The very-high-temperature reactor, or VHTR, is a proposed Generation IV development of the high-temperature gas-cooled reactor. It uses a graphite-moderated core with a once-through uranium fuel cycle, cooled by helium or molten salt, and is designed to reach core-exit temperatures of approximately 1,000 degrees Celsius, higher than the 700 to 950 degree range of existing high-temperature gas-cooled reactors. This higher temperature capability opens additional applications such as hydrogen production and industrial process heat that are not as feasible with conventional high-temperature gas-cooled reactor designs.
Facts
Partially Attested
Technology TypeGeneration IV nuclear reactor 1 Quote is from the Wikipedia article on the related High-temperature gas-cooled reactor, HTGR, whose own Wikidata entry lists very-high-temperature reactor as a different item, no dedicated VHTR article exists Classification
MaturityTRL 6: Technology Demonstrated in Relevant Environment 1 Connections
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Source High-temperature gas-cooled reactor - Wikipedia
Sources
1. High-temperature gas-cooled reactor - Wikipedia
Body text, VHTR definition sentence
the Generation IV very-high-temperature reactor (VHTR)
Uses Source: Uranium, Wikipedia article lead
is a type of gas-cooled nuclear reactor which uses uranium fuel and graphite moderation to produce very high reactor core output
In Group: Gas-Cooled Reactors, Lead
A high-temperature gas-cooled reactor (HTGR) is a type of gas-cooled nuclear reactor which uses uranium fuel and graphite moderation to produce very high reactor core output temperatures. (700 to 950 °C) All existing HTGR reactors use helium coolant.
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