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Journal Articles

The CIELO Collaboration; Neutron reactions on $$^1$$H, $$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U, and $$^{239}$$Pu

Chadwick, M. B.*; Dupont, E.*; Bauge, E.*; Blokhin, A.*; Bouland, O.*; Brown, D. A.*; Capote, R.*; Carlson, A. D.*; Danon, Y.*; De Saint Jean, C.*; et al.

Nuclear Data Sheets, 118, p.1 - 25, 2014/04

 Times Cited Count:105 Percentile:98.52(Physics, Nuclear)

CIELO (Collaborative International Evaluated Library Organization) provides a new working paradigm to facilitate evaluated nuclear reaction data advances. It brings together experts from across the international nuclear reaction data community to identify and document discrepancies among existing evaluated data libraries, measured data, and model calculation interpretations, and aims to make progress in reconciling these discrepancies to create more accurate ENDF-formatted files. The focus will initially be on a small number of the highest-priority isotopes, namely $$^{1}$$H, $$^{16}$$O, $$^{56}$$Fe, $$^{235,238}$$U, and $$^{239}$$Pu. This paper identifies discrepancies between various evaluations of the highest priority isotopes. The evaluated data for these materials in the existing nuclear data libraries are reviewed, and some integral properties are given. The paper summarizes a program of nuclear science and computational work needed to create the new CIELO nuclear data evaluations.

Journal Articles

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

Chadwick, M. B.*; Herman, M.*; Oblo$v{z}$insk$'y$, P.*; Dunn, M. E.*; Danon, Y.*; Kahler, A. C.*; Smith, D. L.*; Pritychenko, B.*; Arbanas, G.*; Arcilla, R.*; et al.

Nuclear Data Sheets, 112(12), p.2887 - 2996, 2011/12

 Times Cited Count:1934 Percentile:100(Physics, Nuclear)

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.

Journal Articles

Neutron cross-section evaluations for $$^{70,72,73,74,76}$$Ge

Iwamoto, Osamu; Herman, M.*; Mughabghab, S. F.*; Oblozinsk$'y$, P.*; Trkov, A.*

AIP Conference Proceedings 769, p.434 - 437, 2005/05

Entirely new evaluations for all the Ge isotopes, from thermal energy to 20 MeV, has been performed with focus on photon production. In the resonance region, parameters were improved considerably compared to earlier evaluations. In the fast region, code EMPIRE-2.19 was used. Validation was done against photon data on Fe and Nb. Isotopic evaluations for Ge were summed up and compared with available measurements on natural Ge. Various quantities related to photon production, showing strong dependence on neutron incident energy, are discussed.

Journal Articles

Review of neutron cross-section evaluations for fission products

Oblozinsk$'y$, P.*; Herman, M.*; Mughabghab, S. F.*; Sirakov, I.*; Chang, J.*; Nakagawa, Tsuneo; Shibata, Keiichi; Kawai, Masayoshi*; Ignatyuk, A. V.*; Pronyaev, V. G.*; et al.

AIP Conference Proceedings 769, p.438 - 441, 2005/05

Review of neutron cross-section evaluations for fission products included in 5 major evaluated nuclear-data libralies was performed. The aim of the project, conducted under the WPEC Subgroup 21 during 2001-2004, was to prepare recommendations for best evaluations of nuclei in the range Z=1-68. Altogether, existing evaluations for 211 materials were reviewd, 7 new materials were added, and recommendations were prepared for 218 materials.

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