Tritium removal by CO{sub 2} laser heating

Conference · Wed Oct 01 00:00:00 EDT 1997

OSTI ID:537388

Skinner, C H; Kugel, H; Mueller, D ^[1]; Doyle, B L; Wampler, W R ^[2]

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1. Princeton Univ., NJ (United States). Plasma Physics Lab.
2. Sandia National Labs., Albuquerque, NM (United States)

Efficient techniques for rapid tritium removal will be necessary for ITER to meet its physics and engineering goals. One potential technique is transient surface heating by a scanning CO{sub 2} or Nd:Yag laser that would release tritium without the severe engineering difficulties of bulk heating of the vessel. The authors have modeled the heat propagation into a surface layer and find that a multi-kW/cm{sup 2} flux with an exposure time of order 10 ms 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. They identify remaining issues that need to be addressed experimentally.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States); Princeton Univ., NJ (United States). Plasma Physics Lab.
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC04-94AL85000; AC02-76CH03073
• OSTI ID: 537388
• Report Number(s): SAND--97-2554C; CONF-971065--; ON: DE98000561
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
CARBON DIOXIDE LASERS
D-T OPERATION
DESORPTION
HEATING
ITER TOKAMAK
LASER RADIATION
NEODYMIUM LASERS
TRITIUM RECOVERY