ARRC: A random ray neutron transport code for nuclear reactor simulation

Tramm, John R.; Smith, Kord S.; Forget, Benoit; Siegel, Andrew R.

doi:10.1016/j.anucene.2017.10.015

Title: ARRC: A random ray neutron transport code for nuclear reactor simulation

Journal Article · 01 February 2018 · Annals of Nuclear Energy

DOI: https://doi.org/10.1016/j.anucene.2017.10.015 · OSTI ID:1549043

Tramm, John R.; Smith, Kord S.;

; Siegel, Andrew R.

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Sponsoring Organization:: USDOE Office of Science (SC), Advanced Scientific Computing Research (ASCR)

Grant/Contract Number:: AC02-06CH11357

OSTI ID:: 1549043

Journal Information:: Annals of Nuclear Energy, Journal Name: Annals of Nuclear Energy Vol. 112 Journal Issue: C; ISSN 0306-4549

Publisher:: ElsevierCopyright Statement

Country of Publication:: United Kingdom

Language:: English

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Cited by: 7 works

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References (34)

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