基于RELAP5的大功率非能动核电厂SGTR事故分析研究

本文应用RELAP5/mod3.3程序对大功率非能动核电厂进行建模,开展了蒸汽发生器传热管破裂事故(SGTR)分析研究,研究就事故造成的最大质量释放和破损SG最大水体积两种工况分别进行了计算。通过对两种工况计算结果的分析,发现虽然在不同工况条件下,系统参数变化和事故发展序列存在一定差异,但总体来讲,在SGTR事故过程中即使操纵员不干预,大功率非能动核电厂保护系统和非能动设计措施将会触发自动的响应措施,可终止蒸汽发生器(SG)传热管的泄漏,并将反应堆冷却剂系统(RCS)稳定在安全状态,能够防止SG发生满溢和自动降压系统动作,最终使放射性后果在可接受剂量水平限值范围内。

Research of High-power Passive Nuclear Power Plant SGTR Accident Based on RELAP5 Code

High-power Passive Nuclear Power Plant model is established using RELAP5/mod 3.3 code in detail. Refer to SGTR accident basic assumptions,research of High-power Passive nuclear power plant SGTR accident is carried out. The max mass release of the accident and damaged SG max water volume are taken into account in the research for calculations respectively. Through the analysis of the calculation results of the two situations,even though the system parameters changes and sequence of events have some difference at different situations,but overall even if the operators do not interfere,High-power Passive Nuclear Power Plant protection systems and passive design measures will trigger automatic response measures,it can terminate the SG heat transfer tube leaking and make RCS be stable in a safe condition and to prevent SG overflowing and ADS actions occurring.