High heat flux behaviour of damaged plasma facing components
A medium scale prototype of the ITER divertor vertical target, manufactured with calibrated internal bonding defects is tested and studied via infrared characterisation, thermal fatigue testing and finite element analysis. Tools for defect detection and behaviour of these defects along in-service lifetime are presented in this document.
Bibliographic Reference: An article published in: Fusion Engineering and Design, 56-57 (2001), pp. 285-290.
Record Number: 200214406 / Last updated on: 2002-02-18
Original language: en
Available languages: en