ABSTRACT. A cryosorption panel test arrangement will be installed in the cryogenic forevacuum system of the Active Gas Handling System (AGHS) at JET. The panel is of ITER relevant design in terms of geometry and dimension, coating and sorbent material. The central objective of this task is to study, for the first time in such an in-depth and parametric way, the interaction of tritium and tritiated gas mixtures with the panel, with respect to pumping performance, desorption characteristics and structural influences. This paper describes the motivation for this task and outlines the experimental aims and how they are planned to be achieved. It presents the actual status and gives a description of the test arrangement design. The paper demonst...
Accurate measurement of the nuclear environment within a test tritium breeding-blanket module of a f...
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate...
As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the ri...
A reliable but versatile primary cryopumping system is required for high vacuum pumping of the ITER ...
JET is a unique facility in the preparation of ITER in that it is the largest operating fusion devic...
An apparatus used to obtain data on the cryocondensation pumping of deuterium, hydrogen and helium m...
The Tritium System Test Assembly (TSTA), at the Los Alamos Scientific Laboratory, is intended to dem...
Extensive preparations are now underway for an experiment in the Joint European Torus (JET) using tr...
For tritium processing in JET during the next Deuterium-Tritium-Experiment (DTE2), a fully tritium c...
Abstract. The design of the ITER-FEAT vacuum pumping and fuelling systems is supported by two key R&...
The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fus...
We designed an experimental system capable of handling at least 100 Ci tritium in an experimental ru...
Extensive preparations are now underway for an experiment in the Joint European Torus QET) using tri...
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusi...
Neutral beam injectors and divertors for fusion devices require very high-speed pumping capabilities...
Accurate measurement of the nuclear environment within a test tritium breeding-blanket module of a f...
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate...
As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the ri...
A reliable but versatile primary cryopumping system is required for high vacuum pumping of the ITER ...
JET is a unique facility in the preparation of ITER in that it is the largest operating fusion devic...
An apparatus used to obtain data on the cryocondensation pumping of deuterium, hydrogen and helium m...
The Tritium System Test Assembly (TSTA), at the Los Alamos Scientific Laboratory, is intended to dem...
Extensive preparations are now underway for an experiment in the Joint European Torus (JET) using tr...
For tritium processing in JET during the next Deuterium-Tritium-Experiment (DTE2), a fully tritium c...
Abstract. The design of the ITER-FEAT vacuum pumping and fuelling systems is supported by two key R&...
The JET Fusion Technology (FT) work programme was launched in 2000, in the frame of the European Fus...
We designed an experimental system capable of handling at least 100 Ci tritium in an experimental ru...
Extensive preparations are now underway for an experiment in the Joint European Torus QET) using tri...
Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusi...
Neutral beam injectors and divertors for fusion devices require very high-speed pumping capabilities...
Accurate measurement of the nuclear environment within a test tritium breeding-blanket module of a f...
The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate...
As a licensed nuclear facility, ITER must limit the in-vessel tritium (T) retention to reduce the ri...