Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface / prepared by Chunkuan Shih [and six others]

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Bibliographic Details
Online Access:	Online Access Online Access
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.

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Call Number:	Y 3.N 88:53/0465
Y 3.N 88:53/0465	Available