310 7443 1451 295 70-Yb-171 < 6.614 6.800 -1.559 7443 1451 296 70-Yb-170 < 8.470 6.779 -1.737 7443 1451 297 70-Yb-169 < 6.867 6.342 99.000 7443 1451 298 70-Yb-168 < 9.051 6.315 -1.951 7443 1451 299 69-Tm-180 < 5.550 9.139 1.555 7443 1451 300 69-Tm-179 < 5.556 7.580 1.224 7443 1451 301 69-Tm-178 < 4.718 8.901 1.038 7443 1451 302 69-Tm-177 < 6.163 8.453 0.795 7443 1451 303 69-Tm-176 < 5.129 8.163 0.402 7443 1451 304 69-Tm-175 < 6.517 7.761 0.215 7443 1451 305 69-Tm-174 < 5.682 7.508 0.050 7443 1451 306 69-Tm-173 < 6.949 7.058 -0.120 7443 1451 307 69-Tm-172 < 6.236 6.944 -0.276 7443 1451 308 69-Tm-171 < 7.486 6.390 -0.649 7443 1451 309 69-Tm-170 < 6.593 6.162 -0.851 7443 1451 310 69-Tm-169 < 8.033 5.572 -1.200 7443 1451 311 69-Tm-168 < 6.840 5.310 -1.245 7443 1451 312 69-Tm-167 < 8.727 4.906 -1.411 7443 1451 313 7443 1451 314 < indicates inclusive spectra only 7443 1451 315 7443 1451 316 RESULTS 7443 1451 317 7443 1451 318 MF=3 Neutron cross sections 7443 1451 319 EMPIRE calculations were adopted for: 7443 1451 320 MT=1 Total 7443 1451 321 MT=2 Elastic scattering 7443 1451 322 MT=102 Capture 7443 1451 323 7443 1451 324 REFERENCES 7443 1451 325 7443 1451 326 [He01] M. Herman EMPIRE-II Statistical Model 7443 1451 327 Code for Nuclear Reaction Calculations, in 7443 1451 328 Nuclear Reaction Data and Nuclear Reactors, 7443 1451 329 eds. N.Paver, M. Herman and A.Gandini, ICTP 7443 1451 330 Lecture Notes 5 (ICTP Trieste, 2001) pp.137. 7443 1451 331 7443 1451 332 [He02] M. Herman, R. Capote, P. Oblozinsky, 7443 1451 333 M. Sin, A. Trkov, A. Ventura, V. Zerkin 7443 1451 334 Recent Development of the Nuclear 7443 1451 335 Reaction Model Code EMPIRE, International 7443 1451 336 Conference on Nuclear Data for Science & 7443 1451 337 Technology - ND2004 September 26 - October 1, 7443 1451 338 2004, Santa Fe, New Mexico. 7443 1451 339 7443 1451 340 [Ri03] 7443 1451 341 Handbook for calculations of nuclear reaction 7443 1451 342 data: Reference Input Parameter Library II. 7443 1451 343 IAEA, Vienna 2005. Available online at 7443 1451 344 http://www-nds.iaea.org/RIPL-2/ 7443 1451 345 7443 1451 346 ************************************************ 7443 1451 347 7443 1451 348 7443 1451 349 EVALUATION PROCEDURE OF COVARIANCE DATA ABOVE RESONANCE RANGE 7443 1451 350 7443 1451 351 The GANDR System is employed to generate covariance matrix of the7443 1451 352 cross sections of W-186 based on the new INDL file produced as a 7443 1451 353 result of an IAEA Data Development Project. 7443 1451 354 7443 1451 355 The prior covariance matrix (above 100 keV) is generated by the 7443 1451 356 Monte Carlo technique. The final covariance matrix is the result 7443 1451 357 of a GANDR calculation after introducing a selected set of 7443 1451 358 experimental data as follows. Only the EXFOR entries preceeded 7443 1451 359 by the sequence number are included in the fitting procedure. 7443 1451 360 Reasons for exclusion or modification are given in the comments. 