基于子通道模型的超临界二氧化碳燃料组件热工特性分析

Thermal Characteristic Analysis of Supercritical CO2 Fuel Assembly Based on Sub-channel Model

  • 摘要: 为实现偏远地区小型核反应堆的供电,本文开发了超临界二氧化碳燃料组件子通道分析程序BRESA并对结果进行验证,并对程序进行了稳态和瞬态的特性分析。通过开发的二维子通道分析程序,能够得到热工水力参数在轴向和径向上的分布规律,稳态特性分析可以获得燃料组件空间上的热工水力参数,在稳态计算的基础上,分析了流量变化瞬态工况,在流量线性增加、线性减少和流量突变瞬态工况下,燃料组件各参数的响应特性,获得了焓和压力在空间上随时间的变化趋势。结果表明,在流量线性变化的瞬态工况下,焓和压力小幅变化;在流量突变的瞬态工况下,焓和压力发生突变和大幅波动,出口焓的波动最大达到12%,这对反应堆的安全运行造成了挑战。本文的研究结果为超临界二氧化碳反应堆系统的变工况研究提供理论支持和技术指导。

     

    Abstract: In order to realize the power supply of small nuclear reactors in remote areas, the sub-channel analysis program BRESA of supercritical carbon dioxide (S-CO2) fuel assembly based on Modelica language was developed in this paper. According to the fuel assembly model of 37 rods, the axial and radial physical and thermal parameters of S-CO2 fuel assembly were calculated, and the flow mixing effect between channels was introduced to obtain the distribution law of thermal hydraulics parameters in the axial and radial directions, The enthalpy rise and temperature rise changes of various typical channels were studied. The results show that the enthalpy rise and temperature rise changes of the channel in the middle of the fuel assembly are high, while the enthalpy rise and temperature rise changes of the channel at the edge of the fuel assembly are low. Through comparison with relevant literature, it is proved that the thermal hydraulic parameters of this study meet the design requirements and the correctness of the program is verified. On the basis of steady-state calculations, the transient conditions of flow rate changes were analyzed, and the response characteristics of various parameters of fuel assemblies under transient conditions of linear increase, linear decrease, and sudden change in flow rate were analyzed. The response characteristics of reactor power response and control system were investigated and analyzed, and the spatial variation trends of enthalpy and pressure with time were obtained. The results indicate that under transient conditions, the reactor power will vary with flow fluctuations, which is related to the negative feedback effect of the control system and temperature. The pressure and enthalpy values also fluctuate and change when the flow rate changes, which is influenced by the dual effects of flow rate and power changes. Under transient conditions of sudden flow changes, enthalpy and pressure undergo sudden and significant fluctuations, with the maximum fluctuation of outlet enthalpy reaching 12%, posing a challenge to the safe operation of the reactor. The research results of this paper provide theoretical support and technical guidance for the design and research of supercritical carbon dioxide reactor systems.

     

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