Assessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 /

Bibliographic Details
Main Author:	Oh, J. G. (Author)
Corporate Author:	U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Technology (sponsoring body.)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, September 1998.
Series:	International agreement report ; NUREG/IA-0148.
Subjects:	Pressurized water reactors > Loss of coolant > Computer programs > Testing.
Online Access:	https://purl.fdlp.gov/GPO/gpo83169

Description
Item Description:	"Korea Power Engineering Company." "Korea Institute of Nuclear Safety." "Japan Atomic Energy Research Institute." "September 1998." "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP)." "G. Rhee, NRC project manager"--Bibliographic data sheet.
Physical Description:	1 online resource (viii, 111 pages) : illustrations.
Bibliography:	Includes bibliographical references (page 29).