Community Research and Development Information Service - CORDIS

Abstract

The divertor plate represents a critical component in the design of a tokamak fusion reactor. Within the frame of the International Tokamak Experimental Reactor (ITER), many proposals are underway. The thermal behaviour following a complete Loss of Coolant Accident (LOCA) of a pre-designed divertor plate is analysed in this paper. The aim is to carry out a parametric study on the most critical parameter, i.e. the plasma shutdown time. Several load hypotheses are studied in order to contribute to a better understanding of the design requirements for the components. According to these results, significant material damage is expected to occur if plasma burning is not stopped efficiently within a few seconds of the LOCA detection.

Additional information

Authors: SORIA A, Universidad Politecnica, Instituto de Fusion Nuclear, Madrid (ES);RENDA V, JRC Ispra (IT);PAPA L, JRC Ispra (IT)
Bibliographic Reference: Article: Fusion Engineering and Design, Vol. 13 (1991) pp. 339-361
Record Number: 199111307 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: en
Available languages: en