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HandWiki. Boiling Water Reactor. Encyclopedia. Available online: https://encyclopedia.pub/entry/36255 (accessed on 25 September 2026).
HandWiki. Boiling Water Reactor. Encyclopedia. Available at: https://encyclopedia.pub/entry/36255. Accessed September 25, 2026.
HandWiki. "Boiling Water Reactor" Encyclopedia, https://encyclopedia.pub/entry/36255 (accessed September 25, 2026).
HandWiki. (2022, November 24). Boiling Water Reactor. In Encyclopedia. https://encyclopedia.pub/entry/36255
HandWiki. "Boiling Water Reactor." Encyclopedia. Web. 24 November, 2022.
Boiling Water Reactor
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A boiling water reactor (BWR) is a type of light water nuclear reactor used for the generation of electrical power. It is the second most common type of electricity-generating nuclear reactor after the pressurized water reactor (PWR), which is also a type of light water nuclear reactor. The main difference between a BWR and PWR is that in a BWR, the reactor core heats water, which turns to steam and then drives a steam turbine. In a PWR, the reactor core heats water, which does not boil. This hot water then exchanges heat with a lower pressure system, which turns water into steam that drives the turbine. The BWR was developed by the Argonne National Laboratory and General Electric (GE) in the mid-1950s. The main present manufacturer is GE Hitachi Nuclear Energy, which specializes in the design and construction of this type of reactor.

nuclear reactor water reactor reactor core

References

  1. "Core damage frequency perspectives for BWR 3/4 and Westinghouse 4-loop plants based on IPE results". Osti.gov. 31 December 1995. http://www.osti.gov/scitech/servlets/purl/205567. 
  2. Bonin, Bernhard; Klein, Etienne (2012). Le nucléaire expliqué par des physiciens. 
  3. James W. Morgan, Exelon Nuclear (15 November 2007). "Upgrade your BWR recirc pumps with adjustable-speed drives". Power: Business and Technology for the Global Generation Industry. http://www.powermag.com/nuclear/Upgrade-your-BWR-recirc-pumps-with-adjustable-speed-drives_369.html. 
  4. Kuan, P.; Hanson, D. J.; Odar, F. (1991). Managing water addition to a degraded core. 
  5. Haskin, F.E.; Camp, A.L. (1994). Perspectives on Reactor Safety (NUREG/CR-6042) (Reactor Safety Course R-800), 1st Edition. Beltsville, MD: U.S. Nuclear Regulatory Commission. p. 3.1–5. https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6042/. Retrieved 23 November 2010. 
  6. (PDF (11 MB)) Boiling Water Reactor Simulator with Passive Safety Systems - IAEA, IAEA, October 2009, p. 14, http://www.iaea.org/NuclearPower/Downloads/Simulators/Advanced.BWR.Manual.2009-10.pdf, retrieved 8 June 2012 
  7. Nuclear Reactors Build, Being Built, or Planned in the United States as of June 30, 1970. 1970. doi:10.2172/4115425. https://www.osti.gov/servlets/purl/4115425. 
  8. Sandia National Laboratories (July 2006), Containment Integrity Research at Sandia National Laboratories – An Overview, U.S. Nuclear Regulatory Commission, NUREG/CR-6906, SAND2006-2274P, https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6906/cr6906.pdf, retrieved 13 March 2011 
  9. "Advanced Boiling Water Reactor (ABWR) fact sheet". 2010. https://nuclear.gepower.com/content/dam/gepower-nuclear/global/en_US/documents/product-fact-sheets/ABWR%20Fact%20Sheet.pdf. 
  10. "Issued Design Certification - Economic Simplified Boiling-Water Reactor (ESBWR)". https://www.nrc.gov/reactors/new-reactors/design-cert/esbwr.html. 
  11. Hinds, David; Maslak, Chris (January 2006). "Next-generation nuclear energy: The ESBWR". Nuclear News (La Grange Park, Illinois, United States of America: American Nuclear Society) 49 (1): 35–40. ISSN 0029-5574. http://www.ans.org/pubs/magazines/nn/docs/2006-1-3.pdf. Retrieved 2009-04-04. 
  12. KEIJI TAKEUCHI COMMENTARY: Crucial vents were not installed until 1990s Asahi.com http://www.asahi.com/english/TKY201103140243.html
  13. NEDO-21231, "Banked Position Withdrawal Sequence," January 1977. General Electric Corporation
  14. http://pbadupws.nrc.gov/docs/ML0523/ML052340664.pdf NUREG-0800, (67:234) Chpt 4, Section 4.4, Rev. 1, Thermal and Hydraulic Design, of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants. LWR Edition. (10 page(s), 7/31/1981)
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