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核电站安全壳是核电厂最后一道核安全屏障,根据国际原子能机构的规定和国际惯例,安全壳投入使用必须经过结构强度试验和密封性试验。以CANDU堆型某电厂1号安全壳压力试验为蓝本,阐明应变测量技术在结构性能评估的应用;通过试验应变的测量以及与理论应变的比较分析,给出应变测量的具体影响因素、量值差异原因以及结构得以验证的试验与理论应变相吻合的结论;最后,文章给出了一种结构性能参数的具体计算方法,为结构在役性能评估提供了基础数据。
Nuclear power plant containment is the last nuclear safety barrier of nuclear power plant. According to the rules of the International Atomic Energy Agency and international practice, the containment must go through structural strength test and tightness test. Based on the CANDU reactor 1 pressure test of a power plant, the application of strain measurement technology in the structural performance assessment is expounded. Through the measurement of the test strain and comparison with the theoretical strain, the influence factors of the strain measurement, The reason of the difference and the test that the structure can be verified are consistent with the theoretical strain. Finally, the article gives a concrete calculation method of the structural performance parameters, which provides the basic data for evaluating the service performance of the structure.