1 0 0 7.919700+4 1.952740+2 0 0 0 07925 1451 1 0.000000+0 0.000000+0 0 0 0 67925 1451 2 1.000000+0 2.800000+6 1 0 19 77925 1451 3 0.000000+0 0.000000+0 1 0 305 37925 1451 4 79-Au-197 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 7925 1451 5 DIST-DEC06 7925 1451 6 ----INTERN. STANDARD MATERIAL 7925 7925 1451 7 -----STANDARDS SUBLIBRARY 7925 1451 8 ------ENDF-6 FORMAT 7925 1451 9 Submitted to the IAEA by V.G. Pronyaev (CRP Scientific Secretary),7925 1451 10 IPPE, 19/02/2007********************************************** 7925 1451 11 7925 1451 12 197Au(n,g) cross section of the ENDF/B-VII standards 7925 1451 13 sub-library submitted by A.D. Carlson, NIST, on 28 February 2006. 7925 1451 14 This cross section is recommended as a standard at thermal and 7925 1451 15 from 0.2 MeV to 2.5 MeV. 7925 1451 16 7925 1451 17 Included are: 7925 1451 18 197Au(n,g) MT=102 7925 1451 19 ************************************************************** 7925 1451 20 7925 1451 21 The evaluation was done in the framework of an IAEA (Vienna, 7925 1451 22 Austria) Coordinated Research Project on improvement of the 7925 1451 23 standard cross sections with contributions by 7925 1451 24 the NEA (Paris, France) WPEC Subgroup 7 on Nuclear Data Standards 7925 1451 25 and the CSEWG (USA). 7925 1451 26 Participants of the Project: 7925 1451 27 Sergei A. Badikov, Institute of Physics and Power Engineering, 7925 1451 28 Russia 7925 1451 29 Chen Zhenpeng, Tsinghua University, China 7925 1451 30 Allan D. Carlson, National Institute of Standards and Technology, 7925 1451 31 USA 7925 1451 32 Evgeny V. Gai, Institute of Physics and Power Engineering, 7925 1451 33 Russia 7925 1451 34 Gerald M. Hale, Los Alamos National Laboratory, USA 7925 1451 35 Franz-Josef Hambsch, Institute for Reference Materials and 7925 1451 36 Measurements, Belgium 7925 1451 37 Hartmut M. Hofmann, Universitat Erlangen-Nurnberg, Germany 7925 1451 38 Nancy M. Larson, Oak Ridge National Laboratory, USA 7925 1451 39 Donald L. Smith, Argonne National Laboratory, USA 7925 1451 40 Soo-Youl Oh, Korea Atomic Energy Research Institute, 7925 1451 41 Republic of Korea 7925 1451 42 Siegfried Tagesen, Institute for Isotopenforschung and 7925 1451 43 Kernphysik der Universitat Wien, Austria 7925 1451 44 Herbert Vonach, Institute for Isotopenforschung and 7925 1451 45 Kernphysik der Universitat Wien, Austria 7925 1451 46 Vladimir G. Pronyaev, International Atomic Energy Agency, Austria 7925 1451 47 and Institute of Physics and Power Engineering, Russia 7925 1451 48 7925 1451 49 The evaluation methodology and the preliminary results are given 7925 1451 50 in [1]. A detailed description and the final results will be 7925 1451 51 published by the IAEA as an IAEA technical report series [2]. 7925 1451 52 7925 1451 53 The ENDF/B-VII standard cross section evaluations are a 7925 1451 54 result of the combining of the GMA [3] simultaneous evaluation 7925 1451 55 with EDA [4] and RAC [5] R-matrix evaluations. A large 7925 1451 56 database of experimental data was used for the evaluation. The 7925 1451 57 status of the standards database [6] was reported on recently. 