NEUTRON REACTION STANDARD PREPARED BY THE IAEA CRP 3 OCTOBER 2005 1 0 0 0 9.423900+4 2.369986+2 0 0 0 09437 1451 1 0.0 0.0 0 0 0 69437 1451 2 1.000000+0 2.000000+8 1 0 10 09437 1451 3 0.0 0.0 1 0 379 39437 1451 4 94-PU-239 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 9437 1451 5 DIST- 9437 1451 6 ----ENDF/B-VII MATERIAL 9437 9437 1451 7 -----INCIDENT NEUTRON DATA, NEUTRON REACTION STANDARD 9437 1451 8 ------ENDF-6 FORMAT 9437 1451 9 9437 1451 10 *****************************************************************9437 1451 11 9437 1451 12 The evaluation was done in the framework of the IAEA (Vienna, 9437 1451 13 Austria) Coordinated Research Project "On Improvement of the 9437 1451 14 Standard Cross Sections for Light Elements" with contributions 9437 1451 15 by the NEA (Paris,France) WPEC Subgroup 7 on Nuclear Data 9437 1451 16 Standards and the CSEWG (USA). 9437 1451 17 Participants of the Project: 9437 1451 18 Sergei A. Badikov, Institute of Physics and Power Engineering, 9437 1451 19 Russia 9437 1451 20 Chen Zhenpeng, Tsinghua University, China 9437 1451 21 Allan D. Carlson, National Institute of Standards and Technology, 9437 1451 22 USA 9437 1451 23 Evgeny V. Gai, Institute of Physics and Power Engineering, 9437 1451 24 Russia 9437 1451 25 Gerald M. Hale, Los Alamos National Laboratory, USA 9437 1451 26 Franz-Josef Hambsch, Institute for Reference Materials and 9437 1451 27 Measurements, Belgium 9437 1451 28 Hartmut M. Hofmann, Universitat Erlangen-Nurnberg, Germany 9437 1451 29 Nancy M. Larson, Oak Ridge National Laboratory, USA 9437 1451 30 Donald L. Smith, Argonne National Laboratory, USA 9437 1451 31 Soo-Youl Oh, Korea Atomic Energy Research Institute, 9437 1451 32 Republic of Korea 9437 1451 33 Siegfried Tagesen, Institute for Isotopenforschung and 9437 1451 34 Kernphysik der Universitat Wien, Austria 9437 1451 35 Herbert Vonach, Institute for Isotopenforschung and 9437 1451 36 Kernphysik der Universitat Wien, Austria 9437 1451 37 Vladimir G. Pronyaev, International Atomic Energy Agency, 9437 1451 38 Austria 9437 1451 39 9437 1451 40 The evaluation methodology and the preliminary results are given 9437 1451 41 in [1]. A detailed description and the final results will be 9437 1451 42 published by the IAEA as an IAEA-TECDOC series report [2]. 9437 1451 43 9437 1451 44 The file represents a reaction which was used in the fit of the 9437 1451 45 standards. Actually due to the evaluation methodology the full 9437 1451 46 covariance matrix of data uncertainty includes other blocks 9437 1451 47 describing cross-reaction and cross-material correlations. 9437 1451 48 Recommended values and uncertainties representing only diagonal 9437 1451 49 elements of the covariance matrix are shown below: 9437 1451 50 9437 1451 51 Reaction: 239Pu(n,f) 9437 1451 52