Corrosion and SCC resistant materials and chemistry for SCWR design

本提案涉及2012- 2016年发展优先事项，其中指出，“研究是 需要识别和测试可用于堆芯内和堆芯外的候选材料类别 组件，包括堆芯出口温度高达625°C的燃料通道设计和合适的燃料 包壳材料（正常运行时高达850°C，短镦粗时温度更高 条件）"，以及“材料性能需要在腐蚀和应力的关键区域得到证明 腐蚀开裂（SCC）以及蠕变等机械性能。“基于我们之前在 评估现有材料在加拿大预期条件下的性能， 超临界水反应堆（SCWR）的概念，并在确定机制的发生， 在SCWR条件下的腐蚀和SCC，目前的建议集中在重要的未解决的问题：1） 确定SCW性能在候选合金元素溶解中的作用;（2）开发 可靠的表面改性方法，以增强腐蚀防护;（3）了解 材料成分对腐蚀和SCC敏感性的影响;以及（4）通过生成 在SCWR条件下材料对腐蚀和SCC敏感性的要求信息。研究 将产生具有强大潜力的新知识/技术，以加强加拿大的核工业， 履行加拿大在GEN IV国际论坛（GIF）协议下的义务。这项研究将 与AECL和NRCan合作进行。这两个第四代研究的领先组织 和发展将直接有助于在提案中定义的研究工作，将提供指导， 研究方向，并将通过与该领域其他研究人员的协调提供协助。研究 该计划还将为核材料领域的许多高素质人员提供培训 和化学控制。

The present proposal addresses Development Priorities for 2012-16, in which it was stated that "research is required to identify and test classes of candidate materials that can be used for in-core and out-of-core components, including a fuel channel design for a core outlet temperature of up to 625°C and a suitable fuel cladding material (up to 850°C during normal operation and higher temperatures during short upset conditions)", and "material performance will need to be demonstrated in the key areas of corrosion and stress corrosion cracking (SCC), as well as mechanical properties such as creep." Based on our previous success on assessing existing materials in terms of their performance under the conditions expected in the Canadian supercritical water reactor (SCWR) concept and in determining the mechanisms governing the occurrence of corrosion and SCC under SCWR conditions, the current proposal focuses on important unresolved issues: 1) identify the role of SCW properties in the dissolution of elements from candidate alloys; (2) development of reliable methods of surface modification for enhanced corrosion protection; (3) understand the effects of materials composition on corrosion and SCC susceptibilities; and (4) expand the SCWR database by generating required information on material susceptibility to corrosion and SCC under SCWR conditions. The research will generate new knowledge/technology with a strong potential to strengthen Canada's nuclear industry and to fulfill Canada's obligations under the GEN IV International Forum (GIF) agreement. The research will be conducted in collaboration with AECL and NRCan. These two leading organizations in Generation IV research and development will contribute directly to the research work defined in the proposal, will provide guidance on the direction of research, and will assist through coordination with other researchers in the field. The research program also will provide training for a number of highly qualified personnel in the areas of nuclear material and chemistry control for SCWR.