Critical Heat Flux One-side Heating AC Loss Annular Swirl Breeding Blanket CS model coil Divertor Divertor Plate End-return Fabrication Full scale separable first wall Fusion Engineering Heat Generation High heat flux test ITER Japanese Design Proposal Joining technique Negative Ion Source Neutral Beam Injection System Numerical Simulation Pebble bed Plasma Facing Components Runaway Electrons Shielding blanket Structural Analysis Subcooled Boiling Thermo-mechanical Performance Tritium Breeding Performance Tritium leakage hydrogen permeation