Post-test calculation of the ROSA/LSTF test 3-1 using RELAP5/Mod3.3 /

Bibliographic Details
Main Author:	Martínez-Solares, Verónica
Corporate Author:	U.S. Nuclear Regulatory Commission
Other Authors:	Reventós, F., Pretel, C.
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, [2012]
Series:	International agreement report ; NUREG/IA-0409.
Subjects:	Pressurized water reactors > Loss of coolant > Computer simulation. Nuclear power plants > Accidents > Computer simulation. Nuclear power plants > Computer programs.
Online Access:	https://purl.fdlp.gov/GPO/gpo21615

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