ENDF/B-VII.1 nuclear data for science and technology; Cross sections, covariances, fission product yields and decay data

Chadwick, M. B.*; Herman, M.*; Obloinsk, P.*; Dunn, M. E.*; Danon, Y.*; Kahler, A. C.*; Smith, D. L.*; Pritychenko, B.*; Arbanas, G.*; Arcilla, R.*; Brewer, R.*; Brown, D. A.*; Capote, R.*; Carlson, A. D.*; Cho, Y. S.*; Derrien, H.*; Guber, K.*; Hale, G. M.*; Hoblit, S.*; Holloway, S.*; Johnson, T. D.*; Kawano, Toshihiko*; Kiedrowski, B. C.*; Kim, H.*; Kunieda, Satoshi  ; Larson, N. M.*; Leal, L.*; Lestone, J. P.*; Little, R. C.*; McCutchan, E. A.*; MacFarlane, R. E.*; MacInnes, M.*; Mattoon, C. M.*; McKnight, R. D.*; Mughabghab, S. F.*; Nobre, G. P. A.*; Palmiotti, G.*; Palumbo, A.*; Pigni, M. T.*; Pronyaev, V. G.*; Sayer, R. O.*; Sonzogni, A. A.*; Summers, N. C.*; Talou, P.*; Thompson, I. J.*; Trkov, A.*; Vogt, R. L.*; Van der Marck, S. C.*; Wallner, A.*; White, M. C.*; Wiarda, D.*; Young, P. G.*

The ENDF/B-VII.1 library is our latest recommended evaluated nuclear data file for use in nuclear science and technology applications, and incorporates advances made in the five years since the release of ENDF/B-VII.0. These advances focus on neutron cross sections, covariances, fission product yields and decay data, and represent work by the US Cross Section Evaluation Working Group (CSEWG) in nuclear data evaluation that utilizes developments in nuclear theory, modeling, simulation, and experiment. It features extension of covered nuclei, covariance data for 190 nuclei, R-matrix analyses of neutron reactions on light nuclei, updates for some medium-heavy and actinoid nuclei, etc. Criticality benchmark tests with a transport simulation code MCNP shows improved performances.