Tritium Removal from Carbon Plasma Facing Components | Zendy

C.H. Skinner | Zendy; J.P. Coad | Zendy; G. Federici | Zendy

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Tritium Removal from Carbon Plasma Facing Components

Author(s) -

C.H. Skinner,

J.P. Coad,

G. Federici

Publication year - 2003

Language(s) - English

Resource type - Reports

DOI - 10.2172/820208

Subject(s) - tritium , joint european torus , tokamak , tokamak fusion test reactor , nuclear engineering , fusion power , environmental science , carbon fibers , plasma , nuclear physics , materials science , engineering , physics , composite number , composite material

Tritium removal is a major unsolved development task for next-step devices with carbon plasma-facing components. The 2-3 order of magnitude increase in duty cycle and associated tritium accumulation rate in a next-step tokamak will place unprecedented demands on tritium removal technology. The associated technical risk can be mitigated only if suitable removal techniques are demonstrated on tokamaks before the construction of a next-step device. This article reviews the history of codeposition, the tritium experience of TFTR (Tokamak Fusion Test Reactor) and JET (Joint European Torus) and the tritium removal rate required to support ITER's planned operational schedule. The merits and shortcomings of various tritium removal techniques are discussed with particular emphasis on oxidation and laser surface heating

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