high-temperature gas-cooled reactor

high-temperature gas-cooled reactor

[′hī ‚tem·prə·chər ¦gas ‚küld rē′ak·tər]
(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.
References in periodicals archive ?
The fuel elements in a High-temperature Gas-cooled Reactor design are composed of tennis ball-sized spheres of uranium oxide encased in graphite.
Drawing on the small operating HTR-10 research reactor at the Institute of Nuclear and New Energy Technology of Tsinghua University, Chinergy is a new entity tasked with building the world's first commercial, modular high-temperature gas-cooled reactor.
While at Gulf General Atomic, he oversaw the design and testing of commercial high-temperature gas-cooled reactors.

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