Point kinetics calculations with fully coupled thermal fluids reactivity feedback

Conference · Mon Jul 01 00:00:00 EDT 2013

OSTI ID:22212744

Zhang, H.; Zou, L.; Andrs, D.; Zhao, H.; Martineau, R. ^[1]

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1. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83406 (United States)

The point kinetics model has been widely used in the analysis of the transient behavior of a nuclear reactor. In the traditional nuclear reactor system safety analysis codes such as RELAP5, the reactivity feedback effects are calculated in a loosely coupled fashion through operator splitting approach. This paper discusses the point kinetics calculations with the fully coupled thermal fluids and fuel temperature feedback implemented into the RELAP-7 code currently being developed with the MOOSE framework. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22212744
• Resource Relation: Conference: M and C 2013: 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID (United States), 5-9 May 2013; Other Information: Country of input: France; 7 refs.; Related Information: In: Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013| 3016 p.
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICAL METHODS AND COMPUTING
22 GENERAL STUDIES OF NUCLEAR REACTORS
COMPUTER CALCULATIONS
FLUIDS
REACTIVITY COEFFICIENTS
REACTOR KINETICS
SAFETY ANALYSIS
TRANSIENTS