High Temperature Gas-cooled Reactor: Difference between revisions

From Citizendium
Jump to navigation Jump to search
imported>Howard C. Berkowitz
No edit summary
imported>Howard C. Berkowitz
No edit summary
Line 1: Line 1:
{{subpages}}
{{subpages}}
[[Image:Vhtr ngnp sm.jpg|left|thumb|500px|VHTR schematic]]
[[Image:Vhtr ngnp sm.jpg|left|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 [[graphite moderator|graphite-moderated]], [[helium cooling (reactor)|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
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
  | 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]]
  | publisher = [[Idaho National Laboratory]], [[U.S. Department of Energy]]

Revision as of 18:49, 10 May 2010

This article is a stub and thus not approved.
Main Article
Discussion
Related Articles  [?]
Bibliography  [?]
External Links  [?]
Citable Version  [?]
 
This editable Main Article is under development and subject to a disclaimer.
VHTR schematic

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 the uranium hydride reactor by Hyperion Power Generation and the Chinese 200 MW HTR-PB. [2]

References