中国抗中子辐照钢的抗辐照设计与验证

Design and Verification of Irradiation Resistance Property of China Low Activation Martensitic Steel

  • 摘要: 聚变堆等未来先进核能系统要求材料在强流高能中子辐照下长期保持良好的结构稳定性和机械性能。为适应未来先进核能技术发展的需要,中国科学院核能安全技术研究所•凤麟团队牵头研发了具有我国自主知识产权的中国抗中子辐照钢——CLAM钢。CLAM钢的设计考虑了未来核能清洁性的要求,以及苛刻服役环境中材料抗辐照、耐高温、耐腐蚀等性能要求。通过中子学计算分析设计了低活化成分范围,基于选择性纳米相析出进行了抗辐照、耐高温性能优化设计。针对材料的抗辐照性能,利用国内外中子、离子、电子及等离子体辐照设施开展了系列辐照考验研究,通过多角度表征辐照前后材料的微观结构和宏观性能,综合评估了材料的辐照性能,并与国际上同类材料在相近或相同条件下的辐照性能进行了对比分析,结果表明CLAM钢具有良好的抗辐照性能。

     

    Abstract: Future advanced nuclear energy systems such as fusion reactors require materials to maintain good structural stability and mechanical properties for a long time under high-flux high-energy neutron irradiation. In order to satisfy the requirements of the development of future advanced nuclear energy technology, the China Low Activation Martensitic (CLAM) steel was developed by the FDS Team, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, under wide domestic and overseas collaborations. In the design of CLAM steel, following features were considered according to the property requirements such as low activation, intense irradiation resistance, and high temperature and corrosion resistance of the service environments in advanced nuclear energy. The low activation compositions were designed with neutron activation analysis, while neutron irradiation and heat resistance properties were designed and optimized by a selective nano-precipitation mechanism. To evaluate the irradiation performance of CLAM steel, a series of irradiation tests were carried out by using neutron, ion, electron and plasma irradiation facilities both in China and overseas. The microstructures and macroscopic properties before and after irradiation were multi-perspective analyzed. The irradiation resistance properties of CLAM steel were compared with those of the similar materials developed in other countries. The results show that CLAM steel has good irradiation resistance.

     

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