Overview of fusion nuclear technology in Europe

被引：22

作者：

Andreani, R ^{[1
]}

Gasparotto, M ^{[1
]}

机构：

[1] Max Planck Inst Plasma Phys, EFDA Close Support Unit, D-85740 Garching, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2002年 / 61-62卷

关键词：

fusion; nuclear technology; framework programme;

D O I：

10.1016/S0920-3796(02)00110-2

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

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&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. (C) 2002 Elsevier Science B.V. All rights reserved.

引用

页码：27 / 36

页数：10

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