高温气冷堆非能动舱室冷却系统排热功率计算分析

Heat Removal Power Analysis of HTR-PM Passive Reactor Cavity Cooling System

  • 摘要: 非能动舱室冷却系统(RCCS)是模块式球床高温气冷堆(HTR-PM)的重要安全设施,准确预测事故工况下其与反应堆压力容器间的传热量对于RCCS设计具有重要意义。本文依托HTR-PM热态调试阶段反应堆压力容器壁面温度分布,采用计算流体动力学(CFD)方法,开展了RCCS全比例三维辐射传热及对流换热模拟。结果显示,Realizable k-ε湍流模型与Discrete Ordinates辐射传热模型可准确预测RCCS的排热功率,数值结果与测量结果相对误差在10%左右。基于THERMIX程序计算得到的事故工况后反应堆压力容器壁面温度分布,计算分析了投入不同列数RCCS及不同冷却水温度下的排热功率,并给出了不同工况时水冷壁与混凝土温度分布计算结果。

     

    Abstract: Passive reactor cavity cooling system (RCCS) is an important safety related facility for high-temperature gas-cooled reactor pebble-bed module (HTR-PM). This system is responsible for cooling and protecting the reactor cavity and reactor pressure vessel (RPV). Without any active equipment or human intervention, RCCS can passively remove reactor cavity heat to the ultimate heat sink (atmosphere) by radiation, convection and natural circulation. Considering the safety redundancy, RCCS is divided into three independent units. According to the design requirements of HTR-PM, two units can fulfil the heat removal capacity. In normal operation and accident conditions, about 500 kW and 1 200 kW of heat is needed to be removed respectively. Moreover, the concrete temperature should be controlled below 175 ℃ in accident conditions. Therefor, accurately predicting the heat removal power from RPV to RCCS is important for its thermal hydraulic design. Based on the measured RPV wall temperature distribution during the commissioning of HTR-PM, computational fluid dynamics (CFD) method was used to perform a three-dimensional full-scale simulation of the convection and radiation heat transfer between RCCS water-cooling wall and RPV. The numerical results verify that Realizable k-ε turbulence model and discrete ordinates radiation heat-transfer model can accurately predict the heat removal power of RCCS, with a relative error of about 10%. In normal operation, only one unit of RCCS can remove the heat power greater than 500 kW. Under accident condition, two units of RCCS can remove the heat power of about 1 200 kW. As for the temperature distribution of its water-cooling wall, the maximum temperature difference in the transverse direction is about 33 ℃. Furthermore, the effect of cooling water temperature on the heat removal power of RCCS is evaluated in the case of two units of RCCS in operation. For accident condition, when the cooling water temperature increases from 10 ℃ to 100 ℃, the heat removal power can reduce by 380 kW, i.e., it decreases from 1 288 kW to 906 kW. The concrete temperature is always below 105 ℃, which is lower than the design limitation. In summary, RCCS meets the heat removal requirements of HTR-PM, which can effectively cool and protect the reactor cavity and RPV under both normal and accident conditions.

     

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