One of the candidates for advanced reactor designs identified for the Next Generation Nuclear Plant (NGNP) is the Very High Temperature Reactor (VHTR). The Reactor Cavity Cooling System (RCCS) is a promising passive decay heat removal system for the VHTR to ensure reliability of the transfer of the core decay heat to the environment whilst ensuring that the temperature of structures and concrete wall are under threshold limits during normal and off-normal operations, including accident conditions. The experimental test facility reflects a ⅛ scale model of one conceptual passive decay heat removal system for advanced nuclear reactor designs. This ⅛ scale air-cooled RCCS experimental test facility was scaled, designed, constructed, and opera...
The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further devel...
The Reactor Cavity Cooling System (RCCS) of a High Temperature Gas-cooled Reactor (HGTR) plays an i...
Thermal hydraulics in nuclear engineering including multifluid, multiphase flow phenomena is indispe...
High Temperature Gas cooled Reactor (HTGR) that is one of GEN-IV reactor types enhances its safety a...
The design of passive heat removal systems is one of the main concerns for the modular Very High Tem...
In the U.S., the helium-cooled VHTR has become the centerpiece of DOE NGNP program. Among the VHTR d...
Graduation date: 2006Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is b...
This study investigated how heat transfer occurs during pressurized conduction cooldown accidents (P...
A reactor cavity cooling system (RCCS), an air-cooled helical coil RCCS unit immersed in the water p...
The Very High Temperature gas cooled reactor (VHTR) is one of the GEN IV reactor concepts that have ...
The Very High Temperature Reactor (VHTR) is a proposed next generation nuclear power plant. The VHT...
The Reactor Cavity Cooling System (RCCS) is an important passive cooling safety system used to cool ...
PhD (Nuclear Engineering), North-West University, Potchefstroom CampusThe fourth-generation nuclear ...
The Very High Temperature Reactor (VHTR) is a promising Gen-IV reactor design. It is a helium cooled...
The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Po...
The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further devel...
The Reactor Cavity Cooling System (RCCS) of a High Temperature Gas-cooled Reactor (HGTR) plays an i...
Thermal hydraulics in nuclear engineering including multifluid, multiphase flow phenomena is indispe...
High Temperature Gas cooled Reactor (HTGR) that is one of GEN-IV reactor types enhances its safety a...
The design of passive heat removal systems is one of the main concerns for the modular Very High Tem...
In the U.S., the helium-cooled VHTR has become the centerpiece of DOE NGNP program. Among the VHTR d...
Graduation date: 2006Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is b...
This study investigated how heat transfer occurs during pressurized conduction cooldown accidents (P...
A reactor cavity cooling system (RCCS), an air-cooled helical coil RCCS unit immersed in the water p...
The Very High Temperature gas cooled reactor (VHTR) is one of the GEN IV reactor concepts that have ...
The Very High Temperature Reactor (VHTR) is a proposed next generation nuclear power plant. The VHT...
The Reactor Cavity Cooling System (RCCS) is an important passive cooling safety system used to cool ...
PhD (Nuclear Engineering), North-West University, Potchefstroom CampusThe fourth-generation nuclear ...
The Very High Temperature Reactor (VHTR) is a promising Gen-IV reactor design. It is a helium cooled...
The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Po...
The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further devel...
The Reactor Cavity Cooling System (RCCS) of a High Temperature Gas-cooled Reactor (HGTR) plays an i...
Thermal hydraulics in nuclear engineering including multifluid, multiphase flow phenomena is indispe...