Current and anticipated uses of thermal-hydraulic codes in NFI

Conference · Tue Jul 01 00:00:00 EDT 1997

OSTI ID:544389

Tsuda, K ^[1]; Takayasu, M ^[2]

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1. Nuclear Fuel Industries, Ltd., Tokyo (Japan)
2. Nuclear Fuel Industries, Ltd., Sennann-gun (Japan)

This paper presents the thermal-hydraulic codes currently used in NFI for the LWR fuel development and licensing application including transient and design basis accident analyses of LWR plants. The current status of the codes are described in the context of code capability, modeling feature, and experience of code application related to the fuel development and licensing. Finally, the anticipated use of the future thermal-hydraulic code in NFI is briefly given.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Systems Technology; Nuclear Energy Agency, 75 - Paris (France); SCIENTECH, Inc., Boise, ID (United States)
• OSTI ID: 544389
• Report Number(s): NUREG/CP-0159; NEA/CSNI/R-(97)4; CONF-961192-; ON: TI97008508; TRN: 98:000227
• Resource Relation: Conference: Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements, Annapolis, MD (United States), 5-8 Nov 1996; Other Information: PBD: Jul 1997; Related Information: Is Part Of Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements; Ebert, D.; PB: 824 p.
• Country of Publication: United States
• Language: English

Related Subjects

21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
WATER COOLED REACTORS
DESIGN BASIS ACCIDENTS
REACTOR LICENSING
NUCLEAR FUELS
DESIGN
COMPUTER CODES
RECOMMENDATIONS
TRANSIENTS
HYDRAULICS
USES
COMPUTERIZED SIMULATION