DocumentCode
325007
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
Volume
1
fYear
1997
fDate
6-10 Oct 1997
Firstpage
321
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;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location
San Diego, CA
Print_ISBN
0-7803-4226-7
Type
conf
DOI
10.1109/FUSION.1997.687047
Filename
687047
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