An effective convectivity model for simulation of in-vessel core melt progression in a boiling water reactor
2008 (English)In: Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 2008, 925-935 p.Conference paper (Refereed)
The present paper is concerned with development and application of a so-called Effective Convectivity Model (ECM), which aims to provide a detailed, mechanistic description of heat transfer processes in a BWR lower plenum. The ECM is a Computational Fluid Dynamics (CFD)-like tool which employs a simpler and more effective approach to compute heat transfer by solving only energy conservation equation instead of solving the full set of Navier-Stokes and energy equations by a CFD code. We implement the ECM in a CFD code (Fluent), with detailed description of the ECM development, implementation and validation. A dual approach is used to validate the ECM, namely validation against experimental data and against heat transfer results obtained by CFD predictions in the same geometries and conditions. Insights gained from CFD simulations are also used to improve ECM. The ECM capability as an effective tool to simulate heat transfer of an internally heated volume in 3D complex geometry is demonstrated through examples of heat transfer analysis in a BWR lower plenum being cooled by coolant flow in Control Rod Guide Tubes. Simulation results and key findings of this case are reported and discussed.
Place, publisher, year, edition, pages
2008. 925-935 p.
, Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 2
Boiling water reactors, Chlorine compounds, Codes (standards), Codes (symbols), Computational fluid dynamics, Conservation, Core meltdown, Dynamics, Electric power plants, Energy conservation, Energy management, Energy policy, Flow of fluids, Fluid dynamics, Fluid mechanics, Heat exchangers, Heat transfer, Heating equipment, Navier Stokes equations, Nuclear energy, Nuclear engineering, Nuclear industry, Nuclear power plants, Nuclear reactors, Power plants, Steam power plants, Thermoanalysis, Three dimensional, Boiling water, Cfd codes, CFD simulations, Complex geometries, Computational Fluid Dynamics (CFD), Coolant flow, Effective tool, Energy conservation equations, Energy equations, Experimental data, Heat-transfer analysis, In-control, In-vessel, International Congress on Advances in Nuclear Power Plants, Lower plenum, Navier - stokes, Nuclear renaissance, Simulation results, Electric discharge machining
IdentifiersURN: urn:nbn:se:kth:diva-154325ScopusID: 2-s2.0-52249091307ISBN: 9781604238716OAI: oai:DiVA.org:kth-154325DiVA: diva2:756816
Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work", 13 May 2007 through 18 May 2007, Nice
QC 201410202014-10-202014-10-172014-10-20Bibliographically approved