An analytical study on excitation of nuclear-coupled thermal-hydraulic instability due to seismically induced resonance in BWR

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

DOI:https://doi.org/10.1016/0029-5493(95)01128-5· OSTI ID:544400

Hirano, Masashi ^[1]

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1. Japan Atomic Energy Research Institute, Ibaraki-ken (Japan)

This paper describes the results of a scoping study on seismically induced resonance of nuclear-coupled thermal-hydraulic instability in BWRs, which was conducted by using TRAC-BF1 within a framework of a point kinetics model. As a result of the analysis, it is shown that a reactivity insertion could occur accompanied by in-surge of coolant into the core resulted from the excitation of the nuclear-coupled instability by the external acceleration. In order to analyze this phenomenon more in detail, it is necessary to couple a thermal-hydraulic code with a three-dimensional nuclear kinetics code.

• 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: 544400
• Report Number(s): NUREG/CP-0159; NEA/CSNI/R-(97)4; CONF-961192-; ON: TI97008508; TRN: 98:000238
• Resource Relation: Journal Volume: 162; Journal Issue: 2-3; 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
BWR TYPE REACTORS
INSTABILITY
SEISMIC EFFECTS
HYDRAULICS
COMPUTERIZED SIMULATION
T CODES