7925 1451 58 The most recent discussion is in the IAEA tech. report series [2].7925 1451 59 The database included both shape and absolute cross section 7925 1451 60 measurements and their ratios. It also included data involving 7925 1451 61 the 238U(n,g) and 239Pu(n,f) cross sections. There are 7925 1451 62 many very accurate measurements of these cross sections. The 7925 1451 63 use of these additional data improves the database as a result of 7925 1451 64 ratio measurements of those cross sections to the traditional 7925 1451 65 standards. Measurements of the 235U and 239Pu fission cross 7925 1451 66 sections in the 252Cf spontaneous fission neutron spectrum were 7925 1451 67 also included in the database. These data can be obtained with 7925 1451 68 high accuracy and are only weakly dependent on the 7925 1451 69 uncertainties in the 252Cf spontaneous neutron fission spectrum. 7925 1451 70 These data can have an important effect on the normalization 7925 1451 71 of the evaluated cross sections. Also scattering and total cross 7925 1451 72 section data have been included for 6Li and 10B since they 7925 1451 73 provide information on the standard cross sections. Charged- 7925 1451 74 particle and angular distribution data were also included since 7925 1451 75 they can be used in R-matrix analyses. 7925 1451 76 7925 1451 77 To reduce the effect of discrepant data on the GMA analysis 7925 1451 78 and the RAC R-matrix evaluation for the database of neutron 7925 1451 79 experiments used in the present international evaluation, 7925 1451 80 deviations of experimental measurements from the output of 7925 1451 81 the evaluation were compared with the uncertainties on the 7925 1451 82 data. The outliers were defined as those for which the 7925 1451 83 difference from the evaluated output value was above two 7925 1451 84 standard deviations for a single point or above one standard 7925 1451 85 deviation for a few sequential points. The uncertainty of 7925 1451 86 outliers was increased by adding an additional component to 7925 1451 87 the covariance matrix of the uncertainty of each outlying data 7925 1451 88 set. The length of correlation for this additional medium- 7925 1451 89 energy-range-correlation component was evaluated from an 7925 1451 90 analysis of the energy dependence of the discrepancy. For the 7925 1451 91 R-matrix code EDA, the effect of discrepant data was handled 7925 1451 92 by modifying the output covariances by the chi square per 7925 1451 93 degree of freedom value of the fit. These methods for handling 7925 1451 94 discrepant data resulted in a much better chi square per degree 7925 1451 95 of freedom and larger uncertainty in the evaluated results. The 7925 1451 96 change in the cross section from the procedures was small. 7925 1451 97 7925 1451 98 All data in the database relative to hydrogen cross sections 7925 1451 99 were converted so they are relative to the ENDF/B-VII 7925 1451 100 hydrogen standard. After this conversion process was 7925 1451 101 completed, a hydrogen re-evaluation was recommended as a 7925 1451 102 result of preliminary data testing due to concerns about the 7925 1451 103 thermal capture cross section. The re-evaluation resulted in 7925 1451 104 small changes in the hydrogen standard cross section. The 7925 1451 105 conversion process was not re-done but uncertainties on the 7925 1451 106 converted data were increased to account for the changes in the 7925 1451 107 hydrogen cross section. 