As part of the International Thermonuclear Engineering Reactor (ITER) plasma fueling development program, Oak Ridge National Laboratory (ORNL) has fabricated a pellet injection system to test the mechanical and thermal properties of extruded tritium. This repeating, single-stage, pneumatic injector, called the Tritium-Proof-of-Principle Phase II (TPOP-II) Pellet Injector, has a piston-driven mechanical extruder and is designed to extrude hydrogenic pellets sized for the ITER device. The TPOP-II program has the following development goals: evaluate the feasibility of extruding tritium and DT mixtures for use in future pellet injection systems; determine the mechanical and thermal properties of tritium and DT extrusions; integrate, test and e...
The fusion technology development program for tritium in the US is centered around the Tritium Syste...
ITER Disruption Mitigation System (DMS) will inject a small quantity of neon and a large quantity of...
The experimental qualification of the Tritium Extraction Unit (TEU) from the LiPb eutectic alloy (15....
As part of the International Thermonuclear Engineering Reactor (ITER) plasma fueling development pro...
As part of the International Thermonuclear Experimental Reactor (ITER) plasma fueling development pr...
As part of the International Thermonuclear Engineering Reactor (ITER) plasma fueling development pro...
Oak Ridge National Laboratory (ORNL) has been developing pellet injection systems for plasma fueling...
The tritium proof-of-principle (TPOP) experiment was designed and built by Oak Ridge National Labora...
The TFTR tritium pellet injector (TPI) is designed to provide a tritium pellet fueling capability wi...
The repeating pneumatic hydrogen pellet injector, which was developed at the Oak Ridge National Labo...
Oak Ridge National Laboratory (ORNL) has been developing pellet injectors for plasma fueling experim...
Advanced plasma fueling systems for magnetic confinement devices are being developed at the Oak Ridg...
Abstract. The design of the ITER-FEAT vacuum pumping and fuelling systems is supported by two key R&...
The repeating pneumatic injector is a device from the ORNL development program. A new eight-shot deu...
The development of innovative fueling systems in support of magnetic fusion energy, particularly the...
The fusion technology development program for tritium in the US is centered around the Tritium Syste...
ITER Disruption Mitigation System (DMS) will inject a small quantity of neon and a large quantity of...
The experimental qualification of the Tritium Extraction Unit (TEU) from the LiPb eutectic alloy (15....
As part of the International Thermonuclear Engineering Reactor (ITER) plasma fueling development pro...
As part of the International Thermonuclear Experimental Reactor (ITER) plasma fueling development pr...
As part of the International Thermonuclear Engineering Reactor (ITER) plasma fueling development pro...
Oak Ridge National Laboratory (ORNL) has been developing pellet injection systems for plasma fueling...
The tritium proof-of-principle (TPOP) experiment was designed and built by Oak Ridge National Labora...
The TFTR tritium pellet injector (TPI) is designed to provide a tritium pellet fueling capability wi...
The repeating pneumatic hydrogen pellet injector, which was developed at the Oak Ridge National Labo...
Oak Ridge National Laboratory (ORNL) has been developing pellet injectors for plasma fueling experim...
Advanced plasma fueling systems for magnetic confinement devices are being developed at the Oak Ridg...
Abstract. The design of the ITER-FEAT vacuum pumping and fuelling systems is supported by two key R&...
The repeating pneumatic injector is a device from the ORNL development program. A new eight-shot deu...
The development of innovative fueling systems in support of magnetic fusion energy, particularly the...
The fusion technology development program for tritium in the US is centered around the Tritium Syste...
ITER Disruption Mitigation System (DMS) will inject a small quantity of neon and a large quantity of...
The experimental qualification of the Tritium Extraction Unit (TEU) from the LiPb eutectic alloy (15....