Current research in advanced reactor designs has focused on passive safety systems, where in the event of a loss of cooling to the reactor core, excess heat will be removed by a passive safety heat removal system. A safety system is classified as `passive' because it does not require a pump to circulate the fluid (i.e., forced circulation) or operator action to maintain cooling. The system relies on the natural circulation of a fluid (i.e., fluid density differences and gravity) to transfer the heat. Passive safety system designs include features that enhance natural circulation, such as using smooth pipes, minimizing flow obstructions, and maximizing density differences, which increase fluid velocity and hence the removal of more heat. ...
In recent decades, and with renewed importance after the events in Fukushima, the nuclear community ...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
The role of natural circulation in advanced water cooled reactor design has been extended with the a...
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...
PhD (Nuclear Engineering), North-West University, Potchefstroom CampusThe fourth-generation nuclear ...
Graduation date: 2006Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is b...
In the U.S., the helium-cooled VHTR has become the centerpiece of DOE NGNP program. Among the VHTR d...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
The Very High Temperature gas cooled reactor (VHTR) is one of the GEN IV reactor concepts that have ...
One of the candidates for advanced reactor designs identified for the Next Generation Nuclear Plant ...
The fourth generation gas-cooled nuclear reactor designs provide a promising prospect for energy and...
Steam is exhausted from a turbine into the BWR suppression pool as a means to remove energy from the...
Abstract only availableBased on standard commercial form factors, this study explores chassis-level ...
This project characterizes typical two-phase stratified flow conditions in advanced water reactor ho...
In recent decades, and with renewed importance after the events in Fukushima, the nuclear community ...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
The role of natural circulation in advanced water cooled reactor design has been extended with the a...
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...
PhD (Nuclear Engineering), North-West University, Potchefstroom CampusThe fourth-generation nuclear ...
Graduation date: 2006Among the Generation IV reactors, the Very High Temperature Reactor (VHTR) is b...
In the U.S., the helium-cooled VHTR has become the centerpiece of DOE NGNP program. Among the VHTR d...
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. Howev...
The Very High Temperature gas cooled reactor (VHTR) is one of the GEN IV reactor concepts that have ...
One of the candidates for advanced reactor designs identified for the Next Generation Nuclear Plant ...
The fourth generation gas-cooled nuclear reactor designs provide a promising prospect for energy and...
Steam is exhausted from a turbine into the BWR suppression pool as a means to remove energy from the...
Abstract only availableBased on standard commercial form factors, this study explores chassis-level ...
This project characterizes typical two-phase stratified flow conditions in advanced water reactor ho...
In recent decades, and with renewed importance after the events in Fukushima, the nuclear community ...
The safe operation of nuclear reactors cooled by liquid metal is an important issue to be addressed ...
The role of natural circulation in advanced water cooled reactor design has been extended with the a...