NEUTRON REACTION STANDARD PREPARED BY THE IAEA CRP 3 OCTOBER 2005 1 0 0 0 7.919700+4 1.952740+2 0 0 0 07925 1451 1 0.0 0.0 0 0 0 67925 1451 2 1.00000000 2800000.0 1 0 10 07925 1451 3 0.0 0.0 1 0 153 37925 1451 4 79-AU-197 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 7925 1451 5 DIST- 7925 1451 6 ----ENDF/B-VII MATERIAL 7925 7925 1451 7 -----INCIDENT NEUTRON DATA, NEUTRON REACTION STANDARD 7925 1451 8 ------ENDF-6 FORMAT 7925 1451 9 7925 1451 10 *****************************************************************7925 1451 11 7925 1451 12 The evaluation was done in the framework of an IAEA (Vienna, 7925 1451 13 Austria) Coordinated Research Project "On Improvement of the 7925 1451 14 Standard Cross Sections for Light Elements" with contributions by 7925 1451 15 the NEA (Paris, France) WPEC Subgroup 7 on Nuclear Data Standards 7925 1451 16 and the CSEWG (USA). 7925 1451 17 Participants of the Project: 7925 1451 18 Sergei A. Badikov, Institute of Physics and Power Engineering, 7925 1451 19 Russia 7925 1451 20 Chen Zhenpeng, Tsinghua University, China 7925 1451 21 Allan D. Carlson, National Institute of Standards and Technology, 7925 1451 22 USA 7925 1451 23 Evgeny V. Gai, Institute of Physics and Power Engineering, 7925 1451 24 Russia 7925 1451 25 Gerald M. Hale, Los Alamos National Laboratory, USA 7925 1451 26 Franz-Josef Hambsch, Institute for Reference Materials and 7925 1451 27 Measurements, Belgium 7925 1451 28 Hartmut M. Hofmann, Universitat Erlangen-Nurnberg, Germany 7925 1451 29 Nancy M. Larson, Oak Ridge National Laboratory, USA 7925 1451 30 Donald L. Smith, Argonne National Laboratory, USA 7925 1451 31 Soo-Youl Oh, Korea Atomic Energy Research Institute, 7925 1451 32 Republic of Korea 7925 1451 33 Siegfried Tagesen, Institute for Isotopenforschung and 7925 1451 34 Kernphysik der Universitat Wien, Austria 7925 1451 35 Herbert Vonach, Institute for Isotopenforschung and 7925 1451 36 Kernphysik der Universitat Wien, Austria 7925 1451 37 Vladimir G. Pronyaev, International Atomic Energy Agency, 7925 1451 38 Austria 7925 1451 39 7925 1451 40 The evaluation methodology and the preliminary results are given 7925 1451 41 in [1]. A detailed description and the final results will be 7925 1451 42 published by the IAEA as an IAEA-TECDOC series report [2]. 7925 1451 43 7925 1451 44 The file represents a version for which only the reaction which 7925 1451 45 is used as standard is given. Actually due to the evaluation 7925 1451 46 methodology, the full covariance matrix of the data uncertainty 7925 1451 47 includes other blocks describing cross-reaction and cross- 7925 1451 48 material correlations. Data are given for a neutron energy range 7925 1451 49 wider than that recommended for its use as a standard for this 7925 1451 50 reaction (0.2 - 2.5 MeV). Recommended values and uncertainties 7925 1451 51 representing only the diagonal elements of covariance matrix are 7925 1451 52 shown below: 7925 1451 53 Standard Reaction: 197Au(n,g), MT=102 7925 1451 54