Abstract Following the IAEA Technical Meeting on'Advanced Methodologies for the Analysis
of Materials in Energy Applications Using Ion Beam Accelerators', this paper reviews the …

ITER will use beryllium as a plasma-facing material in the main chamber, covering a total
surface area of about 620 m 2. Given the importance of beryllium erosion and co-deposition …

Operation of the JET tokamak with beryllium and tungsten ITER-like wall provides unique
opportunity for detailed studies on dust generation: quantity, morphology, location, etc. The …

Post mortem analyses of JET ITER-Like-Wall tiles and passive diagnostics have been
completed after each of the first two campaigns (ILW-1 and ILW-2). They show that the …

An assessment of the tritium (T) inventory in plasma facing components (PFC) during JET T
and deuterium-tritium (DT) operations is presented based on the most comprehensive ex …

The status of the literature is reviewed for thermophysical properties of pure polycrystalline
solid and liquid beryllium which constitute input for the modeling of intense plasma–surface …

Fuel retention and material migration results from JET ITER-like wall beryllium limiter tiles
are presented for three operating periods. Ion beam analysis results support the general …

Collection and ex situ studies of dust generated in controlled fusion devices during plasma
operation are regularly carried out after experimental campaigns. Herewith results of the …

Dust particles and co-deposits were sampled for the first time from beryllium limiters and
bulk tungsten divertor (both after ILW-3), and test mirrors from the main chamber after ILW-2 …

A brief overview of ion beam analysis methods and procedures in studies of materials
exposed to fusion plasmas in controlled fusion devices with magnetic confinement is …