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Nuclear-coupled thermal-hydraulic stability analysis of boiling water reactors.

机译:沸水反应堆的核耦合热工水力稳定性分析。

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摘要

We have studied the nuclear-coupled thermal-hydraulic stability of boiling water reactors (BWRs) using a model we developed from: the space-time modal neutron kinetics equations based on spatial ;We first determine the stability boundary (SB) in the most relevant parameter plane, the inlet-subcooling-number/external-pressure-drop plane, for a fixed control rod induced external reactivity equal to the 100% rod line value and then transform the SB to the practical power-flow map. Using this SB, we show that the normal operating point at 100% power is very stable, stability of points on the 100% rod line decreases as the flow rate is reduced, and that points are least stable in the low-flow/high-power region. We also determine the SB when the modal kinetics is replaced by simple point reactor kinetics and show that the first harmonic mode has no significant effect on the SB.;Later we carry out the relevant numerical simulations where we first show that the Hopf bifurcation, that occurs as a parameter is varied across the SB is subcritical, and that, in the important low-flow/high-power region, growing oscillations can result following small finite perturbations of stable steady-states on the 100% rod line. Hence, a point on the 100% rod line in the low-flow/high-power region, although stable, may nevertheless be a point at which a BWR should not be operated. Numerical simulations are then done to calculate the decay ratios (DRs) and frequencies of oscillations for various points on the 100% rod line. It is determined that the NRC requirement of DR ;Finally, the effect of a simple recirculation loop model that we develop is studied by carrying out additional stability analyses and additional numerical simulations. It is shown that the loop has a stabilizing effect on certain points on the 100% rod line for time delays equal to integer multiples of the natural period of oscillation, whereas it has a destabilizing effect for half-integer multiples. However, for more practical time delays, it is determined that the overall effect generally is destabilizing.
机译:我们使用以下模型开发了模型来研究沸水反应堆(BWR)的核耦合热工水力稳定性:基于空间的时空模态中子动力学方程;我们首先确定最相关的稳定性边界(SB)对于固定的控制杆引起的外部反应性(等于100%杆线值),将参数平面(入口-过冷数/外部压降平面)作为参数平面,然后将SB转换为实际功率流图。使用该SB,我们显示100%功率时的正常工作点非常稳定,100%杆线上的点的稳定性会随着流速的降低而降低,而在低流量/高流量时,这些点的稳定性最差电源区域。我们还确定了由单点反应器动力学代替模态动力学时的SB,并表明一次谐波模式对SB没有显着影响;稍后我们进行了相关的数值模拟,其中我们首先证明了Hopf分叉,当整个SB上的参数变化时,会发生亚临界状态,并且在重要的低流量/大功率区域中,在100%杆线上稳定稳态受到较小的有限扰动后,会导致振荡增大。因此,在低流量/大功率区域中100%杆线上的一点虽然稳定,但仍可能是不应操作BWR的点。然后进行数值模拟,以计算100%杆线上各个点的衰减率(DR)和振荡频率。确定了DR的NRC要求;最后,通过进行附加的稳定性分析和附加的数值模拟,研究了我们开发的简单再循环回路模型的效果。结果表明,对于100%的杆线上的某些点,对于具有等于自然振荡周期整数倍的时间延迟的环路,它具有稳定作用,而对于半整数倍数,则具有不稳定作用。但是,对于更实际的时间延迟,可以确定总体效果通常是不稳定的。

著录项

  • 作者

    Karve, Atul A.;

  • 作者单位

    University of Virginia.;

  • 授予单位 University of Virginia.;
  • 学科 Nuclear engineering.;Mechanical engineering.
  • 学位 Ph.D.
  • 年度 1998
  • 页码 256 p.
  • 总页数 256
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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