Assessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU #1 plant /

Bibliographic Details
Main Authors:	Chung, Bud-Dong (Author), Kim, H. J. (Hho Jung) (Author), Lee, Young Jin (Author)
Format:	Government Document eBook
Language:	English
Published:	Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, April 1990.
Series:	International agreement report ; NUREG/IA-0030.
Subjects:	Pressurized water reactors > Safety measures > Computer programs. Transients (Dynamics) > Computer programs.
Online Access:	https://purl.fdlp.gov/GPO/gpo73239

Description
Item Description:	"Nuclear Safety Center, Korea Advanced Energy Research Institute." "Department of Nuclear Engineering, Seoul National University." "April 1990." "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)." "Technical"--Bibliographic data sheet.
Physical Description:	1 online resource (v, 89 pages) : illustrations.
Bibliography:	Includes bibliographical references (page 34).