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On the characteristics of the flow and heat transfer in the core bypass region of a PWR

机译:关于压水堆堆芯旁路区域的流动和传热特性

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摘要

The development of analysis models for the Swiss reactors is a key objective of the STARS project at the Paul Scherrer Institut (PSI). Within this context there is a need for the development of computational fluid dynamics (CFD) models of the Swiss reactors in support of future high fidelity investigations of steady-state and transient scenarios. This article presents initial results for the CFD analysis of a Siemens KWU PWR with a focus on the flow behaviour and heat transfer in the gap between the core shroud and core barrel. Temperatures and densities in this region of the reactor are important, for example, for accurate estimations of fast neutron fluence and activation in the steel structures of the core shroud, core barrel and reactor pressure vessel. The flow behaviour in this region may also be relevant for better understanding of ex-core detector responses. The flow conditions in the core bypass region were found to be in the transition-to-turbulence regime, with vortex shedding taking place downstream of the core formers as a result of flow instabilities. The non-stationary nature of the flow presented a challenge in terms of obtaining a solution within a reasonable time period. Two approaches were proposed to address this challenge: time-averaging of the flow-field information before solving the conjugate heat transfer problem; time-averaging of surface heat fluxes in order to derive detailed surface heat transfer coefficients. Both approaches yielded similar results with similar computational effort. Several characteristics and features of the core bypass flow are discussed. Updated Monte Carlo simulation results show that the influence of the core bypass temperatures on the neutron fluence predictions is non-negligible. This highlights the importance of including accurate bypass temperatures in future Monte Carlo simulations focused on ex-core regions.
机译:Paul Scherrer研究所(PSI)的STARS项目的主要目标是开发瑞士反应堆的分析模型。在这种情况下,需要开发瑞士反应堆的计算流体动力学(CFD)模型,以支持将来对稳态和瞬态情况进行高保真度研究。本文介绍了西门子KWU PWR的CFD分析的初步结果,重点是堆芯导流罩和堆芯筒之间间隙中的流动行为和传热。例如,对于准确估算堆芯护罩,堆芯筒和反应堆压力容器的钢结构中的快速中子注量和活化,反应堆此区域的温度和密度很重要。该区域中的流动行为也可能与更好地理解核外探测器的响应有关。发现堆芯旁通区域的流动条件处于过渡湍流状态,由于流动的不稳定性,涡旋脱落发生在堆芯形成器的下游。流程的非平稳性质对在合理的时间内获得解决方案提出了挑战。提出了两种方法来应对这一挑战:在解决共轭传热问题之前对流场信息进行时间平均;为了得到详细的表面传热系数,对表面热通量进行时间平均。两种方法在相似的计算量下都产生相似的结果。讨论了核心旁路流的几个特征和特征。更新的蒙特卡洛模拟结果表明,堆芯旁路温度对中子注量预测的影响不可忽略。这突出了在未来针对前核心区域的蒙特卡洛模拟中包括准确的旁路温度的重要性。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2018年第4期|117-128|共12页
  • 作者单位

    Paul Scherrer Inst, Lab Reactor Phys & Syst Behav LRS, CH-5232 Villigen, Switzerland;

    Paul Scherrer Inst, Lab Reactor Phys & Syst Behav LRS, CH-5232 Villigen, Switzerland;

    Paul Scherrer Inst, Lab Reactor Phys & Syst Behav LRS, CH-5232 Villigen, Switzerland;

    Paul Scherrer Inst, Lab Reactor Phys & Syst Behav LRS, CH-5232 Villigen, Switzerland;

    Paul Scherrer Inst, Lab Reactor Phys & Syst Behav LRS, CH-5232 Villigen, Switzerland;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Computational fluid dynamics; Core bypass; Heat transfer; Pressurized water reactor;

    机译:计算流体力学;堆芯旁路;传热;压水堆;
  • 入库时间 2022-08-18 00:40:43

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