In the U.S., the helium-cooled VHTR has become the centerpiece of DOE NGNP program. Among the VHTR design’s many technological innovations is a safety system called reactor cavity cooling system (RCCS). The RCCS provides means entirely external to the vessel to reject decay heat to the environment without the need for pumps, diesel generator, or human intervention. Besides keeping structures under designed temperatures during normal operations; the RCCS can take advantage of the high temperature in the vessel to passively remove the heat from the reactor cavity and maintain the reactor system under safe conditions throughout the transient in case of a loss of forced coolant accident. Computational Fluid Dynamics (CFD) tools may provide a me...
The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the ...
A prismatic gas-cooled very high temperature reactor (VHTR) is being developed under the next genera...
The Reactor TRIGA PUSPATI (RTP), a pool-type research reactor started operation in 1982 with maximum...
One of the candidates for advanced reactor designs identified for the Next Generation Nuclear Plant ...
Graduation date: 2006Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is b...
The design of passive heat removal systems is one of the main concerns for the modular Very High Tem...
PhD (Nuclear Engineering), North-West University, Potchefstroom CampusThe fourth-generation nuclear ...
The Reactor Cavity Cooling System (RCCS) is one of the passive safety systems included in the design...
Current research in advanced reactor designs has focused on passive safety systems, where in the eve...
High Temperature Gas cooled Reactor (HTGR) that is one of GEN-IV reactor types enhances its safety a...
The Very High Temperature gas cooled reactor (VHTR) is one of the GEN IV reactor concepts that have ...
A reactor cavity cooling system (RCCS), an air-cooled helical coil RCCS unit immersed in the water p...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
The Reactor Cavity Cooling System (RCCS) is an important passive cooling safety system used to cool ...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the ...
A prismatic gas-cooled very high temperature reactor (VHTR) is being developed under the next genera...
The Reactor TRIGA PUSPATI (RTP), a pool-type research reactor started operation in 1982 with maximum...
One of the candidates for advanced reactor designs identified for the Next Generation Nuclear Plant ...
Graduation date: 2006Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is b...
The design of passive heat removal systems is one of the main concerns for the modular Very High Tem...
PhD (Nuclear Engineering), North-West University, Potchefstroom CampusThe fourth-generation nuclear ...
The Reactor Cavity Cooling System (RCCS) is one of the passive safety systems included in the design...
Current research in advanced reactor designs has focused on passive safety systems, where in the eve...
High Temperature Gas cooled Reactor (HTGR) that is one of GEN-IV reactor types enhances its safety a...
The Very High Temperature gas cooled reactor (VHTR) is one of the GEN IV reactor concepts that have ...
A reactor cavity cooling system (RCCS), an air-cooled helical coil RCCS unit immersed in the water p...
The United States Department of Energy is promoting the resurgence of nuclear power in the U. S. for...
The Reactor Cavity Cooling System (RCCS) is an important passive cooling safety system used to cool ...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the ...
A prismatic gas-cooled very high temperature reactor (VHTR) is being developed under the next genera...
The Reactor TRIGA PUSPATI (RTP), a pool-type research reactor started operation in 1982 with maximum...