Open AccessPreliminary survey of potential fast reactor control materials
Author(s) -
W.J. Gray
Publication year - 1973
Language(s) - English
Resource type - Reports
DOI - 10.2172/4444445
Subject(s) - conceptual design , component (thermodynamics) , inherent safety , control rod , grid , computer science , nuclear reactor core , nuclear engineering , duct (anatomy) , systems engineering , coolant , mechanical engineering , engineering , physics , medicine , geometry , mathematics , pathology , thermodynamics
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