An existing experimental Reactor Cavity Cooling System using water as the coolant received extensive instrumentation and control upgrades to allow for a thorough investigation into the single-phase flow behavior of the system under a variety of experimental conditions. Base level conditions used a uniform heat flux at a power level appropriately scaled from a benchmark computer simulation of the Gas Turbine Modular Helium Reactor (GT-MHR) using scaling relationships derived by Argonne National Laboratory. Experiments were setup to gauge the effects of flow throttling, non-uniform heat flux profiles, alternate power levels and alternate coolant inventory levels on the flow distribution in the Cooling Panel, and to investigate the relationshi...
A test reactor concept for conducting basic studies on a fissioning uranium plasma and for testing v...
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 next generation nuclear reactors d...
An existing experimental Reactor Cavity Cooling System using water as the coolant received extensive...
The Reactor Cavity Cooling System (RCCS) is an important passive cooling safety system used to cool ...
This research focuses on establishing a range of scaled separate and integral effects experiments fo...
One of the candidates for advanced reactor designs identified for the Next Generation Nuclear Plant ...
The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further devel...
The coolant outlet temperature for the Modular Helium Reactor (MHR) was increased to improve the ove...
This paper discusses thermal hydraulic calculations for a Gas Test Loop (GTL) system designed to pro...
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...
The very high temperature reactor (VHTR) is one of the most promising next generation reactors which...
DoctorPassive cooling based on natural circulation is utilized in core catcher system of advanced re...
The primary purpose of this investigation was to experimentally determine the effect of operational ...
A test reactor concept for conducting basic studies on a fissioning uranium plasma and for testing v...
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 next generation nuclear reactors d...
An existing experimental Reactor Cavity Cooling System using water as the coolant received extensive...
The Reactor Cavity Cooling System (RCCS) is an important passive cooling safety system used to cool ...
This research focuses on establishing a range of scaled separate and integral effects experiments fo...
One of the candidates for advanced reactor designs identified for the Next Generation Nuclear Plant ...
The Very-High-Temperature Reactor (VHTR) is one of six reactor technologies chosen for further devel...
The coolant outlet temperature for the Modular Helium Reactor (MHR) was increased to improve the ove...
This paper discusses thermal hydraulic calculations for a Gas Test Loop (GTL) system designed to pro...
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...
The very high temperature reactor (VHTR) is one of the most promising next generation reactors which...
DoctorPassive cooling based on natural circulation is utilized in core catcher system of advanced re...
The primary purpose of this investigation was to experimentally determine the effect of operational ...
A test reactor concept for conducting basic studies on a fissioning uranium plasma and for testing v...
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 next generation nuclear reactors d...