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in subjects: "Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety"  
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Computational features of the CACECO containment analysis code. [LMFBR]

Description: A code, CACECO, has been written to assist in the analysis of containment situations peculiar to sodium cooled reactors. Typically, these situations involve relatively slow energy release processes and chemical reaction heat. Two examples are given to illustrate some of the code's features. These particular cases illustrate the potential for hydrogen formation in the containment building, but show that time is available to take corrective action. The code is suitable for other problems involvin… more
Date: May 29, 1975
Creator: Peak, R. D. & Stepnewski, D. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fuel Coolant Thermal Interaction Project. Quarterly progress report No. 1, July 1, 1975--September 30, 1975. [LMFBR]

Description: The objective of the work reported is to experimentally and analytically study the dominant mechanism in fuel--coolant thermal interactions which could lead to vapor explosions. The exploration of mechanisms is focused in two areas: (a) mechanisms responsible for fragmentation in molten metal droplet experiments (including assessment of the validity of the proposed spontaneous nucleation mechanism), and (b) thermal stress initiated fracture as a fragmentation mechanism. Work being performed in … more
Date: November 19, 1975
Creator: Todreas, N. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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