7925 1451 108 7925 1451 109 Problems associated with PPP were observed early in the 7925 1451 110 evaluation process [7]. The problem appears to be largely a 7925 1451 111 result of using discrepant data but it also is caused by the 7925 1451 112 existence of data correlations. The effect was minimized in the 7925 1451 113 GMA code by adding the Chiba-Smith [8] option to handle PPP 7925 1451 114 problems. This option, called GMAP, renormalizes the 7925 1451 115 experimental absolute errors on the assumption that it is the 7925 1451 116 fractional error that actually reflects the accuracy the 7925 1451 117 experimenter has provided. 7925 1451 118 7925 1451 119 The Au(n,g) cross section and all the other standard cross 7925 1451 120 sections except the H(n,n), 3He(n,p) and C(n,n) cross sections 7925 1451 121 were evaluated using the GMAP code to combine input from 7925 1451 122 the RAC and EDA R-matrix analyses, and a thermal constants 7925 1451 123 evaluation. The Axton [9] evaluation of the thermal constants 7925 1451 124 with the associated variance-covariance data for 233U, 235U, 7925 1451 125 239Pu and 241Pu was used as input to the GMAP code since it 7925 1451 126 includes accurate cross sections which have been measured 7925 1451 127 relative to the neutron cross section standards. Thus this 7925 1451 128 evaluation would have an impact on the determination of the 7925 1451 129 standards. The R-matrix input and thermal constants data were 7925 1451 130 treated like the additions of other data sets to the GMAP code. 7925 1451 131 7925 1451 132 The R-matrix analyses used charged-particle data and the 7925 1451 133 lithium and boron neutron databases, including total and 7925 1451 134 scattering cross section data for these nuclides. The only 7925 1451 135 lithium and boron data for direct use in the GMAP code were 7925 1451 136 the ratio measurements. The R-matrix and GMAP data are 7925 1451 137 totally independent of each other. There are no common data 7925 1451 138 sets and no data sets that have correlations between the R- 7925 1451 139 matrix and GMAP data. For the 6Li(n,t), 10B(n,a) and 7925 1451 140 10B(n,a1) R-matrix work, the cross sections 7925 1451 141 obtained from the RAC and EDA analyses were not identical. 7925 1451 142 The cross sections from the RAC and EDA analyses were 7925 1451 143 averaged (unweighted) and used as the R-matrix input to 7925 1451 144 GMAP. The covariance matrix used with these central values 7925 1451 145 was that from the RAC code since its results appeared more 7925 1451 146 physically reasonable. At each energy point, half the 7925 1451 147 difference between the RAC and GMAP results was treated as 7925 1451 148 a model uncertainty that was added to the RAC covariance of 7925 1451 149 uncertainties. This then takes into account the differences 7925 1451 150 obtained between the RAC and EDA analyses. 7925 1451 151 7925 1451 152 There were some cases where the results of the combination 7925 1451 153 procedure were not smooth for the gold capture cross section. 7925 1451 154 There were some models that could provide insight on how to 7925 1451 155 define the curves. It was determined that a simple smoothing 7925 1451 156 algorithm was satisfactory. It was used sparingly for this 7925 1451 157 cross section based on the models and inter-comparisons of 7925 1451 158 cross sections. 