RELAP5/MOD3.2 assessment using GERDA small break test, 1605AA /

Bibliographic Details
Main Author:	Tietsch, W. (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, July 1999.
Series:	International agreement report ; NUREG/IA-0166.
Subjects:	Pressurized water reactors > Loss of coolant > Computer simulation.
Online Access:	https://purl.fdlp.gov/GPO/gpo83171

Description
Item Description:	"ABB Reaktor GmbH." "July 1999." "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)." "Sponsoring organization: Division of Systems Technology, Office of Nuclear Reactor Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.
Physical Description:	1 online resource (31, A49, B62 pages) : illustrations.
Bibliography:	Includes bibliographical references.