View source for High Temperature Gas-cooled Reactor

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[[Image:Vhtr ngnp sm.jpg|right|thumb|500px|VHTR schematic]]
A candidate for the [[U.S. Department of Energy]] [[Next Generation Nuclear Plant]] (NGNP), the '''Very-High-Temperature Reactor (VHTR)''' is a [[reactor moderator#graphite|graphite-moderated]], [[reactor coolant#helium|helium-cooled]] reactor with a once-through [[uranium]] fuel cycle. Its primary purpose is to provide high heat(850 to 950 degrees Celsius) to a variety of [[chemical engineering]] systems that require substantial heat energy, such as [[hydrogen]] generation or [[petrochemical]] production.  Electrical power generation is an optional and additional goal. supplies heat with high core outlet temperatures which enables applications such as [[hydrogen production]] or process heat for the petrochemical industry or others. <ref>{{citation
 | url = https://inlportal.inl.gov/portal/server.pt?open=514&objID=2251&parentname=CommunityPage&parentid=13&mode=2
 | publisher = [[Idaho National Laboratory]], [[U.S. Department of Energy]]
 | title = 	Very-High-Temperature Reactor (VHTR)}}</ref>

It is a relatively small reactor, seen as a nuclear-powered alternative to heating plants now located at industrial plants. Hydrogen generation is one of the major objectives, with hydrogen being seen as a petroleum alternative. Competitive reactors include the [[uranium hydride]] reactor by [[Hyperion]] Power Generation and the Chinese 200 MW HTR-PB. <ref>{{citation
 | title = United States: Very high temperature gas-cooled reactor could burn 65% of uranium.
 | journal = TendersInfo
 | date = 26 July 2008
 | url = http://www.thefreelibrary.com/United+States:+Very+high+temperature+gas-cooled+reactor+could+burn+...-a0181864466}}</ref>
<ref>{{citation
 | title = Constructing a high-temperature gas-cooled reactor
 | journal = World Nuclear Performance Report
 | date = 2022
 | url = https://www.world-nuclear.org/world-nuclear-performance-report/case-studies/htr-pm.aspx}}</ref>