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Home > Art, Film & Photography > Nuclear Power Plant Components: Boiling Water Reactor Safety Systems, Cooling Tower, Containment Building, Nuclear Safety Systems, Control Rod
Nuclear Power Plant Components: Boiling Water Reactor Safety Systems, Cooling Tower, Containment Building, Nuclear Safety Systems, Control Rod

Nuclear Power Plant Components: Boiling Water Reactor Safety Systems, Cooling Tower, Containment Building, Nuclear Safety Systems, Control Rod


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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: 32. Chapters: Boiling water reactor safety systems, Cooling tower, Containment building, Nuclear safety systems, Control rod, Deaerator, Spent fuel pool, Dry cask storage, Pressurizer, Steam generator, Reactor vessel, Nuclear reactor core, Dry well, Reactor protection system, Core Catcher, Turbine hall, Standby Gas Treatment, Active fuel length, Reactor building. Excerpt: Boiling water reactor safety systems are nuclear safety systems constructed within boiling water reactors in order to prevent or mitigate environmental and health hazards in the event of accident or natural disaster. Like the pressurized water reactor, the BWR reactor core continues to produce heat from radioactive decay after the fission reactions have stopped, making a core damage incident possible in the event that all safety systems have failed and the core does not receive coolant. Also like the pressurized water reactor, a boiling water reactor has a negative void coefficient, that is, the neutron (and the thermal) output of the reactor decreases as the proportion of steam to liquid water increases inside the reactor. However, unlike a pressurized water reactor which contains no steam in the reactor core, a sudden increase in BWR steam pressure (caused, for example, by the actuation of the main steam isolation valve (MSIV) from the reactor) will result in a sudden decrease in the proportion of steam to liquid water inside the reactor. The increased ratio of water to steam will lead to increased neutron moderation, which in turn will cause an increase in the power output of the reactor. This type of event is referred to as a "pressure transient." The BWR is specifically designed to respond to pressure transients, having a "pressure suppression" type of design which vents overpressure using safety relief valves to below the surface of a pool of liquid water ...


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Product Details
  • ISBN-13: 9781155377131
  • Publisher: Books LLC, Wiki Series
  • Publisher Imprint: Books LLC, Wiki Series
  • Height: 246 mm
  • No of Pages: 34
  • Spine Width: 2 mm
  • Weight: 82 gr
  • ISBN-10: 1155377133
  • Publisher Date: 08 Jul 2011
  • Binding: Paperback
  • Language: English
  • Returnable: N
  • Sub Title: Boiling Water Reactor Safety Systems, Cooling Tower, Containment Building, Nuclear Safety Systems, Control Rod
  • Width: 189 mm


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