CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident /

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Bibliographic Details
Author / Creator:Boyd, Christopher Fred, author.
Imprint:Washington, DC : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, October 2003.
Description:1 online resource (various pagings) : illustrations
Language:English
Subject:Pressurized water reactors -- Accidents.
Nuclear reactor accidents.
Nuclear power plants -- Safety measures.
Nuclear power plants -- Safety measures.
Nuclear reactor accidents.
Pressurized water reactors -- Accidents.
Format: E-Resource U.S. Federal Government Document Book
URL for this record:http://pi.lib.uchicago.edu/1001/cat/bib/11059783
Hidden Bibliographic Details
Varying Form of Title:Computational fluid dynamics analysis of one-seventh scale steam generator inlet plenum mixing during a pressurized-water reactor severe accident
Other authors / contributors:Hardesty, K., author.
U.S. Nuclear Regulatory Commission. Division of Systems Analysis and Regulatory Effectiveness, issuing body.
Notes:"NUREG-1781."
"Manuscript completed: September 2003; date published: October 2003."
Includes bibliographical references.
Technical report.
Description based on online resource; title from PDF title page (viewed on May 1, 2017).
Other form:Print version: Boyd, C.F. CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident
GPO item no.:1051-H-48 (online)
Govt.docs classification:Y 3.N 88:10/1781