Community Research and Development Information Service - CORDIS

Abstract

Beryllium is one of the major candidate materials for the plasma facing components of ITER. It represents, however, a considerable safety issue because of its high toxicity and its highly exothermic and fast oxidation in case of steam or air ingress into the vacuum vessel of the reactor. Such conditions might occur after a plasma disruption. The work presented here attempts to analyse the transient behaviour of the thermochemical system of a reacting plasma facing surface, identify its stability limits and assess its impact on overall ITER safety.

Additional information

Authors: ANDRITSOS F, JRC Ispra (IT);SARIGIANNIS D A, JRC Ispra (IT)
Bibliographic Reference: Paper presented: 7th International Conference on Fusion Reactor Materials, Obninsk (RU), September 24-29, 1995
Availability: Available from (1) as Paper EN 39287 ORA
Record Number: 199511460 / Last updated on: 1995-11-03
Category: PUBLICATION
Original language: en
Available languages: en