Community Research and Development Information Service - CORDIS

Abstract

The possible interaction between plasma disruptions and the thermal fatigue lifetime of a bare fusion reactor first wall is discussed. At present a theoretical and experimental activity is carried out at the JRC Ispra in order to investigate if and how a plasma disruption induced crack propagates, under a thermal stress driving force in a high gradient stress field. The most pessimistic reactor relevant plasma disruption is simulated on a first wall mock-up by means of an electron beam gun. Subsequently the component is thermal fatigue cycled and the crack growth is monitored with non-destructive techniques. The experimental results are then compared with existing theoretical models. The possible impact on the first wall design is discussed.

Additional information

Authors: MATERA R, JRC Ispra (IT);MEROLA M, JRC Ispra (IT)
Bibliographic Reference: Paper presented: 2nd International Symposium on Fusion Nuclear Technology, Karlsruhe (DE), June 2-7, 1991
Availability: Available from (1) as Paper EN 36173 ORA
Record Number: 199110750 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: en
Available languages: en
Follow us on: RSS Facebook Twitter YouTube Managed by the EU Publications Office Top