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Application and evaluation of ceramic materials in Tory reactor systems

Technical Report ·
DOI:https://doi.org/10.2172/4330581· OSTI ID:4330581
Declasslfied 28 Nov 1973. The Tory series of test reactors is intended to lead to a reactor capable of use as a ramjet power plant. Current designs are presented. Beryllium oxide is presently the only serious contender as the moderator. Analytical and experimental treatment of the thermal stress problem in BeO is discussed. There is a requirement that a ramjet reactor sustain very large forces caused by flow-induced pressure drop. Development of ceramic structural elements to sustain these forces is discussed. (8 references) (auth)
Research Organization:
California Univ., Livermore (USA). Lawrence Livermore Lab.
DOE Contract Number:
W-7405-ENG-48
NSA Number:
NSA-29-020161
OSTI ID:
4330581
Report Number(s):
UCRL--6238
Country of Publication:
United States
Language:
English

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