Tritium Removal from JET and TFTR Tiles by a Scanning Laser

Skinner, C.H. ; Bekris, N. ; Coad, J.P. ; Gentile, C.A. ; Glugla, M.

Princeton University. Plasma Physics Laboratory.

关键词: Removal;    Heating;    Argon;    70 Plasma Physics And Fusion Technology;    Tftr Tokamak;   

DOI  :  10.2172/798184
RP-ID  :  PPPL-3697.pdf
RP-ID  :  AC02-76CH03073
RP-ID  :  798184

美国|英语

来源: UNT Digital Library

【 摘 要 】

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.