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The Development of a Nodal Method for the Analysis of PWR Cores with Advanced Fuels

机译:用高级燃料分析pWR核心的节点法的研制

摘要

This thesis outlines the development of a nodal method with the purpose of addressing difficultiesudencountered in the modelling of advanced fuels. The standard calculational route used whenudmodelling a Uranium (U) fuelled Pressurised Water Reactor (PWR) is not accurate enough toudanalyse a PWR containing U and Plutonium (Pu). This is because the assumptions madeudwhen developing the standard route are not necessarily representative of situations involvingudadvanced fuels.udTo address some of these poor assumptions a nodal method has been developed which canudsolve the SPN equations in multiple energy groups. The SPN equations are an asymptoticudapproximation of the full neutron transport equation, and as such will include more physicaludeffects than the neutron diffusion equation. The theory behind the development of this nodaludmethod is outlined in this thesis along with an extensive set of benchmark tests for verificationudof the method. It is found that through a similarity transformation of the determining equations,udexisting nodal diffusion solvers can obtain solutions to the SPN equations without anyudapproximations.udPreviously EDF Energy have developed an embedded methodology to address the shortcomingsudof the standard calculational route. This procedure solves the diffusion equation in greater detailudon local sub-meshes in order to correct the standard 2 group nuclear data, and reduces the pinudpower errors by ≈ 50% by capturing spectral effects on the interface between two significantlyuddifferent fuel types. In this thesis the incorporation of the SPN nodal method into the embeddedudmethodology is described.udA small light water reactor benchmark is solved to test the accuracy of the embedded methodologyudcombined with the SPN nodal method. It is concluded that similar accuracy to diffusionudis attained with the SPN equations. This is because the homogenisation procedure producesudan error larger than the improvements due to the use of the SPN equations. To address theudlimitations discovered in this thesis future work is proposed based on the author’s experienceudof research in the area.
机译:本文概述了节点方法的发展,其目的是解决高级燃料建模中遇到的困难。对铀(U)燃料加压水反应堆(PWR)进行建模时所使用的标准计算路线不够准确,无法对包含U和P(Pu)的PWR进行分析。这是因为在开发标准路线时做出的假设不一定代表涉及高级燃料的情况。 ud为了解决这些不良假设中的某些,已经开发了一种节点方法,该方法可以分解多个能量组中的SPN方程。 SPN方程是整个中子输运方程的渐近 ud逼近,因此它将比中子扩散方程包含更多的物理缺陷。本文概述了这种节点 udmethod的发展背后的理论,以及用于验证该方法的大量基准测试。通过对确定方程的相似性转换,发现 udexisting的节点扩散求解器可以得到SPN方程的解而没有任何 ud逼近。 ud以前,EDF Energy已经开发出一种嵌入式方法来解决标准计算路线的缺点。该程序更详细地解决了扩散方程乌冬面局部子网格,以校正标准的2组核数据,并通过捕获两种明显不同的燃料之间的界面上的光谱效应,将销 udpower误差减少了约50%。类型。本文介绍了将SPN节点方法结合到嵌入式 udmethodology中的方法。 ud解决了小型轻水反应堆基准以测试嵌入式方法与SPN节点方法相结合的准确性。结论是,使用SPN方程可以达到与扩散 udis相似的精度。这是因为均质化程序产生的 udan误差大于由于使用SPN方程而导致的改进。为了解决本文中发现的局限性,基于作者在该领域的研究经验,提出了今后的工作。

著录项

  • 作者

    Hall Sheldon;

  • 作者单位
  • 年度 2013
  • 总页数
  • 原文格式 PDF
  • 正文语种 eng
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