دانلود کتاب ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

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Lawrenсe Livermore National Laboratory, US, UCRL-JRNL-225066, 2006, 125 pp.We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions.
The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, 6Li, 10B, Au and for 236 238tj fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases.Contents
Introduction
Overview of the Library
Neutron Reaction Sublibrary
Thermal Neutron Scattering Sublibrary
Neutron Cross Section Standards Sublibrary
Photonuclear Reaction Sublibrary
Charged Particle Reaction Sublibraries
Decay Data Sublibrary
Other Sublibraries
Validation
Conclusions and Future Work
Acknowledgments
References