(nucleonics) A prototype gas-cooled nuclear reactor in which the coolant is pressurized helium gas with an inlet temperature of about 325°C and an outlet temperature of about 750°C, and the fuel consists of fully enriched uranium and thorium. Abbreviated HTGR.
high-temperature gas-cooled reactor
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(′hī ′tem·prə·chər ¦gas ′küld rē′ak·tər)
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 | reactor cavity cooling system (nucleonics) |
| Nuclear power (nuclear engineering) |
| Nuclear reactor (nuclear engineering) |
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Mentioned in
- reactor cavity cooling system (nucleonics)
- Nuclear power (nuclear engineering)
- Nuclear reactor (nuclear engineering)
- Gas cooled reactor types
