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Challenges in coupled thermal-hydraulics and neutronics simulations for LWR safety analysis

机译：用于轻水堆安全分析的热工液压和中子学耦合模拟面临的挑战

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摘要

The simulation of nuclear power plant accident conditions requires three-dimensional (3D) modeling of the reactor core to ensure a realistic description of physical phenomena. The operational flexibility of Light Water Reactor (LWR) plants can be improved by utilizing accurate 3D coupled neutronics/thermal-hydraulics calculations for safety margins evaluations. There are certain requirements to the coupling of thermal-hydraulic system codes and neutron-kinetics codes that ought to be considered. The objective of these requirements is to provide accurate solutions in a reasonable amount of CPU time in coupled simulations of detailed operational transient and accident scenarios. These requirements are met by the development and implementation of six basic components of the coupling methodologies: ways of coupling (internal or external coupling); coupling approach (integration algorithm or parallel processing); spatial mesh overlays; coupled time-step algorithms; coupling numerics (explicit, semi-implicit and implicit schemes); and coupled convergence schemes. These principles of the coupled simulations are discussed In details along with the scientific issues associated with the development of appropriate neutron cross-section libraries for coupled code transient modeling. The current trends in LWR nuclear power generation and regulation as well as the design of next generation LWR reactor concepts along with the continuing computer technology progress stimulate further development of these coupled code systems. These efforts have been focused towards extending the analysis capabilities as well as refining the scale and level of detail of the coupling. This article analyses the coupled phenomena and modeling challenges on both global (assembly-wise) and local (pin-wise) levels. The issues related to the consistent qualification of coupled code systems as well as their application to different types of LWR transients are presented. Finally, the advances in numerical and computation techniques for coupled code simulations are summarized with outlining remaining challenges.
机译：核电厂事故工况的模拟需要对反应堆堆芯进行三维（3D）建模，以确保对物理现象的真实描述。轻水反应堆（LWR）装置的操作灵活性可以通过利用精确的3D耦合中子/热工液压计算进行安全余量评估来提高。对热工液压系统代码和中子动力学代码的耦合有一定的要求。这些要求的目的是在详细运行瞬态和事故场景的耦合模拟中，在合理的CPU时间量内提供准确的解决方案。通过开发和实施耦合方法的六个基本组件可以满足这些要求：耦合方式（内部或外部耦合）；耦合方法（集成算法或并行处理）；空间网格覆盖；耦合时间步算法；耦合数值（显式，半隐式和隐式方案）；和耦合收敛方案。详细讨论了耦合模拟的这些原理，以及与用于耦合代码瞬态建模的适当中子截面库的开发相关的科学问题。轻水堆核发电和调节的当前趋势以及下一代轻水堆反应堆概念的设计以及持续的计算机技术进步，刺激了这些耦合代码系统的进一步发展。这些努力集中于扩展分析功能以及完善耦合细节的规模和水平。本文在全局（组装方式）和局部（引脚方式）级别分析耦合现象和建模挑战。提出了与耦合代码系统的一致性鉴定及其在不同类型的LWR瞬态中的应用有关的问题。最后，总结了耦合代码仿真的数值和计算技术的进步，并概述了剩余的挑战。

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  • 来源
    《Annals of nuclear energy》 |2007年第6期|p.501-513|共13页
  • 作者

    Kostadin Ivanov; Maria Avramova;

  • 作者单位

    Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, 230 Reber Building, University Park, State College, PA 16802, United States;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
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