NEUTRON REACTION STANDARD PREPARED BY THE IAEA CRP 3 OCTOBER 2005 1 0 0 0 9.223501+4 2.330250+2 0 0 0 09228 1451 1 0.0 0.0 0 0 0 69228 1451 2 1.000000+0 2.000000+8 1 0 10 09228 1451 3 0.0 0.0 1 0 383 49228 1451 4 92- U-235 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 9228 1451 5 DIST- 9228 1451 6 ----ENDF/B-VII MATERIAL 9228 9228 1451 7 -----INCIDENT NEUTRON DATA, NEUTRON REACTION STANDARD 9228 1451 8 ------ENDF-6 FORMAT 9228 1451 9 9228 1451 10 *****************************************************************9228 1451 11 9228 1451 12 The evaluation was done in the framework of an IAEA (Vienna, 9228 1451 13 Austria) Coordinated Research Project "On Improvement of the 9228 1451 14 Standard Cross Sections for Light Elements" with contributions by 9228 1451 15 the NEA (Paris,France) WPEC Subgroup 7 on Nuclear Data Standards 9228 1451 16 and the CSEWG (USA). 9228 1451 17 Participants of the Project: 9228 1451 18 Sergei A. Badikov, Institute of Physics and Power Engineering, 9228 1451 19 Russia 9228 1451 20 Chen Zhenpeng, Tsinghua University, China 9228 1451 21 Allan D. Carlson, National Institute of Standards and Technology, 9228 1451 22 USA 9228 1451 23 Evgeny V. Gai, Institute of Physics and Power Engineering, 9228 1451 24 Russia 9228 1451 25 Gerald M. Hale, Los Alamos National Laboratory, USA 9228 1451 26 Franz-Josef Hambsch, Institute for Reference Materials and 9228 1451 27 Measurements, Belgium 9228 1451 28 Hartmut M. Hofmann, Universitat Erlangen-Nurnberg, Germany 9228 1451 29 Nancy M. Larson, Oak Ridge National Laboratory, USA 9228 1451 30 Donald L. Smith, Argonne National Laboratory, USA 9228 1451 31 Soo-Youl Oh, Korea Atomic Energy Research Institute, 9228 1451 32 Republic of Korea 9228 1451 33 Siegfried Tagesen, Institute for Isotopenforschung and 9228 1451 34 Kernphysik der Universitat Wien, Austria 9228 1451 35 Herbert Vonach, Institute for Isotopenforschung and 9228 1451 36 Kernphysik der Universitat Wien, Austria 9228 1451 37 Vladimir G. Pronyaev, International Atomic Energy Agency, 9228 1451 38 Austria 9228 1451 39 9228 1451 40 The evaluation methodology and the preliminary results are given 9228 1451 41 in [1]. A detailed description and the final results will be 9228 1451 42 published by the IAEA in an IAEA-TECDOC series report [2]. 9228 1451 43 9228 1451 44 The file presents a version for which only the reaction which 9228 1451 45 is used as a standard is given. Actually due to the methodology 9228 1451 46 of the evaluation, the full covariance matrix of the data 9228 1451 47 uncertainty includes other blocks describing cross-reaction and 9228 1451 48 cross-material correlations. Data are given for a neutron energy 9228 1451 49 range wider than that recommended for its use as a standard for 9228 1451 50 this reaction (thermal and 0.15 - 200 MeV). Recommended values 9228 1451 51 and uncertainties representing only diagonal elements of the 9228 1451 52 covariance matrix are shown below: 9228 1451 53 Standard Reaction: 235U(n,f) 9228 1451 54