Multiphysics study on phase separation and thermal aggregation effects in the melt pool of the reactor lower head under severe accidents

Zongyan Bai , Tao Zhou , Mubashar Zaman , Yao Yao , Peng Liu
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Abstract

In the progression of severe accidents in light water reactors, the retention of core melt in the reactor pressure vessel (RPV) lower head, known as In-Vessel Retention (IVR), constitutes a core strategy for ensuring nuclear power plant safety and preventing large-scale release of radioactive materials. Targeting the complex multi-component liquid-liquid phase separation phenomena within the melt pool and the resulting “thermal focusing effect,” a coupled phase-field-flow-heat transfer multiphysics model based on free energy functionals was established. By simultaneously solving the Cahn-Hilliard equation, incompressible Navier-Stokes equations, and energy conservation equation in a two-dimensional axisymmetric domain, the dynamic evolution of a U–Zr–Fe–O quaternary system from an initially random uniform mixture to a macroscopic stratified state within the RPV lower head was simulated. Results demonstrate that the melt pool, driven by decay heat and interfacial energy, undergoes a “labyrinthine” bicontinuous structure evolution initiated by spinodal decomposition, ultimately forming a stable bilayer structure with a light metal layer above and a heavy oxide layer below under gravitational effects. The flow field evolves from initial small-scale chaotic convection (maximum velocity 0.0541 m/s) to large-scale circulation driven by thermal buoyancy (maximum velocity 0.00192 m/s), forming a stable configuration with an active upper convection zone and a stagnant lower dead zone. Due to the significant thermal conductivity contrast between the two stratified layers, wall heat flux exhibits a notable increase at the metal-oxide interface region, with peak heat flux reaching approximately 0.9 × 106 W/m2 during mid-evolution, attaining 60% of the upper CHF limit from ULPU experiments, posing a potential threat to IVR safety margins. Quantitative analysis of the phase separation time scale and its impact on wall thermal loading was conducted, providing numerical evidence and theoretical support for IVR safety margin assessment.
严重事故下反应堆下压头熔池相分离和热聚集效应的多物理场研究
在轻水反应堆严重事故的发展过程中,堆芯熔体在反应堆压力容器(RPV)下水头的滞留,即容器内滞留(IVR),是确保核电站安全和防止放射性物质大规模泄漏的核心策略。针对熔池内复杂的多组分液-液分离现象及其产生的“热聚焦效应”,建立了基于自由能泛函的相场-流-传热耦合多物理场模型。通过在二维轴对称域中同时求解Cahn-Hilliard方程、不可压缩Navier-Stokes方程和能量守恒方程,模拟了U-Zr-Fe-O四元体系在RPV下水头内从初始随机均匀混合物到宏观分层状态的动态演化过程。结果表明,在衰变热和界面能的驱动下,熔池在重力作用下,经历了一个由独立分解引发的“迷宫式”双连续结构演化,最终形成了上轻金属层下重氧化层的稳定双层结构。流场由初始的小尺度混沌对流(最大速度为0.0541 m/s)演变为热浮力驱动的大尺度环流(最大速度为0.00192 m/s),形成上层对流区活跃、下层死区停滞的稳定格局。由于两层之间的热导率差异显著,金属-氧化物界面区域的壁面热流密度显著增加,在演化中期热流密度峰值约为0.9 × 106 W/m2,达到ULPU实验中CHF上限的60%,对IVR安全边际构成潜在威胁。定量分析了相分离时间尺度及其对壁面热载荷的影响,为IVR安全裕度评价提供了数值依据和理论支持。
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