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Analysis of main steam line break accident for 3-Loop PWR with RELAP5/MOD3.3 code / prepared by Chunkuan Shih [and five others].

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Format:
Book
Government document
Author/Creator:
Shih, Chunkuan, author.
Contributor:
U.S. Nuclear Regulatory Commission. Division of Systems Analysis, issuing body.
Series:
International agreement report ; NUREG/IA-0527.
International agreement report ; NUREG/IA-0527
Language:
English
Subjects (All):
Pressurized water reactors--Loss of coolant.
Pressurized water reactors.
Pressurized water reactors--Accidents.
Genre:
technical reports.
Technical reports.
Physical Description:
1 online resource (xv, 25 pages) : color illustrations.
Place of Publication:
Washington, D.C. : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Systems Analysis, August 2021.
Notes:
"Manuscript Completed: February 2021; Date Published: August 2021."
Includes bibliographical references (pages 25).
Description based on online resource; title from PDF title page (NRC, viewed Jan. 27, 2026).
OCLC:
1570278503

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