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Verification of Unstructured Mesh Capabilities in MCNP6 for Reactor Physics Problems
Author(s) -
Timothy Burke,
Roger Martz,
Brian C. Kiedrowski,
William R. Martin
Publication year - 2012
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/1049351
Subject(s) - benchmark (surveying) , solver , criticality , computer science , nuclear engineering , mox fuel , computational science , physics , engineering , nuclear physics , geology , uranium , geodesy , programming language

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