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反应堆用的结构材料,特别是用在活性区中的锆合金和不锈钢等结构材料,必须经过严格的质量检查和试验,方能保证反应堆的安全可靠。核用材料的腐蚀试验方法际准化能达到质量保证和质量控制的目的。为了配合我国核电站的设计和建造,目前原子能研究所和西南反应堆工程研究设计院正在着手制定锆合金和不锈钢等结构材料在高温高压水或蒸汽中的腐蚀试验标准方法(草案)。本标准(草案)是参照国外有关标准和我国多年的实践经验制订的。
Structural materials used in reactors, especially structural materials such as zirconium alloys and stainless steels used in the active zone, must undergo stringent quality inspections and tests to ensure the reactor is safe and reliable. Corrosion of nuclear materials used in the method of quasi-standardization can achieve the purpose of quality assurance and quality control. In order to cope with the design and construction of China’s nuclear power plants, Atomic Energy Research Institute and Southwest Institute of Reactors Engineering Research and Design Institute are currently working to develop standards (draft) test standard corrosion test of zirconium alloy and stainless steel and other structural materials in high temperature and pressure water or steam. This standard (draft) is formulated with reference to relevant foreign standards and years of practical experience in our country.