The ENDF/B-VII.0 library, released in December 2006 by the U.S. Cross Section Evaluation Working Group (CSEWG), represents the next generation of evaluated nuclear data for advanced nuclear science and technology applications. This library, which contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes, is based on both experimental data and nuclear reaction theory predictions. Key advancements over the previous ENDF/B-VI library include: 1. New cross sections for actinide isotopes (U, Pu, Th, Np, Am) with improved performance in criticality and neutron transmission benchmark tests. 2. More precise standard cross sections for neutron reactions on H, ^6Li, ^10B, Au, and fission of ^235,238U, developed through a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC). 3. Improved thermal neutron scattering data. 4. Extensive set of neutron cross sections on fission products. 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. 10. New methods for providing uncertainties and covariances, including covariance evaluations for some sample cases. The library consists of 14 sublibraries in the ENDF-6 format, with extensive validation using radiation transport codes to simulate measured critical assemblies. The validation results show significant improvements, including better agreement with low enriched U thermal assemblies, removal of reflector biases in fast systems, and more accurate predictions of intermediate spectrum critical assemblies. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory and is available for download from their web server.The ENDF/B-VII.0 library, released in December 2006 by the U.S. Cross Section Evaluation Working Group (CSEWG), represents the next generation of evaluated nuclear data for advanced nuclear science and technology applications. This library, which contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes, is based on both experimental data and nuclear reaction theory predictions. Key advancements over the previous ENDF/B-VI library include: 1. New cross sections for actinide isotopes (U, Pu, Th, Np, Am) with improved performance in criticality and neutron transmission benchmark tests. 2. More precise standard cross sections for neutron reactions on H, ^6Li, ^10B, Au, and fission of ^235,238U, developed through a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC). 3. Improved thermal neutron scattering data. 4. Extensive set of neutron cross sections on fission products. 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. 10. New methods for providing uncertainties and covariances, including covariance evaluations for some sample cases. The library consists of 14 sublibraries in the ENDF-6 format, with extensive validation using radiation transport codes to simulate measured critical assemblies. The validation results show significant improvements, including better agreement with low enriched U thermal assemblies, removal of reflector biases in fast systems, and more accurate predictions of intermediate spectrum critical assemblies. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center (NNDC) at Brookhaven National Laboratory and is available for download from their web server.