哈尔滨工程大学学报2026，Vol.47Issue(7)：1408-1417,10.DOI:10.11990/jheu.202507048
基于可视化交互式核动力系统瞬态分析程序的先进压水堆蒸汽发生器传热管破裂事故
Research on steam generator heat transfer tube rupture accidents in advanced pressurized water reactors based on VITARS
摘要
Abstract
Steam generator heat transfer tube rupture(SGTR)accidents primarily involve the dynamic response of the re-actor coolant system following tube failure,as well as the associated responses of auxiliary and safety systems.In this study,the visual interactive transient analysis code for reactor system(VITARS)was employed to develop an accident analysis model for an advanced pressurized water reactor(PWR),and SGTR accidents in a U-tube steam generator were simulated.Building upon the analysis of single-tube rupture events,multi-tube rupture accidents were further investigated to evaluate the operational limits of the nuclear power plant.In addition,beyond-design-basis accidents,including SGTR combined with loss of offsite power(LOOP)or complete loss of feedwater,were analyzed.The results indicate that more se-vere consequences occur when the rupture is located at the tube inlet under an initial condition of 5%nominal power(NP).No steam generator overfill is observed when fewer than four tubes are ruptured.Moreover,as the number of failed tubes increases,the total amount of steam discharged to the atmosphere from the affected steam generator decreases.In the case of a single-tube SGTR accident with LOOP,the reactor coolant system parameters remain within safe limits,thereby providing sufficient time for operator intervention.关键词
压水堆核电厂/热工水力/安全分析/反应堆冷却剂系统/辅助给水系统/二次侧非能动余热排出系统/蒸汽发生器传热管破裂事故/失去厂外电源事故/完全丧失给水事故分类
能源科技引用本文复制引用
卢国庆,肖千喜,陈荣华,田文喜,秋穗正..基于可视化交互式核动力系统瞬态分析程序的先进压水堆蒸汽发生器传热管破裂事故[J].哈尔滨工程大学学报,2026,47(7):1408-1417,10.基金项目
国家自然科学基金面上项目(12275205). （12275205）
