The ITER blanket system design challenge

Abstract

This paper summarizes the latest progress in the ITER blanket system design as it proceeds through its final design phase with the Final Design Review planned for Spring 2013. The blanket design is constrained by demanding and sometime conflicting design and interface requirements from the plasma and systems such as the vacuum vessel, in-vessel coils and blanket manifolds. This represents a major design challenge, which is highlighted in this paper with examples of design solutions to accommodate some of the key interface and integration requirements.

Modelling ELM heat flux deposition on the ITER main chamber wall

“…The plasma-facing material in the model adopted here consists of 8 mm thick beryllium (Be) tiles bonded onto CuCrZr alloy heat sink cooled by a hypervapotron [12]. Perfect thermal contact is assumed between the Be tile and the heat sink with the coolant temperature set to the maximum foreseen value of 140°C.…”

Heat loads in inboard limited L-mode plasmas in TCV

“…If such an enhanced heat flux is present, the heat load on the limiter could result in the melting of the beryllium first wall panels, according to their present design [3]. A series of dedicated experiments is performed on TCV to investigate the presence of such an enhanced heat flux.…”

Mechanical support concept of the DEMO breeding blanket

“…Electrical insulation at physical contact interfaces can be ensured by a surface coating. For the insulated supports of the ITER shield block Albronze pads with a 250μm thick plasma-sprayed alumina coating on all sides were qualified [12].…”