Community Research and Development Information Service - CORDIS

Abstract

The main goal of this status report is to review suitable material irradiation damage dosimetry characterisation parameters, in such a way that experimental results obtained in a research reactor environment can be applied in the design of fusion power plants. Recent developments in fusion reactor technology programmes and mainly the large European component qualification tests undertaken for NET (Next European Torus) have led to new requirements. In particular, the application of ceramics (tritium breeding blankets, insulators) raises new issues such as damage to sub-lattices, and relevance of "dpa" as irradiation parameter. This report presents the status of the available metrology methods, recommended cross-sections and damage assessment, relevant to fusion technology material irradiations.

Additional information

Authors: ALBERMAN A, CEA, CEN Saclay, Gif-sur-Yvette (FR);DIERCKX R, JRC Ispra (IT);NOLTHENIUS H J, JRC Petten (NL);VOORBRAAK W P, JRC Petten (NL)
Bibliographic Reference: EUR 14630 EN (1992) 15 pp., FS, free of charge
Availability: Available from Joint Research Centre, Publication Department, I-21020 Ispra (Va.) (IT)
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