Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1564941 | Journal of Nuclear Materials | 2014 | 5 Pages |
Abstract
Near-surface regime plays an important role in thermal management of plasma facing components in fusion reactors. Here, we applied a technique referred to as the ‘3ω’ method to measure the thermal conductivity of near-surface regimes damaged by ion irradiation. By modulating the frequency of the heating current in a micro-fabricated heater strip, the technique enables the probing of near-surface thermal properties. The technique was applied to measure the thermal conductivity of a thin ion-irradiated layer on a tungsten substrate, which was found to decrease by nearly 60% relative to pristine tungsten for a Cu ion dosage of 0.2 dpa.
Related Topics
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Nuclear Energy and Engineering
Authors
Edward Dechaumphai, Joseph L. Barton, Joseph R. Tesmer, Jaeyun Moon, Yongqiang Wang, George R. Tynan, Russell P. Doerner, Renkun Chen,