核聚变堆用钨表面超精密抛光的研究现状与趋势

Research Status and Trend of Ultra-precision Polishing on Tungsten Surface for Fusion Reactors

钨作为未来核聚变堆中最有前景的面向等离子体材料,在反应堆工况下将承受高能粒子的辐照冲击。表面质量的好坏会直接影响材料的氢/氦滞留行为和辐照损伤程度,进而影响聚变堆的安全性和可靠性。现阶段,针对钨的抗辐照改性研究主要着眼于材料的成分、结构和组织设计,关于机械加工对材料表面抗辐照改性的研究甚少。文章聚焦前沿科学问题,从机械加工角度分析核材料领域科学问题,结合国内外相关研究成果及核聚变堆用钨(PFM-W)的机械加工现状,阐述了PFM-W表面超精密抛光的必要性。通过对比不同抛光方法,提出了磁流变抛光和力流变抛光是较为适合PFM-W表面超精密加工的观点,并对未来PFM-W表面超精密抛光研究趋势进行了分析,重点在抛光方法的探索以及抛光后材料表面质量对抗辐照性能影响的研究。

Tungsten, as the most promising plasma facing material in the future fusion reactor, will withstand the irradiation impact of high energy particles under reactor condition. The surface quality of material will directly affect the hydrogen/helium retention behavior and the degree of radiation damage, thus affecting the safety and reliability of fusion reactor. At the present stage, the research on irradiation resistance modification of tungsten mainly focuses on the composition, structure and organization design of the material, few studies have been proceeded on the irradiation resistance modification of material surface. Focusing on the frontier scientific problems, the study intends to analyze the scientific problems in the field of nuclear materials from the perspective of mechanical processing, describes the necessity of ultra-precision polishing on the tungsten surface for nuclear fusion reactor based on the domestic and international research results and machining status of tungsten for nuclear fusion(PFM-W). Through comparing with different polishing methods, the viewpoint that magneto-rheological finishing and force-induced rheological polishing are more suitable for ultra-precision polishing of PFM-W surface. In addition, the future research trend of ultra-precision polishing of PFM-W surface is analyzed, with emphasis on the exploration of the polishing method and the influence of the surface quality of the polished material on the radiation resistance.