1-02超临界水堆包壳管用低活性马氏体钢的制备与性能研究.pdfVIP

超临界水堆包壳管用低活性马氏体钢的制备与性能研究1 黎兴刚，杨英，马荣，燕青芝，葛昌纯，王浩强，李明 北京科技大学核材料研究所，北京，100083 xing-gangli@163.com qingzhiyan111@163.com Tel: 86-010 Fax: 86-010 摘要： 超临界水堆运行于超高压力、高温和强烈中子辐照条件下，常规水冷动力堆的燃料包壳 材料的力学特性和化学性能已不再满足超临界水堆的要求。国内外认为奥氏体不锈钢、铁素 体/马氏体钢、镍基合金可以作为超临界水堆包壳的候选材料。在分析合金元素对材料微观组 织影响的基础上，综合考虑材料的高温腐蚀与蠕变、辐照损伤等因素，确定选择合适的 Cr 与 W 含量，挖掘和添加低活性有效微量元素，开发出 12Cr3W 低活性铁素体/马氏体钢。其 制备流程为真空感应熔炼→热加工→热处理，本文对其辐照前的微观组织、拉伸性能、冲击 韧性等进行了初步研究。 Abstract Operating conditions of supercritical water cooled reactor system is different from those of light water reactor and mainly characterized as high system pressure, high operating temperature and intense neutron irradiation. Zircaloy that has been widespread applied as cladding material in conventional light water reactors is no more available in SCWR due to its low resistance in thermal and corrosion. Austenite stainless steels, F/M steels and nickle alloys have been considered as alternative fuel cladding material of SCWR. Based on the element effect on phase balancing, 12Cr-3W steels were developed by optimizing W and Cr content and the idea of low-activation materials and microalloy technology were introduced into the design of the steels for fission reactors. The fabrication process includes melting in a vacuum induction furnace → thermomechanical treatment→normalizing and tempering treatment. The preliminary investigation was conducted in microstructure, tensile properties and impact toughness for pre-irradiated 12Cr-3W steels. 前言 包壳是核裂变反应堆中工况最苛刻的重要部件，其内壁面临着强烈的中子辐照、裂变气 体压力与腐蚀、燃料肿胀、吸氢致脆和包壳与芯块相互作用等危害，外壁受到冷却剂压力、 冲刷、振动和腐蚀以及氢脆等威胁[1] 。因此，对包壳材料的各项性能（如核性能、耐腐蚀性 1基金项目：973计划（编号：2007CB209800） 能、辐照性能等）的要求，比堆内其他元件要严格很多。 反应堆从亚临界工况跨越到超临界工况（500~650℃，25~30MPa ），常规水冷动力堆