Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface /

Bibliographic Details
Main Author:	Shih, Chunkuan (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : U.S. Nuclear Regulatory Commission, March 2016.
Series:	International agreement report ; NUREG/IA-0465.
Subjects:	Nuclear power plants > Taiwan. Nuclear fuel rods > Thermal properties > Computer programs.
Online Access:	https://purl.fdlp.gov/GPO/gpo66696 http://purl.fdlp.gov/GPO/gpo66696

Available Online