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C.H. Skinner; C.A. Gentile; A. Carpe; G. Guttadora; S. Langish; K.M. Young; W.M. Shu; H. Nakamura
Princeton Plasma Physics Lab., NJ (United States). Funding organisation: USDOE Office of Science (United States)2001
Princeton Plasma Physics Lab., NJ (United States). Funding organisation: USDOE Office of Science (United States)2001
AbstractAbstract
[en] A novel method for tritium release has been demonstrated on codeposited layers on graphite and carbon-fiber-composite tiles from the Tokamak Fusion Test Reactor (TFTR). A scanning continuous wave Nd laser beam heated the codeposits to a temperature of 1200-2300 degrees C for 10 to 200 milliseconds in an argon atmosphere. The temperature rise of the codeposit was significantly higher than that of the manufactured tile material (e.g., 1770 degrees C cf. 1080 degrees C). A major fraction of tritium was thermally desorbed with minimal change to the surface appearance at a laser intensity of 8 kW/cm(superscript ''2''), peak temperatures above 1230 degrees C and heating duration 10-20 milliseconds. In two experiments, 46% and 84% of the total tritium was released during the laser scan. The application of this method for tritium removal from a tokamak reactor appears promising and has significant advantages over oxidative techniques
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Source
28 Sep 2001; 39 p; AC02-76CH03073; Also available from OSTI as DE00788203; PURL: https://www.osti.gov/servlets/purl/788203-bWJCgl/native/
Record Type
Report
Report Number
Country of publication
BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON, CLOSED PLASMA DEVICES, ELEMENTS, FIBERS, HEATING, HYDROGEN ISOTOPES, ISOTOPES, LIGHT NUCLEI, MINERALS, NONMETALS, NUCLEI, ODD-EVEN NUCLEI, PLASMA HEATING, RADIOISOTOPES, SORPTION, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTOR WALLS, TOKAMAK DEVICES, YEARS LIVING RADIOISOTOPES
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