NEUTRON REACTION STANDARD PREPARED BY THE IAEA CRP 3 OCTOBER 2005 1 0 0 0 5.010000+3 9.926921+0 0 0 0 0 525 1451 1 0.000000+0 0.000000+0 0 0 0 6 525 1451 2 1.000000+0 1.000000+6 1 0 10 0 525 1451 3 0.000000+0 0.000000+0 0 0 322 7 525 1451 4 5- B -10 IAEA EVAL-SEP05 IAEA-CRP&NEA-WPEC(SG7)&CSEWG 525 1451 5 DIST- 525 1451 6 ----ENDF/B-VII MATERIAL 525 525 1451 7 -----INCIDENT NEUTRON DATA, NEUTRON REACTION STANDARD 525 1451 8 ------ENDF-6 FORMAT 525 1451 9 525 1451 10 ***************************************************************** 525 1451 11 525 1451 12 The evaluation was done in the framework of an IAEA(Vienna, 525 1451 13 Austria) Coordinated Research Project "On Improvement of the 525 1451 14 Standard Cross Sections for Light Elements" with contributions by 525 1451 15 the NEA (Paris,France) WPEC Subgroup 7 on Nuclear Data Standards 525 1451 16 and the CSEWG(USA). 525 1451 17 Participants of the Project: 525 1451 18 Sergei A. Badikov, Institute of Physics and Power Engineering, 525 1451 19 Russia 525 1451 20 Chen Zhenpeng, Tsinghua University, China 525 1451 21 Allan D. Carlson, National Institute of Standards and Technology, 525 1451 22 USA 525 1451 23 Evgeny V. Gai, Institute of Physics and Power Engineering, 525 1451 24 Russia 525 1451 25 Gerald M. Hale, Los Alamos National Laboratory, USA 525 1451 26 Franz-Josef Hambsch, Institute for Reference Materials and 525 1451 27 Measurements, Belgium 525 1451 28 Hartmut M. Hofmann, Universitat Erlangen-Nurnberg, Germany 525 1451 29 Nancy M. Larson, Oak Ridge National Laboratory, USA 525 1451 30 Donald L. Smith, Argonne National Laboratory, USA 525 1451 31 Soo-Youl Oh, Korea Atomic Energy Research Institute, 525 1451 32 Republic of Korea 525 1451 33 Siegfried Tagesen, Institute for Isotopenforschung and 525 1451 34 Kernphysik der Universitat Wien, Austria 525 1451 35 Herbert Vonach, Institute for Isotopenforschung and 525 1451 36 Kernphysik der Universitat Wien, Austria 525 1451 37 Vladimir G. Pronyaev, International Atomic Energy Agency, 525 1451 38 Austria 525 1451 39 525 1451 40 The methodology of the evaluation and the preliminary results are 525 1451 41 reported in [1]. A detailed description and the final results 525 1451 42 will be published as an IAEA-TECDOC series report [2]. 525 1451 43 525 1451 44 The file represents a version for which only reactions which 525 1451 45 are used as standards are given. Actually due to the evaluation 525 1451 46 methodology, the full covariance matrix of the data uncertainty 525 1451 47 includes other blocks describing cross-reaction and cross-material 525 1451 48 correlations. Data are given for a neutron energy range wider 525 1451 49 than that recommended for its use as a standard for this reaction 525 1451 50 (thermal - 1000 keV). Recommended values and uncertainties 525 1451 51 representing only diagonal elements of the covariance matrix are 525 1451 52 shown below: 525 1451 53 525 1451 54 Reaction 10B(n,a0) 525 1451 55