Tritium removal by CO{sub 2} laser heating
- Princeton Univ., NJ (United States). Princeton Plasma Physics Lab.
- Sandia National Labs., Albuquerque, NM (United States)
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{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 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. They identify remaining issues that need to be addressed experimentally.
- Research Organization:
- Princeton Univ., Princeton Plasma Physics Lab., NJ (United States)
- Sponsoring Organization:
- USDOE Office of Energy Research, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH03073
- OSTI ID:
- 304218
- Report Number(s):
- PPPL--3273; CONF-971065--; ON: DE98050520
- Country of Publication:
- United States
- Language:
- English
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