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 language | English |
|---|---|
| Pages (from-to) | 173-177 |
| Number of pages | 5 |
| Journal | Journal of Nuclear Materials |
| Volume | 329-333 |
| DOIs | |
| Publication status | Published - 2004 |
| MoE publication type | A1 Journal article-refereed |
| Event | 11th International Conference on Fusion Reactor Materials (ICFRM-11) - Kyoto, Japan Duration: 7 Dec 2003 → 12 Dec 2003 |
Keywords
- ITER
- fusion energy
- fusion reactors
- fatigue (materials)
- materials
- fatique
- crack initiation
- crack propagation