解决人类能源问题的重要途径之一就是开发受热控核聚变能。在受热控核聚变反应堆装置中,钨作为优选最有前途的面向等离子体第一壁材料,具备这许多优良特性,如高熔点、高热导率、良好的高温强度等。然而钨基材料在离子中子辐照下会导致微观结构的改变,例如气泡、孔洞、纳米结构的形成。辐照还会导致材料硬化并使材料变脆。钨的辐照损伤问题是钨作为面向等离子体第一壁材料要重点解决的问题之一。通过改变材料的结构和成分设计可以改变钨的抗辐照性能。国内外许多研究人员对纯钨、碳化物掺杂钨、氧化物掺杂钨以及其他钨基材料的辐照损伤行为进行相关研究。对这些相关的研究进展和趋势进行综述。
One of the important way to solve the problem of human energy is to exploit controlled thermonuclear fusion energy. In controlled thermonuclear nuclear fusion reactor device, tungsten as the selection of the most promising for the first wall materials facing plasma have many good qualities, such as high melting point, high thermal conductivity, good high temperature strength, etc.However, the irradiation of ion and neutron for tungsten-matrix materials will lead to the change of microstructure, such as the formation of bubbles, holes, nanostructure. Irradiation can also make the materials hardening and become brittle. The irradiation damage problem of tungsten materials as the first wall materials facing plasma is one of the key problem to solve. By changing the structure and the composition design of tungsten materials can change its radiation resistance. Many researchers of home and aboard have studied the irradiation damage behavior for the pure tungsten, carbide doped tungsten, oxide doped tungsten and other tungsten-matrix materials. The progress and trends of these related studies are reviewed.