The major increase in discharge duration and plasma energy in a next step DT fusion
reactor will give rise to important plasma-material effects that will critically influence its …

The proper design of a fusion reactor is not possible unless there is an understanding of the
hydrogen isotope retention and recycling for the plasma-facing components. From the tritium …

Interactions between the plasma and the vessel walls constitute a major engineering
problem for next step fusion devices, such as ITER, determining the choice of the plasma …

The ITER project development has shown that considerable difficulties are encountered
when already known engineering solutions and materials are used for divertor and divertor …

Recent scientific and technical progress in magnetic fusion experiments has resulted in the
achievement of plasma parameters (density and temperature) which made possible the …

During 1997 JET operation with DT plasmas, 35 g of tritium were introduced into the torus,
mainly by gas puffing. It was found that during this period, the torus tritium inventory would …

The evaluation of hydrogenic retention in present tokamaks is of crucial importance to
estimate the expected tritium (T) vessel inventory in ITER, limited from safety considerations …

In the period 1998—2001 the JET tokamak was operated with the MkII Gas Box divertor. On
two occasions during that period a number of limiter and divertor tiles were retrieved from …

Tritium retention constitutes an outstanding problem for ITER operation and future fusion
reactors, particularly for the choice of the first wall materials. In present day tokamaks, fuel …

Plasma-Material Interaction in Controlled Fusion deals with the specific contact between the
fourth state of matter, ie plasma, and the first state of matter, ie a solid wall, in controlled …