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目前,核动力反应堆的压力容器主要按照ASME《锅炉和压力容器规范》第Ⅲ卷“核动力装置部件”来设计。本文详细分析了这部规范所采用的各项基本设计准则的理论依据,并指出了使用这些设计准则应注意的事项。由于这部规范对应力作了合理的分类,并对不同的应力规定了不同的设计准则,同时又广泛地采用了塑性失效和塑性分析的方法,所以能在较保守的安全系数下有效地提高部件的设计工作应力,达到既节约材料又确保安全可靠的目的。 规范所提出的各项基本设计准则,除疲劳以外,主要是防止过度的塑性变形,所以可统称为防止塑性失效分析。它和核容器的防止脆性破坏分析和防止疲劳分析一起,成为核容器防止破坏的安全设计分析的三项基本内容。
Currently, pressure vessels for nuclear power reactors are designed primarily in accordance with the “Part III Nuclear Power Plant Components” of the ASME Boiler and Pressure Vessel Code. This paper analyzes in detail the theoretical basis of each basic design criterion adopted by this specification and points out the points to be noticed when using these design criteria. Since this code classifies stresses reasonably and sets different design criteria for different stresses, and at the same time extensively applies methods of plastic failure and plasticity analysis, it is possible to effectively increase the number of components with a more conservative safety factor Design work stress, to achieve both the purpose of saving materials and ensure safety and reliability. In addition to fatigue, the basic design criteria proposed in the code are mainly to prevent excessive plastic deformation, so they can be collectively referred to as plastic failure analysis. Together with the prevention of brittle failure analysis and the prevention of fatigue analysis of nuclear containers, it has become the three basic elements of safety design analysis of nuclear containers to prevent damage.