Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA /

Bibliographic Details
Main Author:	Shih, Chunkuan (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, August 2016.
Series:	International agreement report ; NUREG/IA-0471.
Subjects:	Nuclear fuel rods. Nuclear reactor accidents > Analysis. Pressurized water reactors > Loss of coolant > Analysis. Nuclear power plants > Taiwan.
Online Access:	https://purl.fdlp.gov/GPO/gpo71780

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