首页> 外文期刊>Nuclear Engineering and Design >Reflood experiments at elevated pressures using intact and deformed rod bundles to simulate small and medium break loss-of-coolant accidents
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Reflood experiments at elevated pressures using intact and deformed rod bundles to simulate small and medium break loss-of-coolant accidents

机译:使用完整和变形的棒束在高压下进行的驱油实验,以模拟中小型冷却液损失事故

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摘要

Reflood experiments at elevated pressures for small and medium break loss-of-coolant accidents were performed to investigate the influence of fuel deformation on the peak cladding temperature and local quenching behaviors. The typical experimental parameters such as initial water level, power, reflood rate, system pressure, initial wall temperature, and fluid temperature were varied to cover a wide range of flow conditions under a medium and high pressure. The experimental results showed remarkable differences in the peak cladding temperature and local quenching behaviors between the intact and deformed rod bundles due to the flow blockage effect. The present results implied that the fuel rod deformation can enhance the coolability of fuel rods by the flow blockage in the present fully blocked channel. Any bypass in a partially blocked channel may change those results due to a crossflow between intact and deformed rods. The experimental results were then used to validate the system analysis code, Multi-dimensional Analysis of Reactor Safety-KINS Standard (MARS-KS). The MARS-KS code showed good prediction of the present experimental data for most of the flow conditions.
机译:进行了针对中小断裂冷却剂损失事故的高压泄流实验,以研究燃料变形对峰值包层温度和局部淬火行为的影响。改变了典型的实验参数,例如初始水位,功率,回注率,系统压力,初始壁温和流体温度,以涵盖中压和高压下的各种流动条件。实验结果表明,由于流动阻塞的影响,完好的棒束和变形的棒束之间的峰值熔覆温度和局部淬火行为存在显着差异。本结果暗示燃料棒的变形可以通过在当前完全阻塞的通道中的流动阻塞来增强燃料棒的可冷却性。由于完整杆和变形杆之间的交叉流,在部分堵塞的通道中的任何旁路都可能改变这些结果。然后,将实验结果用于验证系统分析代码“反应堆安全性-KINS标准的多维分析”(MARS-KS)。 MARS-KS代码对大多数流动条件显示了对当前实验数据的良好预测。

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