Tritium Removal from JET and TFTR Tiles by a Scanning Laser | Zendy

C.H. Skinner | Zendy; N. Bekris | Zendy; J.P. Coad | Zendy; Carmelo Gentile | Zendy; M. Glugla | Zendy

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Tritium Removal from JET and TFTR Tiles by a Scanning Laser

Author(s) -

C.H. Skinner,

N. Bekris,

J.P. Coad,

Carmelo Gentile,

M. Glugla

Publication year - 2002

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/798184

Subject(s) - joint european torus , tokamak fusion test reactor , tritium , argon , plasma , jet (fluid) , laser , fusion power , materials science , tokamak , tritium illumination , nuclear engineering , nuclear physics , optics , chemistry , physics , organic chemistry , engineering , thermodynamics

Fast and efficient tritium removal is needed for future D-T machines with carbon plasma-facing components. A novel method for tritium release has been demonstrated on co-deposited layers on tiles retrieved from the Tokamak Fusion Test Reactor (TFTR) and from the Joint European Torus (JET). A scanning continuous wave neodymium laser beam was focused to =100 W/mm2 and scanned at high speed over the co-deposits, heating them to temperatures =2000 C for about 10 ms in either air or argon atmospheres. Fiber optic coupling between the laser and scanner was implemented. Up to 87% of the co-deposited tritium was thermally desorbed from the JET and TFTR samples. This technique appears to be a promising in-situ method for tritium removal in a next-step D-T device as it avoids oxidation, the associated de-conditioning of the plasma-facing surfaces, and the expense of processing large quantities of tritium oxide

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