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

Description
Item Description:	"Institute of Nuclear Engineering and Science, National Tsing Hua University, Nuclear and New Energy Education and Research Foundation." "Department of Nuclear Safety, Taiwan Power Company." "K. Tien, NRC project manager." "Manuscript completed: March 2016; date published: August 2016." "Prepared as part of the agreement on research participation and technical exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
Physical Description:	1 online resource (various pagings) : illustrations.
Bibliography:	Includes bibliographical references.