压水堆核电厂事故工况下最大上充流量的数值研究

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Numerical Investigation of Maximum Charging Flowrates under Accident Condition in PWR Nuclear Power Plants

摘要: 使用计算流体软件Flowmaster 7.5模拟了某压水堆核电站的化学和容积控制系统(RCV)以及安全注入系统(RIS)。通过将正常工况下的模拟计算结果与设计参考值进行对比,验证了模型的可靠性。使用该模型预测了发生蒸汽发生器传热管破裂事故(SGTR)后安全注入模式转为上充模式时最大上充流量与一回路压力的关系,并定量比较了采用不同数量的低压安注泵为上充泵增压时最大上充流量和相应主泵密封注入流量与一回路压力的关系。
- 压水堆 /
- 蒸汽发生器传热管破裂 /
- 计算流体 /
- 一回路系统 /
- 化学和容积控制系统 /
- 安全注入系统
Abstract: RCV System and RIS System are simulated with CFD software Flowmaster7.5,and the model is validated with design data.The relationship between maximum charging flowrates and Reactor Coolant System pressure is predicted by this model,when the safety injection mode switches to the charging mode after SGTR,and the relationship between the maximum charging flowrates and the corresponding Reactor Coolant Pump Seal Injection and the Pressure of Reactor Coolant System are quantitatively compared,when the charging pump is pressurized by various low voltage safety injection pumps.
- WR /
- SGTR /
- CFD /
- Reactor coolant system /
- RCV /
- RIS