为合理验证并提高堆舱系统的安全性，本文采用RELAP5和MELCOR程序联合建立了浮动电站反应堆、主系统和堆舱的热工水力分析模型（包含关键的控制信号），可模拟从事故始发直至堆舱响应趋于稳定的瞬态全过程。计算结果表明，研究对象的堆舱系统满足事故下的热工设计要求，且容量配置具有一定的安全裕量。在此基础上，对给水系统隔离、堆舱自由容积、非能动热阱和堆舱喷淋系统等重要影响因素开展敏感性分析。结果表明，控制策略、堆舱安全系统的容量配置能够直接影响事故缓解措施的优劣和安全裕量，通过优化堆舱自由容积和舱内安全系统容量分配比，可进一步提高核动力装置的可靠性和总体安全性。上述结论对于堆舱的设计改进具有一定的工程指导意义。
In order to verify and improve the safety of reactor compartment system, a thermal-hydraulic transient analysis model, includes reactor facility, primary system, reactor compartment with its system and necessary control signals, utilizing both RELAP5 and MELCOR code, is established for a typical marine nuclear power plant (MNPP). It is concluded that the system configuration of reference reactor compartment meets the design requirements, and it has a certain margin of safety. Besides, sensitivity analysis are developed, involving key factors like the timing of feed-water isolation, reactor compartment free volume, capacity of passive structures and the timing of spray system actuation. Results show that, the control strategy and safety system capacity play a vital role in accident mitigation. It is suggested that the ratio between reactor compartment free volume and capacity of safety-related system can be optimized, to enhance reliability and general safety of the MNPP. Results in this study have some instructive value for the improvement of reactor compartment in engineering.
2019,41(10): 84-88 收稿日期：2018-11-12
DOI：10.3404/j.issn.1672-7649.2019.10.016
分类号：P751
基金项目：国家重点研发计划资助项目（2017YFC0307800-06）
作者简介：王珏(1989-),男,博士研究生,研究方向为核科学与技术
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