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                                       Details for article 33 of 50 found articles
 
 
  Neutronics and thermal hydraulics analysis of a low-enriched uranium cermet fuel core for a Mars surface power reactor
 
 
Title: Neutronics and thermal hydraulics analysis of a low-enriched uranium cermet fuel core for a Mars surface power reactor
Author: Schillo, Kevin J.
Kumar, Akansha
Harris, Kurt E.
Hew, Yayu M.
Howe, Steven D.
Appeared in: Annals of nuclear energy
Paging: Volume 96 (2016) nr. C pages 307-312
Year: 2016
Contents:
Publisher: Elsevier Ltd
Source file: Elektronische Wetenschappelijke Tijdschriften
 
 

                             Details for article 33 of 50 found articles
 
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