Current Engineering Issues and Further Upgrading of the JET Tokamak
Fusion Engineering, 1997 17th IEEE/NPSS Symposium（1997）
Key words
finite element analysis,fusion reactor design,fusion reactor materials,fusion reactor safety,fusion reactor theory,nuclear engineering,nuclear engineering computing,13 MW,3.4 to 4 T,3.8 T,Be,JET,Joint European Torus,Mark I divertor,Mark II divertor,Mark IIGB divertor,X-point configuration,engineering,finite element,graphite,low-Z materials,machine protection,plasma control system,plasma current,protection,pumped divertor,sideways vessel displacements,tokamak,upgrading
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