7443 1451 361 7443 1451 362 (n,tot) Total 7443 1451 363 ------------ 7443 1451 364 Author Year EXFOR No. Comment 7443 1451 365 --------------------------------------------------------------- 7443 1451 366 - W.SELOVE (51) X12168 6 Old 7443 1451 367 2 J.F.WHALEN,ET.AL. (82) X11540 19 Add 0.1 b uncertainty 7443 1451 368 3 K.KNOPF,ET.AL. (87) X22045 10 Only 143 keV point 7443 1451 369 4 P.T.GUENTHER,ET.AL. (82) X10803 19 7443 1451 370 - R.C.MARTIN,ET.AL. (67) X12159 5 Old and discrepant 7443 1451 371 6 D.G.FOSTER JR,ET.AL. (71) X10047107 <10 MeV 7443 1451 372 7 D.G.FOSTER JR,ET.AL. (71) X10047107 >10 MeV 7443 1451 373 8 F.S.Dietrich,ET.AL. (03) X13887 4 7443 1451 374 - A.N.DJUMIN,ET.AL. (77) X40585 36 Single point 7443 1451 375 Systematic uncertainties: 7443 1451 376 - 2% for each Exfor set 7443 1451 377 - 2% common to all measurements 7443 1451 378 7443 1451 379 (n,g) Radiative capture 7443 1451 380 ----------------------- 7443 1451 381 Author Year EXFOR No. Comment 7443 1451 382 --------------------------------------------------------------- 7443 1451 383 - S.J.FRIESENHANN (66) X12167 8 Resonance 7443 1451 384 - G.GLEASON (77) X10662 14 Thermal 7443 1451 385 - L.SEREN,ET.AL. (47) X11447115 Thermal 7443 1451 386 - H.POMERANCE (52) X11507 94 Thermal 7443 1451 387 - W.S.LYON (60) X11625 32 Thermal 7443 1451 388 - S.J.FRIESENHAHN, (66) X12167 9 Thermal 7443 1451 389 - C.H.HOGG,ET.AL. (70) X12602 7 Thermal 7443 1451 390 - P.P.DAMLE,ET.AL. (67) X20184 2 Thermal 7443 1451 391 - K.KNOPF,ET.AL. (87) X22045 16 Thermal 7443 1451 392 - M.Karadag,ET.AL. (04) X22842 2 Thermal 7443 1451 393 - V.A.ANUFRIEV,ET.AL. (81) X40608 3 Thermal 7443 1451 394 - S.V.KAPCHIGASHEV, (66) X40755 5 Resonance 7443 1451 395 13 R.C.BLOCK,ET.AL. (66) X11458 8 (9 points) 7443 1451 396 14 R.L.MACKLIN,ET.AL. (83) X10999 9 (34 points) 7443 1451 397 15 M.V.BOKHOVKO,ET.AL. (86) X40925 6 (19 points) <50 keV 7443 1451 398 - M.V.BOKHOVKO,ET.AL. (86) X40925 6 (38 points) >50 keV 7443 1451 399 - K.Siddappa,ET.AL. (74) X30502 18 7443 1451 400 - R.L.MACKLIN,ET.AL. (57) X11399 45 (1 point) 7443 1451 401 - R.BOOTH,ET.AL. (58) X11429 28 7443 1451 402 - A.K.CHAUBEY,ET.AL. (65) X30079 35 7443 1451 403 - V.N.KONONOV,ET.AL. (58) X40421 23 7443 1451 404 - T.BRADLEY,ET.AL. (79) X10938 6 7443 1451 405 - YU.YA.STAVISSKII, (60) X40452 5 7443 1451 406 - J.A.MISKEL,ET.AL. (62) X12115 5 7443 1451 407 - V.N.KONONOV,ET.AL. (66) X40076 7 7443 1451 408 - Vuong Huu Tan,ET.AL. (04) X31542 2 7443 1451 409 - J.A.MISKEL,ET.AL. (62) X12115 6 7443 1451 410 - M.LINDNER,ET.AL. (76) X10221 44 7443 1451 411 - A.E.JOHNSRUD,ET.AL. (59) X11675 25 7443 1451 412 - W.S.LYON,ET.AL. (59) X11407 30 7443 1451 413 - A.I.LEIPUNSKIJ, (58) X40244 36 7443 1451 414 - G.G.ZAIKIN,ET.AL. (68) X40248 4 7443 1451 415 - Z.M.BARTOLOME,ET.AL. (69) X10002 41 7443 1451 416 34 S.JOLY,ET.AL. (81) X21619 15 (3 points) 7443 1451 417 - J.VOIGNIER,ET.AL. (92) X22006 21 7443 1451 418 - GUOHUI ZHANG,ET.AL. (01) X32550 2 7443 1451 419 - L.E.BEGHIAN,ET.AL. (49) X22580 14 7443 1451 420 38 YU.N.TROFIMOV (87) X41001 37 (1 point) 7443 1451 421 - M.V.PASECHNIK,ET.AL. (58) X40336 93 7443 1451 422 - A.I.LEIPUNSKIJ, (58) X40244 17 7443 1451 423 - M.DIKSIC,ET.AL. (70) X30023 12 7443 1451 424 - A.I.LEIPUNSKIJ, (58) X40244 58 7443 1451 425 - J.L.PERKIN,ET.AL. (58) X21438 25 7443 1451 426 - O.SCHWERER,ET.AL. (76) X20670 16 7443 1451 427 45 M.VALKONEN (76) X20673 35 (1 point) 7443 1451 428 46 G.MAGNUSSON,ET.AL. (80) X21004 4 (1 point) 7443 1451 429 47 G.D.Kim,ET.AL. (07) X20673 35 (3 points) 7443 1451 430 Systematic uncertainties: 7443 1451 431 - 3% for each Exfor set 7443 1451 432 - 1% common to all measurements 7443 1451 433 7443 1451 434 7443 1451 435 *** ENDRESS - Merging source and resonance ENDF files 7443 1451 436 Source ENDF W186_ib21g.t0 7443 1451 437 Resonance ENDF ..\resonance\W186_ib8forAndrej.end 7443 1451 438 7443 1451 439 RESOLVED RESONANCE PARAMETERS (L. Leal, ORNL, January 2008) 7443 1451 440 Starting from the resonance parameter data in the IRDF-2002 7443 1451 441 library, small adjustments were made to reproduce the thermal 7443 1451 442 capture cross section of 38.09 barns and the resonance integral 7443 1451 443 of 483.4 barns as closely as possible. This ratio 12.69 is in 7443 1451 444 good agreement with the value 12.59+/-0.22 from the Kayzero 7443 1451 445 database for neutron activation analysis [1]. 7443 1451 446 7443 1451 447 RESOLVED RESONANCE PARAMETERS (IRDF-2002) 7443 1451 448 Resolved MLBW resonance parameters up to 8.5 keV were based 7443 1451 449 on data from ref.[2-3]. Spins of resonances, which were not iden- 7443 1451 450 tified, have been assigned by taking into account 2*J+1 law and 7443 1451 451 approximate linear growth of the number of levels with given spin 7443 1451 452 and parity from energy. Average gamma-widths 0.05 eV (L=0 and L=1)7443 1451 453 were assigned to those resonances, widths for which were absent. 7443 1451 454 Fictitious resonances were added in the energy region 4 - 8.5 keV 7443 1451 455 to obtain the average capture cross section values observed in 7443 1451 456 the experiments [4],[5],[6],[7]. 7443 1451 457 7443 1451 458 UNRESOLVED RESONANCE PARAMETERS (IRDF-2002) 7443 1451 459 Unresolved resonance parameters in the region 8.5 - 100 keV 7443 1451 460 were evaluated with using 'EVPAR' code (Hauser-Feshbach-Moldauer 7443 1451 461 statistical model)[8]. They were calculated from optimized fit to 7443 1451 462 the measured capture [5,6,7,9,10] and total [11,12] cross sections7443 1451 463 data. Average resolved resonance parameters have been used as 7443 1451 464 zero approximation. Contribution of F-wave in the energy region 7443 1451 465 30 - 100 keV given as smoothed background cross section in File 3.7443 1451 466 7443 1451 467 RESONANCE COVARIANCE DATA (L. Leal, ORNL, Jan 2008) 7443 1451 468 The procedure used to generate the resolved covariance data 7443 1451 469 with the SAMMY code is as follow: 7443 1451 470 a) Retrieve best set of available resonance parameters. 7443 1451 471 b) Convert the resonance parameters into the Reich-Moore form. 7443 1451 472 c) Generate "experimental" cross sections for total, scattering, 7443 1451 473 and capture cross sections with the NJOY code, for use as 7443 1451 474 "experimental data" in SAMMY. 