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FUEL ROD MELT PROGRESSION SIMULATION USING LOW-TEMPERATURE MELTING METAL ALLOY

机译:使用低温熔融金属合金燃料杆熔体进展仿真

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The TMI-2 accident and various severe fuel damage experiments have shown that core damage is likely to proceed through various states before the core slumps into the lower head. Numerous experiments were conducted to address when and how the core can lose its original geometry, what geometries are formed, and in what processes the core materials are transported to the lower plenum of the reactor pressure vessel. Core degradation progresses along the line of clad ballooning, clad oxidation, material interaction, metallic blockage, molten pool formation, melt progression, and relocation to the lower head. Relocation into the lower plenum may occur from the lateral periphery or from the bottom of the core depending upon the thermal and physical states of the pool. Determining the quantities and rate of molten material transfer to the lower head is important since significant amounts of molten material relocated to the lower head can threaten the vessel integrity by steam explosion and thermal and mechanical attack of the melt. In this paper the focus is placed on the melt flow regime on a cylindrical fuel rod utilizing the LAMDA (Lumped Analysis of Melting in Degrading Assemblies) facility at the Seoul National University. The downward relocation of the molten material is a combination of the external film flow and the internal pipe flow. The heater rods are 0.8 m long and are coated by a low-temperature melting metal alloy. The electrical internal heating method is employed during the test. External heating is adopted to simulate the exothermic Zircaloy-steam reaction. Tests are conducted in several quasi-steady-state conditions. Given the variable boundary conditions including the heat flux and the water level, observation is made for the melting location, progression, and the mass of molten material. Finally, the core melt progression model is developed from the visual inspection and quantitative analysis of the experimental data. As the core material relocates downwards a blockage may be formed and grow both radially and axially. The velocity of the melt can be calculated from a force balance between the gravity and frictional losses at the melt-rod interface. When the heater rod is uncovered completely, the melt progression is initiated at the mid-point, which is the hot spot in the rod. However, the melting location is elevated as the water level rises because of the downward heat transfer. Considering the melt flow as a film, the steady-state film thickness on the cylindrical heater rod and the average velocity are computed. The steady-state film flow rate is determined in terms of the density, film thickness, and film velocity.
机译:TMI-2事故和各种严重的燃料损坏实验表明,核心损坏可能在核心坍塌进入下部头之前通过各种状态进行。进行了许多实验,以解决核心何时以及如何失去其原始几何形状,形成几何形状,并且在核心材料被传送到反应器压力容器的下层气内的过程中。核心退化沿着碎屑膨胀,包层氧化,材料相互作用,金属堵塞,熔融池地层,熔体进展和重新安置到下部头部。根据池的热和物理状态,从横向周边或核心底部发生在较低增压室中可能发生。确定熔融材料转移到下部头部的量和速率是重要的,因为重新迁移到下部头部的大量熔融材料可以通过蒸汽爆炸和熔体的热和机械攻击来威胁血管完整性。本文在首尔国立大学利用LAMDA(熔化的熔化熔化的熔化分数)设施,将重点放在圆柱形燃料棒上的熔体流动状态。熔融材料的向下迁移是外膜流动和内管流的组合。加热器杆长0.8米,并通过低温熔融金属合金涂覆。在测试期间采用电气内部加热方法。采用外部加热来模拟放热锆铝蒸汽反应。测试在几种准稳态条件下进行。考虑到包括热通量和水位的可变边界条件,对熔化的位置,进展和熔融材料质量进行观察。最后,核心熔体进展模型是从实验数据的目视检查和定量分析中开发的。由于芯材向下重新定位,可以径向和轴向地形成堵塞和生长。熔体的速度可以根据熔体杆界面处的重力和摩擦损失之间的力平衡来计算。当加热器杆完全露出时,在中点开始熔体进展,这是杆中的热点。然而,由于水位因下降传热而升高,熔化位置升高。考虑到作为膜的熔体流动,计算圆柱形加热器杆上的稳态膜厚度和平均速度。在密度,膜厚度和薄膜速度方面确定稳态膜流量。

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