In-vessel tritium retention and removal in ITER
Tritium retention inside the vacuum vessel has emerged as a potentially serious constraint in the operation of the International Thermonuclear Experimental Reactor (ITER). In this paper we review recent tokamak and laboratory data on hydrogen, deuterium and tritium retention for materials and conditions which are of direct relevance to the design of ITER. These data, together with significant advances in understanding the underlying physics, provide the basis for modelling predictions of the tritium inventory in ITER. We present the derivation, and discuss the results, of current predictions both in terms of implantation and codeposition rates, and critically discuss their uncertainties and sensitivity to important design and operation parameters such as plasma edge conditions, the surface temperature, the presence of mixed materials etc.
Bibliographic Reference: Article: Journal of Nuclear Materials, 266-269 (1999), 14-29
Record Number: 199910756 / Last updated on: 1999-05-21
Original language: en
Available languages: en