7925 1451 159 7925 1451 160 The file represents a version for which only the reaction which 7925 1451 161 is used as standard is given. Actually due to the evaluation 7925 1451 162 methodology, the full covariance matrix of the data uncertainty 7925 1451 163 includes other blocks describing cross-reaction and cross- 7925 1451 164 material correlations. Data are given for a neutron energy range 7925 1451 165 wider than that recommended for its use as a standard for this 7925 1451 166 reaction (0.0253 eV and 0.2 - 2.5 MeV). Recommended values and 7925 1451 167 uncertainties representing only the diagonal elements of 7925 1451 168 covariance matrix are shown below: 7925 1451 169 7925 1451 170 Standard Reaction: 197Au(n,g), MT=102 7925 1451 171 The values are point values except from the interval (2.0 keV 7925 1451 172 to 3.0 keV), labelled 0.2500E-02 MeV; to the interval (10 keV 7925 1451 173 to 20 keV), labelled 0.1500E-01 MeV where the cross section values7925 1451 174 are the average cross sections at the center energies for the 7925 1451 175 intervals. 7925 1451 176 7925 1451 177 Neutron Cross Uncertainty Uncertainty 7925 1451 178 energy section (barn) (%) 7925 1451 179 (MeV) (barn) 7925 1451 180 0.2530E-07 98.65931850 0.13853593 0.1404 7925 1451 181 0.2500E-02 3.15813647 0.56433337 17.869 7925 1451 182 0.3500E-02 2.58099387 0.05417321 2.0989 7925 1451 183 0.4500E-02 2.28545555 0.05092097 2.2280 7925 1451 184 0.5500E-02 1.90967660 0.02781642 1.4566 7925 1451 185 0.6500E-02 1.72519776 0.02585512 1.4987 7925 1451 186 0.7500E-02 1.52205940 0.02173001 1.4277 7925 1451 187 0.8500E-02 1.33195364 0.02041558 1.5328 7925 1451 188 0.9500E-02 1.25023425 0.02072775 1.6579 7925 1451 189 0.1500E-01 0.88529574 0.00970831 1.0966 7925 1451 190 0.2000E-01 0.70081240 0.00902308 1.2875 7925 1451 191 0.2400E-01 0.64382957 0.00540716 0.8398 7925 1451 192 0.3000E-01 0.59238902 0.00413067 0.6973 7925 1451 193 0.4500E-01 0.46392815 0.00413582 0.8915 7925 1451 194 0.5500E-01 0.42275736 0.00398988 0.9438 7925 1451 195 0.6500E-01 0.38811248 0.00362727 0.9346 7925 1451 196 0.7500E-01 0.36514890 0.00348115 0.9534 7925 1451 197 0.8500E-01 0.33554849* 0.00324783 0.9679 7925 1451 198 0.9500E-01 0.32262758* 0.00309887 0.9605 7925 1451 199 0.1000E+00 0.31991428* 0.00332756 1.0401 7925 1451 200 0.1200E+00 0.29459216 0.00281541 0.9557 7925 1451 201 0.1500E+00 0.27529696 0.00272810 0.9910 7925 1451 202 0.1700E+00 0.26543616 0.00302669 1.1403 7925 1451 203 0.1800E+00 0.26314860 0.00604501 2.2972 7925 1451 204 0.1900E+00 0.25661976 0.00347051 1.3524 7925 1451 205 0.2000E+00 0.25308706 0.00354077 1.3990 7925 1451 206 0.2100E+00 0.24866585 0.00320738 1.2898 7925 1451 207 0.2200E+00 0.24694665 0.00324611 1.3145 7925 1451 208 0.2300E+00 0.24385967 0.00384182 1.5754 7925 1451 209 0.2350E+00 0.23884975* 0.00309955 1.2977 7925 1451 210 0.2400E+00 0.23590450* 0.00421702 1.7876 7925 1451 211 0.2450E+00 0.23702947* 0.00307322 1.2966 7925 1451 212 0.2500E+00 0.23665657* 0.00321681 1.3593 7925 1451 213 0.2600E+00 0.23623140 0.00309654 1.3108 7925 1451 214 0.2700E+00 0.23123289 0.00377872 1.6342 7925 1451 215 0.2800E+00 0.21735446 0.00279851 1.2875 7925 1451 216 0.3000E+00 0.19819990* 0.00221346 1.1168 7925 1451 217 0.3250E+00 0.18852183* 0.00221745 1.1762 7925 1451 218 0.3500E+00 0.17865817 0.00190327 1.0653 7925 1451 219 0.3750E+00 0.16924827 0.00177038 1.0460 7925 1451 220 0.4000E+00 0.16250629 0.00167639 1.0316 7925 1451 221 0.4250E+00 0.15518777 0.00183231 1.1807 7925 1451 222 0.4500E+00 0.14607597 0.00145481 0.9959 7925 1451 223 0.4750E+00 0.14151087* 0.00147474 1.0421 7925 1451 224 0.5000E+00 0.13704216* 0.00148234 1.0817 7925 1451 225 