|About this Abstract
||2017 TMS Annual Meeting & Exhibition
||Energy Materials 2017: Materials for Nuclear Energy
||Thermal Conductivity Reduction of Tungsten Plasma Facing Material Due to Helium Plasma and Cu2+ Ion Irradiation
||Shuang Cui, Michael Simmonds, Joseph Barton, Yongqiang Wang, Russ Doerner, George Tynan, Renkun Chen
|On-Site Speaker (Planned)
Near-surface region of plasma facing material (PFM) plays an important role in thermal management of fusion reactors. We extracted thermal conductivity of tungsten (W) surface layer damaged by He plasma in PISCES at UCSD and Cu2+ ion beam at LANL with adopted 3-omega method (bulk) and Wiedemann-Franz law (thin film). Results showed that thermal conductivity in the He-plasma damaged layers (bulk and thin film) was reduced by ~80% compared to that of undamaged W. Moreover, Cu2+ ion irradiation is performed on W bulk to mimic neutron displacement damage. Results show that the thermal conductivity of irradiated surfaces (1um thick) drops from the un-irradiated value of 182±3.3 Wm-1K-1 to 37 ±2.8 Wm-1K-1 for 2dpa, 50±7.8 Wm-1K-1 for 0.6 dpa, 52.5±8 Wm-1K-1 for 0.2 dpa irradiated at 500 oC. Our result suggests that suppressed thermal conductivity in PFM needs to be taken into account in the thermal design of future plasma-facing components.
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