Title :
Tritium removal by CO2 laser heating
Author :
Skinner, C.H. ; Kugel, H. ; Mueller, D. ; Doyle, B.L. ; Wampler, W.R.
Author_Institution :
Plasma Phys. Lab., Princeton Univ., NJ, USA
Abstract :
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 CO2 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/cm2 flux with a 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. We identify remaining issues that need to be addressed experimentally
Keywords :
fusion reactor design; fusion reactor safety; tritium handling; CO2 laser heating; ITER; Nd:YAG laser; co-deposited layer; exposure time; heat propagation; multi-kW/cm2 flux; rapid tritium removal; scanning CO2 laser; surface layer; transient surface heating; wall conditioning; Electrons; Heat engines; Heating; Laboratories; Laser modes; Laser theory; Optical control; Physics; Plasma temperature; Surface emitting lasers;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687047
