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Experimental Modeling of VHTR Plenum Flows During Normal Operation and Pressurized Conduction Cooldown.

DE2007911716

Publication Date	2006
Personal Author	McCreery, G. E.; Condie, K. G.
Page Count	33
Abstract	The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S. which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. The present document addresses experimental modeling of flow and thermal mixing phenomena of importance during normal or reduced power operation and during a loss of forced reactor cooling (pressurized conduction cooldown) scenario. The objectives of the experiments are, (1), provide benchmark data for assessment and improvement of codes proposed for NGNP designs and safety studies, and, (2), obtain a better understanding of related phenomena, behavior and needs. Physical models of VHTR vessel upper and lower plenums which use various working fluids to scale phenomena of interest are described. The models may be used to both simulate natural convection conditions during pressurized conduction cooldown and turbulent lower plenum flow during normal or reduced power operation.
Keywords	VHTR reactor Flow models Plenum flows Modeling Very high temperature reactor(VHTR) Next Generation Nuclear Power(NGNP)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200802

Experimental Modeling of VHTR Plenum Flows During Normal Operation and Pressurized Conduction Cooldown.

Experimental Modeling of VHTR Plenum Flows During Normal Operation and Pressurized Conduction Cooldown.
DE2007911716

Publication Date	2006
Personal Author	McCreery, G. E.; Condie, K. G.
Page Count	33
Abstract	The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S. which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. The present document addresses experimental modeling of flow and thermal mixing phenomena of importance during normal or reduced power operation and during a loss of forced reactor cooling (pressurized conduction cooldown) scenario. The objectives of the experiments are, (1), provide benchmark data for assessment and improvement of codes proposed for NGNP designs and safety studies, and, (2), obtain a better understanding of related phenomena, behavior and needs. Physical models of VHTR vessel upper and lower plenums which use various working fluids to scale phenomena of interest are described. The models may be used to both simulate natural convection conditions during pressurized conduction cooldown and turbulent lower plenum flow during normal or reduced power operation.
Keywords	VHTR reactor Flow models Plenum flows Modeling Very high temperature reactor(VHTR) Next Generation Nuclear Power(NGNP)
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Lab., Idaho Falls.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200802