Published November 2002 | Version v1
Journal article

Overview of fusion nuclear technology in Europe

Description

The fusion nuclear technology programme in the EU is focussed on materials and breeding blankets development, tritium and high heat flux component technologies. A strong effort is also devoted to the validation of the design of an intense 14 MeV neutron source (IFMIF). The material programme includes the development of reduced activation ferritic martensitic steel (EUROFER) to be used as structural material in a DEMO reactor, and potentially more attractive higher performance materials: ODS and SiC/SiC composites. The breeding blanket activities are focussed in the preparation of the two European Test Blanket Moduli to be installed in ITER. The Fuel Cycle activities for ITER include development of the torus exhaust cryopump, fuel storage system, performance characterisation of the torus exhaust processing and design of water detritiation system. High heat flux components have been developed in the framework of ITER R and D programme and based on copper alloy heat sink protected by an armour of beryllium, CFC or tungsten. Studies give an important contribution in defining the nuclear technology programme strategy

Additional details

Identifiers

PII
S0920379602001102;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
61-62
Journal Issue
3
Journal Page Range
p. 27-36
ISSN
0920-3796
CODEN
FEDEEE

Optional Information

Copyright
Copyright (c) 2002 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.