0.5200E+00 0.13011856* 0.00140243 1.0778 7925 1451 226 0.5400E+00 0.12467839 0.00146966 1.1788 7925 1451 227 0.5700E+00 0.11978376 0.00180842 1.5097 7925 1451 228 0.6000E+00 0.10952793 0.00118278 1.0799 7925 1451 229 0.6500E+00 0.09977657 0.00126033 1.2632 7925 1451 230 0.7000E+00 0.09596536 0.00108257 1.1281 7925 1451 231 0.7500E+00 0.09431097 0.00122320 1.2970 7925 1451 232 0.8000E+00 0.08864401 0.00092882 1.0478 7925 1451 233 0.8500E+00 0.08524062 0.00138647 1.6265 7925 1451 234 0.9000E+00 0.08449953* 0.00181715 2.1505 7925 1451 235 0.9400E+00 0.08539009* 0.00166777 1.9531 7925 1451 236 0.9600E+00 0.08511002 0.00361199 4.2439 7925 1451 237 0.9800E+00 0.08581323 0.00272686 3.1777 7925 1451 238 0.1000E+01 0.07979908 0.00083047 1.0407 7925 1451 239 0.1100E+01 0.07815919 0.00108799 1.3920 7925 1451 240 0.1250E+01 0.07361931 0.00092932 1.2623 7925 1451 241 0.1400E+01 0.07102221 0.00122496 1.7248 7925 1451 242 0.1600E+01 0.06808586 0.00102782 1.5096 7925 1451 243 0.1800E+01 0.06019876 0.00122788 2.0397 7925 1451 244 0.2000E+01 0.05297658 0.00086598 1.6346 7925 1451 245 0.2200E+01 0.04407293 0.00082283 1.8670 7925 1451 246 0.2400E+01 0.03650792 0.00081764 2.2396 7925 1451 247 0.2600E+01 0.03197786 0.00071000 2.2203 7925 1451 248 0.2800E+01 0.02585768 0.00052952 2.0478 7925 1451 249 * - smoothed cross sections 7925 1451 250 7925 1451 251 The covariance matrix of uncertainties given in MF=33, MT=18 is 7925 1451 252 a positive definite matrix with the eigenvalues: 7925 1451 253 0.19718E-05 0.23992E-04 0.26449E-04 0.33300E-04 0.35104E-04 7925 1451 254 0.37959E-04 0.40070E-04 0.42644E-04 0.44970E-04 0.46128E-04 7925 1451 255 0.48660E-04 0.49823E-04 0.53090E-04 0.54218E-04 0.54370E-04 7925 1451 256 0.55654E-04 0.56113E-04 0.60723E-04 0.63094E-04 0.64998E-04 7925 1451 257 0.66186E-04 0.69505E-04 0.71646E-04 0.73053E-04 0.73594E-04 7925 1451 258 0.84115E-04 0.88284E-04 0.88943E-04 0.89911E-04 0.92635E-04 7925 1451 259 0.98737E-04 0.10098E-03 0.10254E-03 0.10448E-03 0.11250E-03 7925 1451 260 0.12305E-03 0.13797E-03 0.13859E-03 0.14336E-03 0.14386E-03 7925 1451 261 0.14563E-03 0.15463E-03 0.17106E-03 0.18157E-03 0.19022E-03 7925 1451 262 0.19936E-03 0.22038E-03 0.22506E-03 0.23752E-03 0.26023E-03 7925 1451 263 0.27208E-03 0.29053E-03 0.29352E-03 0.31439E-03 0.32186E-03 7925 1451 264 0.33443E-03 0.34953E-03 0.36618E-03 0.40655E-03 0.41121E-03 7925 1451 265 0.43923E-03 0.50656E-03 0.51582E-03 0.67147E-03 0.83397E-03 7925 1451 266 0.10660E-02 0.16781E-02 0.20377E-02 0.32202E-01 7925 1451 267 7925 1451 268 References 7925 1451 269 1. V.G. Pronyaev, S.A. Badikov, Chen Zhenpeng, A.D. Carlson, 7925 1451 270 E.V. Gai, G.M. Hale, F.-J. Hambsch, H.M. Hofmann, N.M. Larson, 7925 1451 271 D.L. Smith, Soo-Youl Oh, S. Tagesen, H. Vonach, International 7925 1451 272 Conference on Nuclear Data for Science and Technology, 7925 1451 273 Santa Fe, NM, USA, 26 September - 1 October 2004, AIP Conference 7925 1451 274 Proceedings, 769, Part 1, p. 808 (2005). 7925 1451 275 2. An International Evaluation of the Neutron Cross Section 7925 1451 276 Standards, to be published as an IAEA technical report series. 7925 1451 277 3. W. P. Poenitz, "Data Interpretation, Objective, Evaluation 7925 1451 278 Procedures and Mathematical Technique for the Evaluation 7925 1451 279 of Energy-Dependent Ratio, Shape and Cross Section Data, 7925 1451 280 "Proceedings of the Conference on Nuclear Data 7925 1451 281 Evaluation Methods and Procedures, BNL-NCS-51363, 7925 1451 282 Vol. I, 249 (1981). 