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Heat pipe failure accident analysis in megawatt heat pipe cooled reactor

机译:Megawatt热管冷却反应器中的热管故障事故分析

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摘要

The heat pipe cooled reactor is an advanced reactor design which is nearly solid-state with an array of in-core heat pipes for passive heat transfer. The local heat pipe failure probability is certainly high over the reactor lifetime. Therefore, the reactor design must include consideration of heat pipe failure accidents which needs to be explored in-depth. The Monte Carlo neutron transport code RMC was used with the general finite element analysis software ANSYS Mechanical to analyze the thermal/mechanical characteristics of a megawatt heat pipe cooled reactor for both normal and heat pipe failure conditions. The simulations were verified against a previous study with the predicted temperature distributions being consistent with each other with an absolute error of less than 3 K. Further analyses show that a 2-D model simulation can also well represent the 3-D model for heat pipe failure accident analyses. Sterbentz et al. (2017) simplified the heat pipe model with a constant temperature boundary condition along the evaporator wall of 950.15 K regardless of the heat load or heat pipe operating temperature. Therefore, a heat pipe subroutine was added to the codes to predict the heat pipe temperatures during a heat pipe failure accident. The results show that the heat pipe failure will cause larger temperature rises and stress concentrations. The heat pipe wall temperatures in the core differ from each other with the differences between the heat pipe loads during normal heat pipe operation and with failures reflecting the local effect of the heat pipe failures. The operating conditions far from the failure area are little affected (20 K temperature change) by a single heat pipe failure. The effects of the heat pipe failure on the reactor core reactivity and local power distribution were also analyzed with a reactivity change of less than 5 pcm and a local power change of less than 0.1%. Therefore, the heat pipe failure can be analyzed in steady-state simulations with unchanged power distributions. (C) 2020 Elsevier Ltd. All rights reserved.
机译:热管冷却反应器是一种先进的反应器设计,该设计几乎是固态的,具有用于被动传热的核心热管阵列。局部热管故障概率肯定高于反应器寿命。因此,反应器设计必须包括考虑需要深入探索的热管故障事故。 Monte Carlo中子传输代码RMC与通用有限元分析软件ANSYS机械一起使用,分析Megawatt热管冷却反应器的热/力学特性,用于正常和热管故障条件。通过以前的研究验证了模拟,预测温度分布彼此一致,绝对误差小于3k。进一步分析表明,2-D模型模拟也可以很好地代表热管的3-D模型失败事故分析。 Sterbentz等。 (2017)无论热负荷或热管操作温度如何,用950.15k的蒸发器壁简化了恒温边界条件的热管模型。因此,将热管子程序添加到码中以预测热管故障事故期间的热管温度。结果表明,热管故障会导致较大的温度升高和应力浓度。芯中的热管壁温度彼此不同,在常规热管操作期间的热管载荷之间的差异,并且反射热管故障的局部效果的故障。通过单一的热管故障,远离故障区域的操作条件很少受到影响(<20k温度变化)。还分析了热管故障对反应器核心反应性和局部配电的影响,反应性变化小于5pcm,局部功率变化小于0.1%。因此,可以以不变的功率分布在稳态模拟中分析热管故障。 (c)2020 elestvier有限公司保留所有权利。

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  • 来源
    《Annals of nuclear energy》 |2020年第12期|107755.1-107755.17|共17页
  • 作者单位

    Tsinghua Univ Dept Engn Phys Beijing 100084 Peoples R China|Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Tsinghua Univ Dept Engn Phys Beijing 100084 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Tsinghua Univ Dept Engn Phys Beijing 100084 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

    Nucl Power Inst China Sci & Technol Reactor Syst Design Technol Lab Chengdu 610213 Peoples R China;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Heat pipe cooled reactor; Heat pipe failure accidents; Heat pipe model; Thermal/mechanical characteristics;

    机译:热管冷却反应器;热管故障事故;热管模型;热/机械特性;

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