Substances /
Molecular Formulas
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Ar; Be; C; CO; Cu; Fe; H; H2O; He; Kr; Li17Pb83; Li2O; Mo; N; NbTi; Ne; Ni; O; Pb; W; aluminium; aluminum; argon; beryllium; carbon; charcoal; copper; helium; hydrogen; iron; lithium; lithium nesosilicate; lithium titanate; lithium zirconate; neon; niobium tin; niobium titanium; nitrogen; oxygen; silicon carbide; titanium hydride |
|
Element Systems
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C-H; C-Si; H-O; H-Ti; Li-O; Li-O-Si; Li-O-Ti; Li-O-Zr; Li-Pb; Nb-Sn; Nb-Ti; Ti-V |
| Properties |
confinement; cross section; current; density; electron density; heat transport; melting point; pressure; resistivity; safety factor; stability; thermal energy; transport |
| Keywords |
D-T experiment; D-T fuel; D-T plasma; ECRF heating; H-mode plasma; ICRF; ITER; NBI; PFC; TF magnet; alpha particle; application; bootstrap current; boundary; breeder material; breeding blanket structure; breeding material; ceramic; chemical sputtering; collisionality; coolant; core contamination; cryogenic pellet; deuterium-tritium plasma; disruption; divertor; electron cyclotron frequency; electron cyclotron range of frequency heating; electron temperature; energetic particle confinement; energy confinement; energy confinement time; first wall material; first wall structure; fuel; fusion power production; fusion triple product; heat sink; helium ash; helium extraction; high-temperature superconductor; hydrogen puffing; impurity seeding; international thermonuclear experimental reactor; ion cyclotron radiofrequency heating; ion temperature; killer pellet; lower hybrid wave heating; magnet system; magnetohydrodynamic stability; mhd stability; multiplier; neutral beam injection; neutron multiplier; nuclear power plant; nuclear reactor plasma; operational limit; particle confinement time; pellet; plasma; plasma contamination; plasma facing component; plasma frequency; plasma fueling system; plasma poisoning; plasma transport process; plasma-surface interaction; poloidal field coil; power handling material; pump coating; pumping system; recycling coefficient; shield blanket material; shielding; superconductor; tokamak; tokamak plasma; toroidal field magnet; transport loss; tritium breeding; vacuum vessel; vacuum vessel structure |
|
Main Subjects
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MCF; magnetic confinement fusion; tokamak |
|
Secondary Subjects
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ITER; MCF; auxiliary systems; configuration; confinement; current drive systems; deuterium-tritium experiments; diagnostics; disruptions; divertor experiments; elementary transport processes; energetic particle confinement; energetic particle interactions with mhd instabilities; energetic particle physics; equilibrium; exhaust; experiments; fueling; heating; introduction; magnetic confinement fusion; magnetohydrodynamic stability; mhd instabilities; mhd stability; operational limits; particle control; particle flow control; particle orbits; plasma; plasma boundary issues; plasma confinement; plasma confinement modes; plasma equilibrium parameters; plasma resistivity; plasma-surface interactions; power; power control; steady-state operation; tokamak; tokamak configuration; tokamak equilibrium; tokamak experiments; tokamak power plants; transport; transport processes; vertical instability |
| Substrates |
CFC; D; SS; SS 30467; SS 304L; SS 316; SS 316L(N); SiC/SiC; T; V alloy; a SS; austenitic stainless steel; bismuth-silver alloy; carbon fibre composite; deuterium; electron; f-m SS; ferritic-martensitic stainless steel; graphite; liquid Li; liquid lithium; plasma; stainless steel; tritium; vanadium titanium alloy |
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