High Temperature Gas-cooled Reactor

From Citizendium
Revision as of 17:21, 10 May 2010 by imported>Howard C. Berkowitz (New page: A candidate for the U.S. Department of Energy Next Generation Nuclear Plant (NGNP), the '''Very-High-Temperature Reactor (VHTR)''' is a graphite-moderated, helium-cooled re...)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search

A candidate for the U.S. Department of Energy Next Generation Nuclear Plant (NGNP), the Very-High-Temperature Reactor (VHTR) is a graphite-moderated, 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. [1]

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 Uranium Hydride hydride reactor by Hyperion Power Generation and the Chinese 200 MW HTR-PB. <ref>"United States: Very high temperature gas-cooled reactor could burn 65% of uranium.", TendersInfo, 26 July 2008</ref?

References