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Computational fluid dynamics analysis of natural circulation flows in a pressurized-water reactor loop under severe accident conditions / prepared by C.F. Boyd and K.W. Armstrong.

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Format:
Book
Government document
Author/Creator:
Boyd, Christopher Fred
Contributor:
Armstrong, K. W.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Language:
English
Subjects (All):
Computational fluid dynamics--Accidents.
Computational fluid dynamics.
Steam generating heavy water reactors--Accidents.
Steam generating heavy water reactors.
Physical Description:
1 online resource (78 pages) : illustrations
Place of Publication:
Washington, DC : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2010]
Notes:
Title from PDF title screen (viewed June 25, 2010).
"Manuscript completed: February 2010; Date published: March 2010."
"NUREG-1922."
Includes bibliographical references (pages 43-44).
OCLC:
643551227

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