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Home > Art, Film & Photography > Graphite Moderated Reactors: Advanced Gas-Cooled Reactor, Molten Salt Reactor, Magnox, Yongbyon Nuclear Scientific Research Center
Graphite Moderated Reactors: Advanced Gas-Cooled Reactor, Molten Salt Reactor, Magnox, Yongbyon Nuclear Scientific Research Center

Graphite Moderated Reactors: Advanced Gas-Cooled Reactor, Molten Salt Reactor, Magnox, Yongbyon Nuclear Scientific Research Center


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About the Book

Please note that the content of this book primarily consists of articles available from Wikipedia or other free sources online. Pages: 24. Chapters: Advanced gas-cooled reactor, Molten salt reactor, Magnox, Yongbyon Nuclear Scientific Research Center, Dungeness Nuclear Power Station, Very high temperature reactor, Hartlepool Nuclear Power Station, B Reactor, UNGG reactor, F-1, Vandellos Nuclear Power Plant, N-Reactor, Latina Nuclear Power Plant, Graphite moderated reactor, GLEEP, Argonaut class reactor, HTTR, Saint-Laurent-des-Eaux, MOATA. Excerpt: A molten salt reactor (MSR) is a type of nuclear fission reactor in which the primary coolant is a molten salt mixture. MSRs run at higher temperatures than water cooled reactors for higher thermodynamic efficiency, while staying at low vapor pressure. The ability to operate at near atmospheric pressures reduces the mechanical stress endured by the system, thus simplifying aspects of reactor design and improving safety. The nuclear fuel may be solid fuel rods or dissolved in the coolant itself. One kind of a MSR is the liquid fluoride thorium reactor (LFTR), recently described by Kirk Sorensen at Mount Royal University. In many designs the nuclear fuel is dissolved in the molten fluoride salt coolant as uranium tetrafluoride (UF4). The fluid becomes critical in a graphite core which serves as the moderator. Fluid fuel reactors have significantly different safety issues compared to solid fuel designs; the potential for major reactor accidents is reduced, while the potential for processing accidents is increased. More recent research has focused on the practical advantages of the high-temperature low-pressure primary cooling loop. Many modern designs rely on ceramic fuel dispersed in a graphite matrix, with the molten salt providing low pressure, high temperature cooling. The salts are much more efficient at removing heat from the core, reducing the need for pumping, piping, and reducing the size of the core as these co...


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Product Details
  • ISBN-13: 9781156773222
  • Publisher: Books LLC, Wiki Series
  • Publisher Imprint: Books LLC, Wiki Series
  • Height: 246 mm
  • No of Pages: 26
  • Spine Width: 1 mm
  • Weight: 68 gr
  • ISBN-10: 1156773229
  • Publisher Date: 06 Jul 2011
  • Binding: Paperback
  • Language: English
  • Returnable: N
  • Sub Title: Advanced Gas-Cooled Reactor, Molten Salt Reactor, Magnox, Yongbyon Nuclear Scientific Research Center
  • Width: 189 mm


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