Over the last fifteen years IFP undertook the working out of technologies related to future
fusion reactors. From 1988 to 1995 IFP was involved in the fusion fuel cycle. The
principal objective was the storage and recovery of tritium via getter materials different
than uranium. Besides, an extensive experimental investigation on the recovery of tritium
by cracking the water molecule was carried out. A tritium storage and delivery system
was designed using the IGNITOR reactor requirements. The work involved “hands on”
experiences in tritium laboratory with the required training of IFP personals. The activity
was carried out in collaboration with the Tritium laboratory of the Ontario Hydro
Dawson Research Division, Canada

From 1995 IFP was involved in the Euratom task "Long Term Programme on Structural
Materials for Fusion Reactors" with regards to this, an important issue in the design of
tokamak like ITER that will use tritium as fuel, is the estimate of the tritium content in
the plasma facing components of the vacuum vessel like the first wall and the divertor. At
IFP, a computer code has been developed to study the behaviour (recycling, diffusion and
permeation) of the hydrogen isotopes inside materials. This code has been applied to the
ITER case with different material options for the first wall. Most of this activity has been
performed in collaboraion with ENEA, CCR Ispra, Pisa University and KFA Julich.
Since the development of new materials and understanding their behavior under plasma
exposure appear to be paramount. IFP built a surface science laboratory mainly dedicated
to study the effects of fusion plasma on the surface of candidate first wall materials.

From 2003 IFP has a member in the ITER-EFDA Plasma-Wall Interaction Task Force
and is involved in the study of erosion and deposition of ITER first wall materials.

Further information from Francesco Ghezzi

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