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 |
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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.
【 预 览 】
Files | Size | Format | View |
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798184.pdf | 492KB | download |