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An apparatus has been developed to study the recycling and outgassing of hydrogen and deuterium from first wall materials under fusion reactor conditions. The first wall of NET (Next European Torus) will be bombarded by a flux of (3x1.0 E16) atoms/cm2/s at relatively low energies (approximately a gaussian distribution with a maximum at 200eV). The main part of the apparatus described in this paper consists of a cylindrical multipole ion source that can produce a plasma of some 1.0 E12 ions/cm3 at a potential of few eV above the potential of the anode. The ion flux density in front of the target can reach some hundred mA/cm2. This corresponds to an atomic hydrogen flux density of about 1.0 E18 per cm2/s if a plasma composition of H(3)+:H(2)+:H+ = 1:1:1 is assumed. A detailed description of the experimental apparatus and first results from an AISI 316 L stainless steel target are presented. This apparatus is the test bed for near future experiment in ETHEL (European Tritium Handling Experimental Laboratory), where permeation, recycling and outgassing of tritium and deuterium-tritium mixtures from first wall materials at very high fluxes and low energies will be studied.

Additional information

Authors: PERUJO A, JRC Ispra (IT);CAMPOSILVAN J, JRC Ispra (IT);CAORLIN M, JRC Ispra (IT);REITER F, JRC Ispra (IT);TOMINETTI S, JRC Ispra (IT);PIOSCZYK B, KFK, Institut für Technische Physik, Karlsruhe (DE)
Bibliographic Reference: Paper presented: Course and Workshop "Tritium and Advanced Fuels in Fusion Reactors", Villa Monastero, Varenna (IT), Sept. 6-15, 1989
Availability: Available from (1) as Paper EN 34929 ORA
Record Number: 199010016 / Last updated on: 1994-12-01
Original language: en
Available languages: en