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research article

Overview of recent European materials R&D activities related to ITER

Peacock, A. T.
•
Barabash, V.
•
Danner, W.
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2004
Journal of Nuclear Materials

An overview is given of the wide range of activities contained within recent R&D being performed within Europe on In-vessel materials for structural, heat sink and plasma facing purposes for ITER. The effect of creep-fatigue interaction on the fatigue life of CuCrZr and the effects of irradiation on over-aged CuCrZr are given. In addition the lifetime of ITER components has been further investigated by the performance of in situ experiments with both neutrons and high-energy protons. The effect of hydrogen on the crack initiation fracture toughness of Ti is reported at a range of irradiation temperatures. The irradiation induced stress relaxation of Alloy 718 used for bolting applications is being studied and initial results will be described. Work in the area of plasma facing materials and re-welding issues will also be presented. (C) 2004 Elsevier B.V. All rights reserved.

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Type
research article
DOI
10.1016/j.jnucmat.2004.04.008
Web of Science ID

WOS:000223505000025

Author(s)
Peacock, A. T.
Barabash, V.
Danner, W.
Rodig, M.
Lorenzetto, P.
Marmy, P.  
Merola, M.
Singh, B. N.
Tahtinen, S.
van der Laan, J.
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Date Issued

2004

Published in
Journal of Nuclear Materials
Volume

329-33

Start page

173

End page

177

Subjects

ITER

Note

Part A

Editorial or Peer reviewed

REVIEWED

Written at

EPFL

EPFL units
CRPP  
SPC  
Available on Infoscience
April 16, 2008
Use this identifier to reference this record
https://infoscience.epfl.ch/handle/20.500.14299/22050
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