Tritium Removal by CO{sub 2} Laser Heating [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy. Office of Energy Research, 1997.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: 44 Kilobytes : digital, PDF file
Additional Creators:: Princeton University. Plasma Physics Laboratory, United States. Department of Energy. Office of Energy Research, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

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.

Report Numbers:

E 1.99:pppl-3273
pppl-3273

Subject(s):

Plasma Physics And Fusion

Other Subject(s):

Note:

Published through SciTech Connect.
10/01/1997.
"pppl-3273"
"DE00004562"
D. Mueller; W.R. Wampler; B.L. Doyle; C.H. Skinner; H. Kugel.

Type of Report and Period Covered Note:

Topical;

Funding Information:

AC02-76CH03073

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