The next generation nuclear plant (NGNP), whose development is supported by the U. S. Department of Energy, will be a very high temperature reactor (VHTR). The VHTR is a single-phase helium-cooled reactor that will provide helium at up to 1000 °C. The prospect of a coolant at these temperatures circulating in the reactor vessel demands that careful analysis be performed to ensure that excessively hot spots are not created and that sufficient mixing of the coolant is obtained. Computational fluid dynamics (CFD) coupled with heat transfer will be used to perform the desired analyses. However, primarily because of the imperfect nature of modeling turbulent flow, any CFD calculations used to perform nuclear reactor safety analysis must be valid...
International audienceWhen looking for a validation experiment for CFD application to reactor simula...
Uncertainties associated with the core bypass flow are some of the key issues that directly influenc...
The experimental program that is being conducted at the Matched Index-of-Refraction (MIR) Flow Facil...
The next generation nuclear plant (NGNP), whose development is supported by the U. S. Department of ...
The U. S. Department of Energy (DOE) is supporting the development of a next generation nuclear plan...
The very high temperature reactor (VHTR) has been chosen as the concept for the next generation nucl...
The U. S. Department of Energy (DOE) is currently supporting the development of a next generation nu...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
The U.S. Department of Energy (DOE) is conducting research and development to support the resurgence...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further devel...
Advanced gas-cooled reactors offer the potential advantage of higher efficiency and enhanced safety ...
The final design of the very high temperature reactor (VHTR) of the fourth generation of nuclear pow...
Data from a scaled model of a portion of the lower plenum of the helium-cooled very high temperature...
Codes aimed at simulating thermal hydraulics phenomena in current and next generation nuclear reacto...
International audienceWhen looking for a validation experiment for CFD application to reactor simula...
Uncertainties associated with the core bypass flow are some of the key issues that directly influenc...
The experimental program that is being conducted at the Matched Index-of-Refraction (MIR) Flow Facil...
The next generation nuclear plant (NGNP), whose development is supported by the U. S. Department of ...
The U. S. Department of Energy (DOE) is supporting the development of a next generation nuclear plan...
The very high temperature reactor (VHTR) has been chosen as the concept for the next generation nucl...
The U. S. Department of Energy (DOE) is currently supporting the development of a next generation nu...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
The U.S. Department of Energy (DOE) is conducting research and development to support the resurgence...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further devel...
Advanced gas-cooled reactors offer the potential advantage of higher efficiency and enhanced safety ...
The final design of the very high temperature reactor (VHTR) of the fourth generation of nuclear pow...
Data from a scaled model of a portion of the lower plenum of the helium-cooled very high temperature...
Codes aimed at simulating thermal hydraulics phenomena in current and next generation nuclear reacto...
International audienceWhen looking for a validation experiment for CFD application to reactor simula...
Uncertainties associated with the core bypass flow are some of the key issues that directly influenc...
The experimental program that is being conducted at the Matched Index-of-Refraction (MIR) Flow Facil...