Thermo-mechanical investigation on divertor supports for fusion experimental reactor
Conference
·
OSTI ID:196979
- Tokai Research Establishment, Ibaraki (Japan); and others
The Japan Atomic Energy Research Institute (JAERI) has been conducting technology development aiming at the constructing of Fusion Experimental Reactor (FER) to follow JT-60 in Japan. The divertor plate to control impurities in the main plasma is one of the key components of the reactor core assembly. The divertor plate has to be operated under severe heat/particle loads from plasma during its operation and thus the divertor supports should be designed to provide flexibility for thermal expansion along the divertor cooling tube, mechanical stiffness for fixing the distance between the divertor and the plasma separatrix, and easy replacement of the divertor in the event of failure. This paper gives hydraulic experimental results including fluid-induced vibration characteristics of the divertor cooling tube in the different hydraulic and supporting conditions.
- OSTI ID:
- 196979
- Report Number(s):
- CONF-940664--
- Country of Publication:
- United States
- Language:
- English
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