Poster, 2013, ENG

Deuterium retention and erosion proprerties of nanostructured W coatings

R. Caniello, S. Deambrosis, D. Dellasega, E. Miorin, M. Passoni, M.H.J. 't Hoen, E. Vassallo, P.A. Zeijlmans van Emmichoven

Istituto di Fisica del Plasma, CNR, EURATOM-ENEA-CNR Association - Milano (Italy), Dipartimento di Energia, Politecnico di Milano - Milano (Italy), Istituto per l'Energetica e le Interfasi, CNR, Padova, (Italy), FOM Institute DIFFER, Association EURATOM-FOM, Nieuwegein (Netherlands).

One of the aims of the ITER Tokamak is to demonstrate the feasibility of a prolonged fusion power production based on a deuterium (D)- tritium (T) plasma. Plasma facing materials (PFMs) are a key issue for this objective. ITER will use tungsten (W) in the divertor baffle and other regions, which will be subject to high fluxes of energetic particles. Although, W is considered the most suitable material for the divertor region, owing to its high sputtering threshold and melting point, the possible retention of tritium in tungsten needs to be assessed for safety requirements. Due to the plasma interaction, W coatings in the divertor could have different morphologies and/or nanostructures. The present research activity aims to study different nanostructured W coatings exposed to high-flux D ion to evaluate the hydrogen retention properties.

AIV XXI Congress, Catania (Italy), May 15-17, 2013

Keywords

Retention of tritium, tokamak, fusion device, tungsten

CNR authors

Passoni Matteo, Dellasega David, Caniello Roberto, Vassallo Espedito, Miorin Enrico, Deambrosis Silvia Maria

CNR institutes

ICMATE – Istituto di Chimica della Materia Condensata e di Tecnologie per l'Energia