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Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor

机译:自然循环一体化自压水反应堆稳定性分析及参数研究

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摘要

The stability analysis of a natural circulation integrated self-pressurized water reactor is investigated by the Lyapunov approach. The analysis of the pressurized water reactors (PWRs), particularly the integrated self-pressurized water reactors, is essential in keeping the neutronic and thermal-hydraulic parameters of the system stable. An appropriate nonlinear dynamic model is introduced based on conservation of mass, momentum and energy which is then linearized, in a state-space model. The Lyapunov approach and Routh-Hurwitz criterion are applied to assess the stability of this linearized system over its entire power range. The analysis is done for the primary coolant circuit in the RPV by assuming the steam dome pressure as the fixed parameter. It is found that the system remains stable over its entire power range. The influence of different geometrical features is studied at nominal conditions. It has been found that by reducing the chimney height results in a decrease in the coolant flow rate and a downward motion of the onset of flashing while the average core coolant temperature rises. For lower values of friction losses coefficient, the coolant flow rate increases, and the onset of flashing moves upward and the average core coolant temperature decreases. A change in independent parameters, which are effective in generating the natural circulation of the coolant, can influence the inherent safety of the system: An increase in reactor power and chimney height and a decrease in friction losses coefficient improve the system inherent safety. Two input functions as extra reactivity for increasing and decreasing the power from the nominal state are implemented into the dynamic model and the model response is therefore assessed by considering the lack of two phase flow entry to the core restriction. The boundary of the system stability lies in the range 32-107 MWt and using the system outside this range the system pressure needs to be controlled through spray and heater systems. The obtained results are based on the initial information, data and primary design of these types of reactors. Determining a more accurate boundary requires more detailed design and assessment together with experimental test facilities with respect to other restricting parameters of the system. The results presented in this paper can be implemented in further research on this type of reactors, particularly for nonlinear stability analysis and finding nonlinear Lyapunov function. (C) 2019 Elsevier Ltd. All rights reserved.
机译:利用Lyapunov方法研究了自然循环集成自压水反应堆的稳定性分析。对压水堆(PWR),特别是集成的自压水堆的分析,对于保持系统的中子和热工水力参数稳定至关重要。在质量,动量和能量守恒的基础上,引入适当的非线性动力学模型,然后在状态空间模型中将其线性化。应用Lyapunov方法和Routh-Hurwitz准则来评估该线性化系统在整个功率范围内的稳定性。通过将蒸汽气室压力作为固定参数,对RPV中的主冷却剂回路进行分析。发现系统在整个功率范围内保持稳定。在标称条件下研究了不同几何特征的影响。已经发现,通过减小烟囱高度,导致冷却剂流速降低,并且在平均堆芯冷却剂温度升高的同时,闪蒸开始时向下运动。对于较低的摩擦损耗系数值,冷却液流速增加,并且闪蒸开始向上移动,并且平均堆芯冷却液温度降低。有效生成冷却剂自然循环的独立参数的更改会影响系统的固有安全性:反应堆功率和烟囱高度的增加以及摩擦损耗系数的降低会改善系统的固有安全性。在动态模型中实现了两个输入功能,作为用于增加和减少标称状态功率的额外反应性,因此,通过考虑缺少进入核心限制的两相流来评估模型响应。系统稳定性的边界在32-107 MWt范围内,使用超出此范围的系统,需要通过喷雾和加热器系统控制系统压力。获得的结果基于这些类型反应堆的初步信息,数据和初步设计。要确定更准确的边界,就系统的其他限制参数而言,需要进行更详细的设计和评估以及实验测试设施。本文提出的结果可用于对该类型反应堆的进一步研究中,尤其是用于非线性稳定性分析和发现非线性Lyapunov函数时。 (C)2019 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2020年第5期|107279.1-107279.15|共15页
  • 作者

  • 作者单位

    Univ Isfahan Fac Adv Sci & Technol Dept Nucl Engn Hezarjarib Ave Esfahan 8174673441 Iran;

    Univ Isfahan Fac Engn & Technol Dept Biomed Engn Hezarjarib Ave Esfahan 8174673441 Iran;

    NSTRI Reactor & Nucl Safety Sch End North Karegar St Tehran 1439951113 Iran;

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

    SMR; iPWR; Dynamic model; Stability analysis; State-space model; Routh-Hurwitz criterion; Lyapunov approach;

    机译:SMR;iPWR;动态模型稳定性分析;状态空间模型;Routh-Hurwitz准则;李雅普诺夫方法;

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