Tritium Removal from Codeposits on Carbon Tiles by a Scanning Laser | Zendy

C.H. Skinner | Zendy; C.A. Gentile | Zendy; A. Carpe | Zendy; G. Guttadora | Zendy; S. Langish | Zendy; K.M. Young | Zendy; Wei Shu | Zendy; and H. Nakamura | Zendy

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Tritium Removal from Codeposits on Carbon Tiles by a Scanning Laser

Author(s) -

C.H. Skinner,

C.A. Gentile,

A. Carpe,

G. Guttadora,

S. Langish,

K.M. Young,

Wei Shu,

and H. Nakamura

Publication year - 2001

Publication title -

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

Language(s) - English

Resource type - Reports

DOI - 10.2172/788203

Subject(s) - tritium , graphite , fusion power , materials science , laser , tokamak fusion test reactor , tokamak , analytical chemistry (journal) , argon , carbon fibers , chemistry , radiochemistry , composite number , composite material , optics , plasma , nuclear physics , chromatography , physics , organic chemistry

A novel method for tritium release has been demonstrated on codeposited layers on graphite and carbon-fiber-composite tiles from the Tokamak Fusion Test Reactor (TFTR). A scanning continuous wave Nd laser beam heated the codeposits to a temperature of 1200-2300 degrees C for 10 to 200 milliseconds in an argon atmosphere. The temperature rise of the codeposit was significantly higher than that of the manufactured tile material (e.g., 1770 degrees C cf. 1080 degrees C). A major fraction of tritium was thermally desorbed with minimal change to the surface appearance at a laser intensity of 8 kW/cm(superscript ''2''), peak temperatures above 1230 degrees C and heating duration 10-20 milliseconds. In two experiments, 46% and 84% of the total tritium was released during the laser scan. The application of this method for tritium removal from a tokamak reactor appears promising and has significant advantages over oxidative techniques

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