Design and life assessment of first wall components
- Insitut fuer Materialforschung II, Karlsruhe (Germany)
The first wall (FW) of a tokamak fusion reactor is subjected to periodically changing high heat fluxes. The severe loading conditions imply restrictions on FW concepts. The selection of candidate structural materials, cooling media, range of operating temperatures design implementations in geometry terms as well as the questions of protection tiles and/or limiters are strongly interrelated. Any of these items could not be changed individually. Two very different approaches will be investigated: (1) High temperature concept. The FW is directly integrated as part of the blanket box, fabricated from vanadium alloys, cooled by liquid metal at 300{degrees}C-400{degrees}C from the rear part only, coated with a beryllium layer on the plasma side, and provided with beryllium limiters. This concept is being discussed in the current ITER engineering design phase. (2) Low temperature concept (reference design during ITER-CDA). Austenitic steel, SS 316 L, is used as structural material for the component, which is actively cooled (cooling tubes in FW) by water at low pressure and low temperatures of 60{degrees}C-100{degrees}C, and, on the plasma facing surface, is completely covered by protecting graphite (CFC) tiles. Both designs are critically evaluated with respect to their capability to accommodate admissible heat fluxes. Detailed temperature and stress analyses were performed for both. Stress levels and resistance to fatigue are being assessed.
- OSTI ID:
- 196851
- Report Number(s):
- CONF-940664-; TRN: 95:005767-0018
- Resource Relation:
- Conference: ISFNT-3: international symposium on fusion nuclear technology, Los Angeles, CA (United States), 27 Jun - 1 Jul 1994; Other Information: PBD: 1994; Related Information: Is Part Of Third international symposium on fusion nuclear technology; PB: 362 p.
- Country of Publication:
- United States
- Language:
- English
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