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PSA-BASED DESIGN EXTENSION OF EXISTING PWR PLANT AND APPLICATION IN THE DESIGN OF ADVANCED PWR PLANT

机译:基于PSA的现有PWR工厂设计扩展及其在先进PWR工厂设计中的应用。

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After Fukushima, the design of nuclear power plants to cope with beyond design basis accidents and severe accidents is urgently needed to be improved. That means the previous design envelope scope needs to be optimized and extended. Some accident conditions which may be less probable but still with obvious risk should be enveloped into advanced nuclear power plant design consideration. As an effective tool to evaluate the progression of various accidents and corresponding management measures, probabilistic safety analysis (PSA) can be used to evaluate the vulnerabilities of the plants' safety during different accident scenarios. In this paper, firstly both level 1 and level 2 PSA modeling are carried out for Fuqing Phase I nuclear power plant. According to the PSA calculation results of this typical generation II plant designed in China, a series of beyond design basis accident and severe accident scenarios may cause unacceptable core damage and radiological release frequencies that will violate the requirement of the newly-issued design safety code HAF102 in China. For China's newly-designed evolutionary type advanced PWR plant, in order to achieve the high design safety level stated in HAF102, these non-negligible scenarios should be enveloped into plant's design basis. By introducing these conditions into new design envelope scope, finally a series corresponding new safety design features are suggested for China's advanced nuclear power plant.
机译:在福岛之后,迫切需要改进核电厂的设计,以应对超出设计基准的事故和严重事故。这意味着需要优化和扩展以前的设计范围。某些不太可能发生但仍具有明显风险的事故情况应纳入先进核电站的设计考虑范围。作为评估各种事故进展和相应管理措施的有效工具,概率安全分析(PSA)可用于评估不同事故场景下工厂安全的脆弱性。本文首先对福清一期核电厂进行了1级和2级PSA建模。根据在中国设计的典型第二代工厂的PSA计算结果,一系列超出设计基准的事故和严重事故场景可能会导致不可接受的核心损坏和放射线释放频率,这将违反新发布的设计安全规范HAF102的要求在中国。对于中国新设计的进化型先进压水堆电厂,为了达到HAF102中规定的高设计安全水平,这些不可忽略的情况应纳入电厂的设计基础。通过将这些条件引入新的设计范围,最后为中国的先进核电站提出了一系列相应的新安全设计特征。

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