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Burnette, R.D.; Hoot, C.G.
GA Technologies, Inc., San Diego, CA (USA)1983
GA Technologies, Inc., San Diego, CA (USA)1983
AbstractAbstract
[en] Graphite corrosion in the high-temperature gas-cooled reactor (HTGR) is calculated using two key assumptions: (1) the kinetic, catalysis, and transport characteristics of graphite determined by bench-scale tests apply to large components at reactor conditions and (2) the effects of high pressure and turbulent flow are predictable. To better understand the differences between laboratory tests and reactor conditions, a high-pressure test loop (HPTL) has been constructed and used to perform tests at reactor temperature, pressure, and flow conditions. The HPTL is intended to determine the functional dependence of oxidation rate and characteristics on total pressure and gas velocity and to compare the oxidation results with calculations using models and codes developed for the reactor
Original Title
HTGR
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Secondary Subject
Source
Apr 1983; 5 p; 16. American Carbon Society biennial conference; La Jolla, CA (USA); 17-22 Jul 1983; CONF-830711--4; Available from NTIS, PC A02/MF A01 as DE83011117
Record Type
Report
Literature Type
Conference
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