Status of the Engineering Design of the Iter Divertor
17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2（1998）
关键词
Tokamak devices,fusion reactor design,fusion reactor materials,ITER divertor,armour erosion,electromagnetic loading,engineering design,final design,geometry,heat sink,layout,material selection,plasma facing components,thermal loading,thermal low cycle fatigue
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