NEUTRON REACTION STANDARD PREPARED BY THE IAEA CRP 3 OCTOBER 2005 1 0 0 0 9.223800+4 2.360060+2 0 0 0 09237 1451 1 0.0 0.0 0 0 0 69237 1451 2 1.000000+0 2.000000+8 1 0 10 09237 1451 3 0.0 0.0 1 0 285 59237 1451 4 92- U-238 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 9237 1451 5 DIST- 9237 1451 6 ----ENDF/B-VII MATERIAL 9237 9237 1451 7 -----INCIDENT NEUTRON DATA, NEUTRON REACTION STANDARD 9237 1451 8 ------ENDF-6 FORMAT 9237 1451 9 9237 1451 10 *****************************************************************9237 1451 11 9237 1451 12 The evaluation was done in the framework of an IAEA (Vienna, 9237 1451 13 Austria) Coordinated Research Project "On Improvement of the 9237 1451 14 Standard Cross Sections for Light Elements" with contributions by 9237 1451 15 the NEA (Paris,France) WPEC Subgroup 7 on Nuclear Data Standards 9237 1451 16 and the CSEWG (USA). 9237 1451 17 Participants of the Project: 9237 1451 18 Sergei A. Badikov, Institute of Physics and Power Engineering, 9237 1451 19 Russia 9237 1451 20 Chen Zhenpeng, Tsinghua University, China 9237 1451 21 Allan D. Carlson, National Institute of Standards and Technology, 9237 1451 22 USA 9237 1451 23 Evgeny V. Gai, Institute of Physics and Power Engineering, 9237 1451 24 Russia 9237 1451 25 Gerald M. Hale, Los Alamos National Laboratory, USA 9237 1451 26 Franz-Josef Hambsch, Institute for Reference Materials and 9237 1451 27 Measurements, Belgium 9237 1451 28 Hartmut M. Hofmann, Universitat Erlangen-Nurnberg, Germany 9237 1451 29 Nancy M. Larson, Oak Ridge National Laboratory, USA 9237 1451 30 Donald L. Smith, Argonne National Laboratory, USA 9237 1451 31 Soo-Youl Oh, Korea Atomic Energy Research Institute, 9237 1451 32 Republic of Korea 9237 1451 33 Siegfried Tagesen, Institute for Isotopenforschung and 9237 1451 34 Kernphysik der Universitat Wien, Austria 9237 1451 35 Herbert Vonach, Institute for Isotopenforschung and 9237 1451 36 Kernphysik der Universitat Wien, Austria 9237 1451 37 Vladimir G. Pronyaev, International Atomic Energy Agency, 9237 1451 38 Austria 9237 1451 39 9237 1451 40 The methodology of the evaluation and the preliminary results are 9237 1451 41 reported in [1]. A detailed description and the final results 9237 1451 42 will be published by the IAEA as an IAEA-TECDOC series report [2] 9237 1451 43 9237 1451 44 The file presents a version for which the (n,f) reaction which is 9237 1451 45 used as standard and the (n,g) reaction which was used in the 9237 1451 46 evaluation of the standards, are given. Actually due to the 9237 1451 47 evaluation methodology, the full covariance matrix of data 9237 1451 48 uncertainty includes other blocks describing cross-reaction and 9237 1451 49 cross-material correlations. Data are given for a neutron energy 9237 1451 50 range wider than that recommended for its use as a standard for 9237 1451 51 the (n,f) reaction (2 MeV - 200 MeV). Recommended values and 9237 1451 52 uncertainties representing only diagonal elements of the 9237 1451 53 covariance matrix are shown below: 9237 1451 54 Standard Reaction: 238U(n,f) 9237 1451 55