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首页> 外文期刊>Nuclear Technology >PARAMETRIC STUDY OF SLOSHING EFFECTS IN THE PRIMARY SYSTEM OF AN ISOLATED LEAD-COOLED FAST REACTOR
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PARAMETRIC STUDY OF SLOSHING EFFECTS IN THE PRIMARY SYSTEM OF AN ISOLATED LEAD-COOLED FAST REACTOR

机译：隔离铅冷快反应堆主系统中晃动效果的参数研究

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摘要

Risks related to sloshing of liquid metal coolant due to seismic excitation need to be investigated. Sloshing effects on reactor performance include first, fluid-structure interaction and second, gas entrapment in the coolant with subsequent transport of void to the core region. While the first can hypothetically lead to structural damage or coolant spill, the second increases the risk of a reactivity insertion accident and/or local dryout of the fuel. A two-dimensional computational fluid dynamics study is carried out in order to obtain insights into the modes of sloshing depending on the parameters of seismic excitation. The applicability and performance of the numerical mesh and the Eulerian volume of fluid method used to track the free surface are evaluated by modeling a simple dam break experiment. Sloshing in the cold plenum free surface region of the European Lead-cooled SYstem (ELSY) conceptual pool-type lead-cooled fast reactor (LFR) is studied. Various sinusoidal excitations are used to imitate the seismic response at the reactor level. The goal is to identify the domain of frequencies and magnitudes of the seismic response that can lead to loads threatening the structural integrity and possible core voiding due to sloshing. A map of sloshing modes has been developed to characterize the sloshing response as a function of excitation parameters. Pressure forces on vertical walls and the lid have been calculated. Finally, insight into coolant voiding has been provided.
机译：需要研究与因地震激励而引起的液态金属冷却剂晃动有关的风险。对反应堆性能的晃动影响包括第一，流体-结构相互作用以及第二，气体滞留在冷却剂中，随后将空隙传输到堆芯区域。虽然第一种可能会导致结构损坏或冷却液溢出，但是第二种会增加反应性插入事故和/或燃料局部变干的风险。进行了二维计算流体动力学研究，以便根据地震激励的参数获得对晃荡模式的了解。通过模拟一个简单的溃坝实验，评估了数值网格的适用性和性能以及用于跟踪自由表面的流体欧拉体积方法。研究了欧洲铅冷系统（ELSY）概念池式铅冷快堆（LFR）在冷气室自由表面区域的晃动。各种正弦激励用于模拟反应堆一级的地震响应。目的是确定地震响应的频率和幅度域，该域可能导致载荷威胁结构完整性，并可能由于晃动而导致岩心空隙。已经开发了晃荡模式图，以将晃荡响应表征为激励参数的函数。计算了垂直壁和盖子上的压力。最后，提供了对冷却液排空的见解。

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  • 来源
    《Nuclear Technology》 |2015年第1期|1-10|共10页
  • 作者

    MARTI JELTSOV; WALTER VILLANUEVA; PAVEL KUDINOV;

  • 作者单位

    KTH Royal Institute of Technology, School of Engineering Sciences, Department of Physics Division of Nuclear Power Safety, Roslagstullsbacken 21, SE-106 91, Stockholm, Sweden;

    KTH Royal Institute of Technology, School of Engineering Sciences, Department of Physics Division of Nuclear Power Safety, Roslagstullsbacken 21, SE-106 91, Stockholm, Sweden;

    KTH Royal Institute of Technology, School of Engineering Sciences, Department of Physics Division of Nuclear Power Safety, Roslagstullsbacken 21, SE-106 91, Stockholm, Sweden;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    sloshing; lead-cooled fast reactor; computational fluid dynamics;

    机译：晃动铅冷快堆;计算流体动力学;

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