钨基面向等离子体材料的研究进展

朱玲旭^{1, 2}, 燕青芝¹，郎少庭¹，徐 磊¹，葛昌纯^{1, 2}

(1. 北京科技大学 核材料研究所，北京 100083；
2. 西南交通大学 材料科学与工程学院，成都 610031)

摘 要：综述了国内外广泛研究的W-La₂O₃和W-TiC合金的制备工艺、力学性能和辐照性能的研究进展。结果表明：向钨基体中加入La₂O₃弥散相，虽然能够显著改善钨的强度和韧性，但使钨的抗辐照性能降低，氢泡密度和氢滞留量明显增加；当采用TiC纳米颗粒作为弥散相，经过热等静压烧结和塑性加工后，钨合金的抗弯强度达到4.4 GPa，再结晶温度高于2 473 K，韧脆转变温度(DBTT)比纯钨的低100 K；TiC的加入能够显著提高钨的抗辐照性能，与纯钨相比，氚滞留量减小，没有明显的辐照硬化，材料表面没有裂纹和剥落。

关键词：钨基面向等离子体材料；弥散强化；辐照效应

Research progress of tungsten-base materials as plasma facing materials

ZHU Ling-xu^{1, 2}, YAN Qing-zhi¹, LANG Shao-ting¹, XU Lei¹, GE Chang-chun^{1, 2}

(1. Institute of Nuclear Materials, University of Science and Technology Beijing, Beijing 100083, China;
2. School of Materials Science and Engineering, Southwest Jiaotong University, Chengdu 6)

Abstract:Research progress on preparation process, mechanical properties and irradiation performance of W-La₂O₃ and W-TiC alloy was reviewed. The previous research results reveal that the addition of La₂O₃ phase into tungsten matrix improves the strength and toughness of tungsten remarkablely, and results in the reduction of irradiation resistance and increase in density of hydrogen blisters and hydrogen retention. When TiC nanoparticles are used as dispersion phase, W-TiC alloy worked by hot isostatic pressing sintering and plastic processing exhibits high bending strength of 4.4 GPa, high recrystallization temperature over 2 473 K and low DBTT (100 K lower than pure that of tungsten. In addition, the additon of TiC significantly improves the irradiation resistance of tungsten. Compared to pure tungsten, W-TiC alloy has a lower deuterium retention without visible irradiation hardening, crack and flaking on the material surface.

Key words:tungsten-base plasma facing material; dispersion strengthening; irradiation effect