Open AccessFAST FLUX TEST FACILITY. CONCEPTUAL COMPONENT DESIGN DESCRIPTION FOR THE REACTOR VESSEL AND SHIELD COMPONENT NO. 32.
Author(s) -
D.P. Schively
Publication year - 1969
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4155427
Subject(s) - conceptual design , component (thermodynamics) , systems engineering , shield , nuclear engineering , grid , nuclear reactor core , control rod , computer science , coolant , engineering , mechanical engineering , reliability engineering , physics , geology , petrology , thermodynamics , geodesy
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