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Simulation of the PKL-G7.1 experiment in a Westinghouse nuclear power plant using RELAP5/MOD3.3 /

Bibliographic Details
Main Author:	Sánchez-Sáez, F. (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, January 2019.
Series:	International agreement report ; NUREG/IA-0487.
Subjects:	Nuclear power plants > Computer programs. Pressurized water reactors > Loss of coolant.
Online Access:	https://purl.fdlp.gov/GPO/gpo128318

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