7925 1451 283 4. G. M. Hale, "Use of R-Matrix Methods for Light Element 7925 1451 284 Evaluations, "Proceedings of the Conference on Nuclear 7925 1451 285 Data Evaluation Methods and Procedures, BNL-NCS- 7925 1451 286 51363, Vol. II, 509 (1981). 7925 1451 287 5. Z. P. Chen, "Reduced R-Matrix Analysis for 17O System," 7925 1451 288 Atomic Energy Science and Technology, Vol. 29, No. 4, 7925 1451 289 366 (1995). 7925 1451 290 6. F. -J. Hambsch, A. D. Carlson, H. Vonach, "Status of the 7925 1451 291 Neutron Cross Section Standards Database, "Proc. Int. 7925 1451 292 Conf. on Nuclear Data for Science and Technology, Sept. 7925 1451 293 26-Oct. 1, 2004, Santa Fe, USA, AIP Conf. Proc. Vol. 769, 7925 1451 294 826 (2005). 7925 1451 295 7. A. D. Carlson, G. M. Hale, V. G. Pronyaev, "Summary 7925 1451 296 Report of the First Research Coordination Meeting on 7925 1451 297 Improvement of the Standard Cross Sections for Light 7925 1451 298 Elements, "INDC(NDS)-438, IAEA, (2003). 7925 1451 299 8. S. Chiba, D. L. Smith, "A Suggested procedure for 7925 1451 300 Resolving an Anomaly in Least- Squares Data Analysis 7925 1451 301 Known as "Peelle's Pertinent Puzzle" and the General 7925 1451 302 Implications for Nuclear Data Evaluation, "ANL/NDM- 7925 1451 303 121 , (1991). 7925 1451 304 9. E. J. Axton, "Evaluation of the Thermal Constants of 233U, 7925 1451 305 235U, 239Pu and 241Pu, and the Fission Neutron Yield of 7925 1451 306 252Cf, "CBNM (IRMM) Report GE/PH/01/86, (1986). 7925 1451 307 7925 1451 308 ****************************** CONTENTS **************************7925 1451 309 1 451 312 07925 1451 310 3 102 26 07925 1451 311 33 102 418 07925 1451 312 0.000000+0 0.000000+0 0 0 0 07925 1 099999 0.000000+0 0.000000+0 0 0 0 07925 0 0 0 7.919700+4 1.952740+2 0 0 0 07925 3102 1 6.512380+6 6.512380+6 0 0 1 697925 3102 2 69 5 7925 3102 3 2.530000-2 9.865900+1 2.500000+3 3.158100+0 3.500000+3 2.581000+07925 3102 4 4.500000+3 2.285500+0 5.500000+3 1.909700+0 6.500000+3 1.725200+07925 3102 5 7.500000+3 1.522100+0 8.500000+3 1.332000+0 9.500000+3 1.250200+07925 3102 6 1.500000+4 8.853000-1 2.000000+4 7.008100-1 2.400000+4 6.438300-17925 3102 7 3.000000+4 5.923900-1 4.500000+4 4.639300-1 5.500000+4 4.227600-17925 3102 8 6.500000+4 3.881100-1 7.500000+4 3.651500-1 8.500000+4 3.355485-17925 3102 9 9.500000+4 3.226276-1 1.000000+5 3.199143-1 1.200000+5 2.945900-17925 3102 10 1.500000+5 2.753000-1 1.700000+5 2.654400-1 1.800000+5 2.631500-17925 3102 11 1.900000+5 2.566200-1 2.000000+5 2.530900-1 2.100000+5 2.486700-17925 3102 12 2.200000+5 2.469500-1 2.300000+5 2.438600-1 2.350000+5 2.388498-17925 3102 13 2.400000+5 2.359045-1 2.450000+5 2.370295-1 2.500000+5 2.366566-17925 3102 14 2.600000+5 2.362300-1 2.700000+5 2.312300-1 2.800000+5 2.173500-17925 3102 15 3.000000+5 1.981999-1 3.250000+5 1.885218-1 3.500000+5 1.786600-17925 3102 16 3.750000+5 1.692500-1 4.000000+5 1.625100-1 4.250000+5 1.551900-17925 3102 17 4.500000+5 1.460800-1 4.750000+5 1.415109-1 5.000000+5 1.370422-17925 3102 18 5.200000+5 1.301186-1 5.400000+5 1.246800-1 5.700000+5 1.197800-17925 3102 19 6.000000+5 1.095300-1 6.500000+5 9.977700-2 7.000000+5 9.596500-27925 3102 20 7.500000+5 9.431100-2 8.000000+5 8.864400-2 8.500000+5 8.524100-27925 3102 21 9.000000+5 8.449953-2 9.400000+5 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