Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor

Graphite is an often-used moderating material on the basis of its good moderating power and very low absorption cross section. This small absorption cross section permits the use of natural or low-enriched uranium in graphite moderated reactors. Graphite is now being considered as the moderator for...

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Bibliographic Details
Main Authors: Košťál, Michal, Rypar, Vojtěch, Milčák, Ján, Juříček, Vlastimil, Losa, Evžen, Harper, Sterling, Forget, Benoit Robert Yves
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Format: Article
Published: Elsevier 2018
Online Access:http://hdl.handle.net/1721.1/113212
https://orcid.org/0000-0003-1459-7672