Published July 1997 | Version v1
Report Restricted

Current and anticipated uses of thermal-hydraulic codes in NFI

Creators

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

Description

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

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Additional details

Publishing Information

Imprint Title
Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements
Imprint Pagination
824 p.
Journal Page Range
p. 274-279.
Report number
NUREG/CP--0159

Conference

Title
Organization for Economic Co-Operation and Development (OECD)/Committee on the Safety of Nuclear Installations (CSNI) workshop on transient thermal-hydraulic codes requirements.
Dates
5-8 Nov 1996.
Place
Annapolis, MD (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29024729
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; COMPUTERIZED SIMULATION; DESIGN; DESIGN BASIS ACCIDENTS; HYDRAULICS; NUCLEAR FUELS; REACTOR LICENSING; RECOMMENDATIONS; TRANSIENTS; USES; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; ENERGY SOURCES; FUELS; LICENSING; MATERIALS; REACTOR ACCIDENTS; REACTOR MATERIALS; REACTORS; SIMULATION

Optional Information

Secondary number(s)
NEA/CSNI/R--(97)4; CONF-961192--.