Studying the effects of radiation damage on tungsten (W), a primary candidate material for plasma facing components (PFCs), is of great significance in the thermal management of future fusion reactors. Investigation of accumulation and annihilation of radiation defects under ion irradiation in tungsten offers insights in selecting operational conditions in future fusion reactor designs. Here we investigate the dosage and irradiation temperature dependence on thermal conductivity (κ) of W under fusion-relevant radiation conditions by using an improved 3ω technique. Our results show a significant reduction in κ for W irradiated at room temperature with energetic (MeV) heavy ions. The damage, quantified by displacement per atom (dpa), spanned from 10⁻³ to 0.6 dpa for Cu ions and 0.2 dpa for W ions. With increasing Cu ion damage level, κ decreased and reached a minimum of 52 ± 13.6 W/m·K at 0.6 dpa, ∼30% of κ for pristine W. When the ion irradiation was performed at 1000 K, which is a temperature that is sufficiently high to induce significant dynamic annealing in W, κ was largely recovered to around 80% of the pristine value. We attribute this κ recovery to the thermal annealing and annihilation of the irradiation induced defects, i.e. through vacancy/self-interstitial atom (SIA) recombination. This finding is consistent with our prior observation of defect recovery probed by deuterium retention.

研究辐射损伤对钨（W）的影响，钨是面向等离子体组件（PFC）的主要候选材料，在未来聚变反应堆的热管理中具有重要意义。钨离子辐射下辐射缺陷的积累和an灭的研究提供了在未来聚变反应堆设计中选择运行条件的见识。在这里，我们通过使用改进的3ω技术研究在熔融相关辐射条件下W的剂量和辐照温度对W的热导率（κ）的依赖性。我们的结果表明，室温下用高能（MeV）重离子辐照的W的κ显着降低。用每原子位移（dpa）量化的损伤范围为10 ^-3对于Cu离子为0.6 dpa，对于W离子为0.2 dpa。随着Cu离子损伤水平的增加，κ降低，在0.6 dpa时，κ最低达到52±13.6 W / m·K，是原始W的κ的约30％。当在1000 K的温度下进行离子辐照时，当κ足够高以引起W中显着的动态退火时，κ大部分被回收到原始值的约80％。我们将此κ恢复归因于辐射退火缺陷的热退火和an灭，即通过空位/自填隙原子（SIA）重组。这一发现与我们先前通过氘保留探测到的缺陷恢复的观察结果一致。