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Methodologies for boiling water reactors stability analysis based on the study of neutronic power signals.

机译:基于中子功率信号研究的沸水反应堆稳定性分析方法。

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摘要

The present PhD Thesis deals with the Boiling Water Reactors (BWR) stability characterization by means of neutronic power signals analysis. The main objective is to detect the stability-related neutron flux oscillations in order to be suppressed before exceeding specified acceptable fuel design limits. In this context, the present PhD Thesis makes contributions by means of tools and methodologies that allow to determine the stability regime in a robust way, using the lineal stability parameters, Decay Ratio (DR) and natural frequency.; Firstly, the identification of the natural frequency associated with the neutronic oscillation is revised using spectral analysis. Once the natural frequency is determined, the DR estimation is studied. In order to estimate the DR, autoregressive (AR) models and dynamics reconstruction techniques are revised, making contributions in order to improve the stability regime characterization. Also a previous treatment of the neutronic power signals based on the singular system analysis (SSA) is proposed to improve the signals characteristics and better determine the stability regime of the reactor. Furthermore, the linear approximation of the BWR behaviour is analysed by means the linear stability parameters variation during the measuring time of the neutronic power signals.; In order to validate the tools and methodologies presented and compare their performance, analytic signals and the neutronic power signals from the Forsmark 1&2 Stability Benchmark are used. The purpose of this international benchmark was the intercomparison of the different time series analysis methods that can be applied to study BWR stability regime using neutronic power signals.
机译:本博士论文通过中子功率信号分析研究沸水反应堆(BWR)的稳定性。主要目的是检测与稳定性相关的中子通量振荡,以便在超过指定的可接受的燃料设计限制之前将其抑制。在此背景下,本博士学位论文通过工具和方法论做出了贡献,这些工具和方法论允许使用线性稳定性参数,衰减比(DR)和固有频率以鲁棒的方式确定稳定性体系。首先,使用频谱分析修改了与中子振荡相关的固有频率的识别。一旦确定了固有频率,就可以研究DR估计。为了估计DR,对自回归(AR)模型和动力学重建技术进行了修改,从而做出了贡献,以改善稳定性状态的表征。还提出了基于奇异系统分析(SSA)的中子功率信号的先前处理,以改善信号特性并更好地确定反应堆的稳定性。此外,通过在中子功率信号的测量时间内线性稳定性参数的变化来分析BWR行为的线性近似。为了验证所介绍的工具和方法并比较其性能,使用了Forsmark 1&2稳定性基准的分析信号和中子功率信号。该国际基准的目的是比较不同的时间序列分析方法,这些方法可用于研究使用中子功率信号的BWR稳定状态。

著录项

  • 作者

    Navarro Esbri, Joaquin.;

  • 作者单位

    Universidad Politecnica de Valencia (Spain).;

  • 授予单位 Universidad Politecnica de Valencia (Spain).;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2001
  • 页码 283 p.
  • 总页数 283
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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