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Computational Flow Predictions for the Lower Plenum of a High-Temperature, Gas-Cooled Reactor.

DE2008911720

Publication Date	2006
Page Count	4
Abstract	Advanced gas-cooled reactors offer the potential advantage of higher efficiency and enhanced safety over present day nuclear reactors. Accurate simulation models of these Generation IV reactors are necessary for design and licensing. One design under consideration by the Very High Temperature Reactor (VHTR) program is a modular, prismatic gas-cooled reactor. In this reactor, the lower plenum region may experience locally high temperatures that can adversely impact the plant's structural integrity. Since existing system analysis codes cannot capture the complex flow effects occurring in the lower plenum, computational fluid dynamics (CFD) codes are being employed to model these flows. The goal of the present study is to validate the CFD calculations using experimental data.
Keywords	HTGR type reactors Computerized simulation Reactor cores Design Efficiency Fluid mechanics Licensing Reactors Safety Computational fluid dynamics Lower plenum
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200821
Contract Number	DE-AC07-99ID-13727

Computational Flow Predictions for the Lower Plenum of a High-Temperature, Gas-Cooled Reactor.

Computational Flow Predictions for the Lower Plenum of a High-Temperature, Gas-Cooled Reactor.
DE2008911720

Publication Date	2006
Page Count	4
Abstract	Advanced gas-cooled reactors offer the potential advantage of higher efficiency and enhanced safety over present day nuclear reactors. Accurate simulation models of these Generation IV reactors are necessary for design and licensing. One design under consideration by the Very High Temperature Reactor (VHTR) program is a modular, prismatic gas-cooled reactor. In this reactor, the lower plenum region may experience locally high temperatures that can adversely impact the plant's structural integrity. Since existing system analysis codes cannot capture the complex flow effects occurring in the lower plenum, computational fluid dynamics (CFD) codes are being employed to model these flows. The goal of the present study is to validate the CFD calculations using experimental data.
Keywords	HTGR type reactors Computerized simulation Reactor cores Design Efficiency Fluid mechanics Licensing Reactors Safety Computational fluid dynamics Lower plenum
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Engineering Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200821
Contract Number	DE-AC07-99ID-13727