Thermal-hydraulic systems safety analysis to support the design process for the advanced neutron source reactor

Journal Article · Thu Aug 01 04:00:00 EDT 1991 · Nuclear Technology; (United States)

OSTI ID:5559411

Fletcher, C D; Ghan, L S ^[1]

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1. Idaho National Engineering Lab., EG and G Idaho, Inc., Idaho Falls, ID (US)

This paper reports on large thermal-hydraulic systems computer codes that are most often applied to investigate safety issues in existing nuclear facilities. One such code is applied to aid the design process for a proposed state-of-the-art research reactor. The RELAPS computer code is used to simulate system response to hypothetical loss-of-coolant accidents (LOCAs) in an early design of the Advanced Neutron Source (ANS). Among accident scenarios, a LOCA event is expected to be one of the most challenging to the ANS reactor core; similar analyses for other accident types are in progress. This is the first detailed study of ANS transient system response during accidents, and the outcome of the analysis is used to benefit the design process. The ANS model used is based on an early (preconceptual) cooling system design layout.

• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5559411
• Journal Information: Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 95:2; ISSN NUTYB; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220400 -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANALOG SYSTEMS
COMPUTER CODES
COOLING SYSTEMS
DESIGN
FUNCTIONAL MODELS
LOSS OF COOLANT
PERFORMANCE TESTING
R CODES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR MONITORING SYSTEMS
REACTOR SAFETY EXPERIMENTS
REACTOR SIMULATORS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATORS
TEST FACILITIES
TESTING