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

A.T. Peacock (Corresponding Author), V. Barabash, W. Dänner, M. Rödig, P. Lorenzetto, P. Marmy, M. Merola, B.N. Singh, Seppo Tähtinen, J. van der Laan, C.H. Wu

Research output: Contribution to journalArticleScientificpeer-review

24 Citations (Scopus)

Abstract

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.
Original languageEnglish
Pages (from-to)173 - 177
Number of pages5
JournalJournal of Nuclear Materials
Volume329-333
DOIs
Publication statusPublished - 2004
MoE publication typeA1 Journal article-refereed
Event11th International Conference on Fusion Reactor Materials (ICFRM-11) - Kyoto, Japan
Duration: 7 Dec 200312 Dec 2003

Fingerprint

Irradiation
irradiation
Fatigue of materials
Plasmas
fatigue life
crack initiation
heat sinks
stress relaxation
Heat sinks
Stress relaxation
proton energy
fracture strength
welding
Crack initiation
vessels
Protons
Fracture toughness
Hydrogen
Neutrons
Creep

Keywords

  • ITER
  • fusion energy
  • fusion reactors
  • fatigue (materials)
  • materials
  • fatique
  • crack initiation
  • crack propagation

Cite this

Peacock, A. T., Barabash, V., Dänner, W., Rödig, M., Lorenzetto, P., Marmy, P., ... Wu, C. H. (2004). Overview of recent European materials R&D activities related to ITER. Journal of Nuclear Materials, 329-333, 173 - 177. https://doi.org/10.1016/j.jnucmat.2004.04.008
Peacock, A.T. ; Barabash, V. ; Dänner, W. ; Rödig, M. ; Lorenzetto, P. ; Marmy, P. ; Merola, M. ; Singh, B.N. ; Tähtinen, Seppo ; van der Laan, J. ; Wu, C.H. / Overview of recent European materials R&D activities related to ITER. In: Journal of Nuclear Materials. 2004 ; Vol. 329-333. pp. 173 - 177.
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Peacock, AT, Barabash, V, Dänner, W, Rödig, M, Lorenzetto, P, Marmy, P, Merola, M, Singh, BN, Tähtinen, S, van der Laan, J & Wu, CH 2004, 'Overview of recent European materials R&D activities related to ITER', Journal of Nuclear Materials, vol. 329-333, pp. 173 - 177. https://doi.org/10.1016/j.jnucmat.2004.04.008

Overview of recent European materials R&D activities related to ITER. / Peacock, A.T. (Corresponding Author); Barabash, V.; Dänner, W.; Rödig, M.; Lorenzetto, P.; Marmy, P.; Merola, M.; Singh, B.N.; Tähtinen, Seppo; van der Laan, J.; Wu, C.H.

In: Journal of Nuclear Materials, Vol. 329-333, 2004, p. 173 - 177.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Overview of recent European materials R&D activities related to ITER

AU - Peacock, A.T.

AU - Barabash, V.

AU - Dänner, W.

AU - Rödig, M.

AU - Lorenzetto, P.

AU - Marmy, P.

AU - Merola, M.

AU - Singh, B.N.

AU - Tähtinen, Seppo

AU - van der Laan, J.

AU - Wu, C.H.

PY - 2004

Y1 - 2004

N2 - 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.

AB - 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.

KW - ITER

KW - fusion energy

KW - fusion reactors

KW - fatigue (materials)

KW - materials

KW - fatique

KW - crack initiation

KW - crack propagation

U2 - 10.1016/j.jnucmat.2004.04.008

DO - 10.1016/j.jnucmat.2004.04.008

M3 - Article

VL - 329-333

SP - 173

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

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ER -

Peacock AT, Barabash V, Dänner W, Rödig M, Lorenzetto P, Marmy P et al. Overview of recent European materials R&D activities related to ITER. Journal of Nuclear Materials. 2004;329-333:173 - 177. https://doi.org/10.1016/j.jnucmat.2004.04.008