The first wall (FW) of a tokamak fusion reactor is subjected to periodically changing large heat fluxes. Water-cooled FW panels made from austenitic SS 316 L steel are analyzed. First, life predictions for initially defect-free components, obtained by applying design code rules, are compared with ex
โฆ LIBER โฆ
Structural assessment of the NET/ITER first wall and component testing
โ Scribed by R.R. Jakeman; G. Vieider; R. Matera
- Publisher
- Elsevier Science
- Year
- 1991
- Tongue
- English
- Weight
- 594 KB
- Volume
- 16
- Category
- Article
- ISSN
- 0920-3796
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