首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >THE RD PERFROI PROJECT ON THERMAL MECHANICAL AND THERMAL HYDRAULICS BEHAVIORS OF A FUEL ROD ASSEMBLY DURING A LOSS OF COOLANT ACCIDENT
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THE RD PERFROI PROJECT ON THERMAL MECHANICAL AND THERMAL HYDRAULICS BEHAVIORS OF A FUEL ROD ASSEMBLY DURING A LOSS OF COOLANT ACCIDENT

机译:损失冷却剂过程中燃料棒组件热力学和热力学行为的研发绩效项目

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The safety principle in case of a LOCA is to preserve the short and long term coolability of the core. The associated safety requirements are to ensure the resistance of the fuel rods upon quench and post-quench loads and to maintain a coolable geometry in the core. An R&D program has been launched by IRSN with the support of EDF, to perform both experimental and modeling activities in the frame of the LOCA transient, on technical issues such as: 1. flow blockage within a fuel rods bundle and its potential impact on coolability, 2. fuel fragment relocation in the ballooned areas: its potential impact on cladding PCT (Peak Cladding Temperature) and on the maximum oxidation rate, 3. potential loss of cladding integrity upon quench and post-quench loads. The PERFROI project (2014-2019) focusing on the first above issue, is structured in two axes: 1. axis 1: thermal mechanical behavior of deformation and rupture of cladding taking into account the contact between fuel rods; specific research at LaMCoS laboratory focus on the hydrogen behavior in cladding alloys and its impact on the mechanical behavior of the rod; 2. axis 2: thermal hydraulics study of a partially blocked region of the core (ballooned area taking into account the fuel relocation with local over power), during cooling phase by water injection; More detailed activities foreseen in collaboration with LEMTA laboratory will focus on the characterization of two phase flows with heat transfer in deformed structures.
机译:对于LOCA,安全原则是保持芯的短期和长期可冷却性。相关的安全要求是确保燃料棒在淬火和骤冷后的载荷下具有抵抗力,并在堆芯中保持可冷却的几何形状。 IRSN在EDF的支持下启动了一项研发计划,以在LOCA瞬变的框架内进行实验和建模活动,涉及的技术问题包括:1.燃料棒束内的流量阻塞及其对冷却性的潜在影响,2.气球碎片在膨胀区域的迁移:它对包层PCT(峰值包层温度)和最大氧化速率的潜在影响,3.淬火和淬火后载荷对包层完整性的潜在损失。针对上述第一个问题的PERFROI项目(2014-2019年)分为两个轴:1.轴1:考虑到燃料棒之间的接触,热变形和包壳破裂的热力学行为; LaMCoS实验室的具体研究集中在熔覆合金中的氢行为及其对棒的机械行为的影响; 2.轴2:在注水冷却阶段,对岩心部分受阻区域(考虑到局部功率过大而考虑到燃料重新分配的区域)进行热力水力研究;预计与LEMTA实验室合作开展的更详细的活动将集中于在变形结构中进行传热的两相流的表征。

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