Neutron Cross Section Processing Methods for Improved Integral Benchmarking of Unresolved Resonance Region Evaluations

Neutron Cross Section Processing Methods for Improved Integral Benchmarking of Unresolved Resonance Region Evaluations

In this work we describe the development and application of computational methods for processing neutron cross section data in the unresolved resonance region (URR). These methods are integrated with a continuous-energy Monte Carlo neutron transport code, thereby enabling their use in high-fidelity...

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Bibliographic Details
Main Authors: Brown, Forrest B., Walsh, Jonathan Alan, Forget, Benoit Robert Yves, Smith, Kord S.
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Article
Published: EDP Sciences 2018
Online Access:http://hdl.handle.net/1721.1/113297
https://orcid.org/0000-0002-2542-1149
https://orcid.org/0000-0003-1459-7672
https://orcid.org/0000-0003-2497-4312

Internet

http://hdl.handle.net/1721.1/113297
https://orcid.org/0000-0002-2542-1149
https://orcid.org/0000-0003-1459-7672
https://orcid.org/0000-0003-2497-4312

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