Published in

Elsevier, Journal of Nuclear Materials, 1-3(455), p. 56-60, 2014

DOI: 10.1016/j.jnucmat.2014.03.059

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Near-surface thermal characterization of plasma facing components using the 3-omega method

This paper is available in a repository.
This paper is available in a repository.

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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.