首页> 中文期刊> 《科技创新导报》 >小型压水堆小破口失水事故诱发的严重事故序列分析

小型压水堆小破口失水事故诱发的严重事故序列分析

         

摘要

Lose of Coolant Accident(LOCA) is one of the main inducements of PWR(Pressurized Water Reactor) severe accident and it should be intensively protect against. Based on the method of combination of event tree and deterministic analysis, the severe accident sequence induced by a small LOCA was analyzed. Firstly, the uncertainty of the severe accident sequence after a small LOCA was found out, which was based on the event tree analysis. Secondly, based on the SCDAP-RELAP5 code, the response characteristic of the main latent parameter in different accident consequence was simulated. The accident consequence that can result in core melt was given out and the vulnerable spot of coping with small PWR severe accident was ascertained, which will provide a scientific base in making related prevention measures and improving the ability of deal with a severe accident.%小型压水堆冷却剂丧失事故(LOCA,Lose of Coolant Accident)是诱发反应堆堆芯熔化的主要初因之一,需要重点防范应对.为分析确定小破口失水事故诱发的严重事故序列,论文首先基于事件树分析方法研究小破口失水事故可能的响应序列,然后基于SCDAP-RELAP5程序模拟计算不同事故序列下系统主要特征参数的响应特征,确定导致堆芯熔化的事故序列,给出小型压水堆应对严重事故的薄弱环节,为后续有针对性地制定预防措施提供了科学依据.

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