7443 1451 475 d) Assign a global "experimental" uncertainty to the 7443 1451 476 "experimental data." The uncertainties used were based on 7443 1451 477 uncertainty in the thermal capture cross section and 7443 1451 478 uncertainty in the capture resonance integrals. 7443 1451 479 e) Run SAMMY code with the option to generate 7443 1451 480 resonance-covariances retroactively. 7443 1451 481 f) Convert the resonance-covariance results from SAMMY into 7443 1451 482 the ENDF format for file 32 and MT=151. 7443 1451 483 7443 1451 484 The resulting resonance parameters and covariance were used in 7443 1451 485 the calculations of average cross sections and uncertainties. 7443 1451 486 The calculations were done with SAMMY, ERRORJ, and PUFF-IV codes. 7443 1451 487 The results of these three codes agreed very well. 7443 1451 488 7443 1451 489 References : 7443 1451 490 1. F. De Corte, A. Simonits, Atomic Data Nucl. Data Tables 85, 7443 1451 491 (2003), 47-67. 7443 1451 492 2. S.F.Mughabghab et al. Neutron Cross Sections, vol.1, part B, 7443 1451 493 New York, Academic Press, 1984 7443 1451 494 3. S.I.Sukhoruchkin et al. Landolt Bornstein New Series, v.I/16B,7443 1451 495 ed. H.Schopper, Springer, 1998, pp.w19-w23 7443 1451 496 4. S.V.Kapchigashev, Ju.P.Popov, F.L.Shapiro EXFOR 40755.005 7443 1451 497 5. Z.M.Bartolome et al. Nucl. Sci. Eng., v.37, pp.137-156, 1969 7443 1451 498 6. R.L.Macklin et al. Nucl. Sci. Eng., v.84, p.98, June 1983 7443 1451 499 7. M.V.Bokhovko et al. Voprosy Atomnoj Nauki i Tekhniki, Ser.: 7443 1451 500 Yadernye Konstanty, v.1, p.39, February 1986 7443 1451 501 8. G.N.Manturov et al. Voprosy Atomnoy Nauki i Tekhniki, Ser.: 7443 1451 502 Jadernye Konstanty, v.1, p.50, 1983 7443 1451 503 9. Yu.Ya.Stavisskii, V.A.Tolstikov Atomnaja Energija, v.9, 7443 1451 504 p.401, 1960 7443 1451 505 10. V.N.Kononov et al. Yadernaja Fizika, v.4, no.2, p.282, 1966 7443 1451 506 11. P.T.Guenther. et al. Phys. Rev. C., v.26, p.2433, 1982 7443 1451 507 12. V.N.Kononov et al. Sov J. of Nuclear Physics, v.46, part 1, 7443 1451 508 ***************************************************************** 7443 1451 509 ***************** Program LINEAR (VERSION 2012-1) ***************7443 1451 510 For All Data Greater than 1.0000D-10 barns in Absolute Value 7443 1451 511 Data Linearized to Within an Accuracy of .100000000 per-cent 7443 1451 512 ***************** Program GROUPIE (VERSION 2012-1) **************7443 1451 513 Unshielded Group Averages Using 640 Groups 7443 1451 514 Weighting Spectrum: Flat (Constant) Spectrum 7443 1451 515 1 451 503 17443 1451 516 2 151 4 17443 1451 517 3 1 17755 17443 1451 518 3 2 17523 17443 1451 519 3 102 32393 17443 1451 520 33 102 184 17443 1451 521 7443 1 0 522 7443 0 0 523 74186.0000 184.357000 0 0 1 07443 2151 524 7.418600+4 1.000000+0 0 0 1 07443 2151 525 1.000000-5 8.500000+3 0 0 0 07443 2151 526 0.000000+0 7.640000-1 0 0 0 07443 2151 527 7443 2 0 528 7443 0 0 529 74186.0000 184.357000 0 0 0 07443 3 1 530 0.0 0.0 0 0 1 6417443 3 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