论文部分内容阅读
1 前言 安全壳是核电站反应堆的最后一道安全屏障,对核电的安全至关重要。根据国际原子能机构为规定和国际惯例,核电站建成后,必须经过安全壳结构整体性试验（SIT）,检验安全壳在构造、强度和施工质量方面承受失水事故工况的能力。检测评定合格,方能装料发电。 安全壳结构检测项目（SIT）,除测试传感器、数据采集处理等试验技术外,还包括安全壳结构分析,实测与计算的吻合分析、安全评估等多项工作内容。 压水反应堆核电厂的安全壳有钢结构、钢筋混凝土结构、预应力混凝土结构几种形式,其中预应力混凝土结构由于性能好,近年来得到各核电国的重视。美、日、法等国家对该种安全壳,从原材料、节点构造到施工工艺、模型试验等进行过系统的试验研究。对于安全壳结构整体性试验（SIT）,也建立起一套较为完整的测试系统和技术制度,编制了相应的规程和标准。
1 Preface Containment is the last safety barrier of nuclear power reactors and is crucial for the safety of nuclear power. According to the International Atomic Energy Agency regulations and international practice, the completion of a nuclear power station must go through the SIT (Integrity Test of Containerized Structures) to test the ability of containment to withstand the loss of water in terms of structure, strength and construction quality. Testing and evaluation of qualified, before loading power generation. In addition to test technologies such as test sensors and data acquisition and processing, the containment structure inspection project (SIT) also includes a number of work contents including structural analysis of the containment, anastomosis analysis of actual measurement and calculation, and safety assessment. Containment of pressurized water reactor nuclear power plant contain steel structure, reinforced concrete structure, prestressed concrete structure in several forms, of which prestressed concrete structure due to good performance, in recent years by all nuclear power countries attention. The United States, Japan, France and other countries of the type of containment, from the raw materials, node structure to the construction process, model tests conducted a systematic experimental study. For the integrity of the containment structure test (SIT), but also to establish a more complete test system and technical system, the preparation of the corresponding rules and standards.