Tritium Removal by CO{sub 2} Laser Heating

Technical Report · Wed Oct 01 04:00:00 UTC 1997

DOI:https://doi.org/10.2172/4562· OSTI ID:4562

Doyle, B L ^[1]; Skinner, C H; Mueller, D; Kugel, H; Wampler, W R

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1. Princeton Plasma Physics Laboratory

Efficient techniques for rapid tritium removal will be necessary for ITER (International Thermonuclear Experimental Reactor) to meet its physics and engineering goals. One potential technique is transient surface heating by a scanning CO(subscript 2) or Nd:Yag laser that would release tritium without the severe engineering difficulties of bulk heating of the vessel. We have modeled the heat propagation into a surface layer and find that a multi-kW/cm(superscript2) flux with an exposure time of order 10 msec is suitable to heat a 50 micron co-deposited layer to 1,000-2,000 degrees. Improved wall conditioning may be a significant side benefit. We identify remaining issues that need to be addressed experimentally.

• Research Organization: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ
• Sponsoring Organization: USDOE Office of Energy Research (ER)
• DOE Contract Number: AC02-76CH03073
• OSTI ID: 4562
• Report Number(s): PPPL-3273; ON: DE00004562
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
Carbon Dioxide Lasers
ITER Tokamak
Radiation Heating
Tritium Recovery