压水堆核电厂严重事故卸压阀能力评估

发布时间：2018-07-13 15:22

【摘要】：在百万千瓦级压水堆核电厂中为防止高压熔堆严重事故发生时发生高压熔喷(HPME)和安全壳直接加热(DCH),参考EPR堆型在稳压器上额外设置严重事故卸压阀(SADV),对主系统进行快速卸压。建立百万千瓦级压水堆核电厂事故分析模型,选取丧失厂外电叠加汽动辅助给水泵失效,一回路管道小破口以及丧失主给水三条典型严重事故序列,进行系统热工水力及卸压能力分析。计算结果表明:如果不开启严重事故卸压阀,三条事故序列在压力容器下封头失效时一回路压力均较高,有发生高压熔喷和安全壳直接加热的风险。根据严重事故管理导则开启严重事故卸压阀,可以有效降低一回路压力,三条事故序列均可以防止高压熔喷和安全壳直接加热发生。针对卸压阀阀门面积的影响进行分析,表明阀门面积减小到4.8×10-3 m2后下封头失效时RCS压力会有所增加,仍然能够满足RCS的卸压要求,且可延迟下封头失效时间。
[Abstract]:In order to prevent the occurrence of HPME and DCH in millions of kilowatts PWR nuclear power plants, the main system is relieved quickly by setting additional serious accident relief valve (SADV) on the voltage stabilizer with reference to EPR reactor. The accident analysis model of millions of kilowatt PWR nuclear power plants is established, and three typical serious accident sequences are selected, such as the failure of power superimposed steam auxiliary feedwater pump, the small break of primary circuit pipeline and the loss of main feed water. To analyze the thermohydraulic and pressure relief capacity of the system. The calculation results show that if the pressure relief valve is not opened, the first loop pressure of the three accident sequences is higher when the head of the pressure vessel fails, and there is the risk of high pressure melt spraying and direct heating of the containment. According to the guideline of serious accident management to open the pressure relief valve of serious accident, the pressure of primary circuit can be effectively reduced, and the three accident sequences can prevent the occurrence of high pressure melt spray and direct heating of containment. The effect of valve area on valve area of relief valve is analyzed. It is shown that when the valve area is reduced to 4.8 脳 10 ~ (-3) m ~ 2, the RCS pressure will increase when the valve head fails, which can still meet the pressure relief requirements of RCS and can delay the failure time of the lower head.
【作者单位】：上海交通大学机械与动力工程学院;
【基金】：国家自然科学基金(11205099)
【分类号】：TL364.4

【共引文献】