自下而上加热的浅水池中的自然对流及其对侧壁热聚焦效应的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
N. Seiler , M. Johnson , L. Vyskocil , Y. Vorobyov , W. Villanueva , M. Abu Bakar , O. Zhabin , M. Kratochvil , B. Bian , A. Drouillet
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引用次数: 0

摘要

压水堆(PWR)的舱内滞留(IVR)战略非常关注自下而上加热的浅层液态金属池内的对流,因为横向热通量集中在反应堆壁会对反应堆容器的热机械完整性造成威胁。在国际原子能机构(IAEA)的 "冕熔体滞留协调研究项目 "下,多个国际研究机构进行了 CFD 模拟,以预测低普朗特数(Pr=0.02)和高外部瑞利数(Ra∼1012)的轻金属原型层从自由表面和反应堆侧壁散热的热-水行为。包括 LES-WALE、LES-Smagorinsky 和光谱-DNS 在内的各种计算方法在两次水中 BALI-Metal 实验(Pr=6.9)的条件下进行了验证,结果表明在垂直和横向边界热通量的预测重新分配方面存在良好的一致性。对轻金属层原型的模拟表明,自由表面的热辐射导致了 30%-34% 的散热。侧壁的平均热损失相当于外加热通量 3.3-3.7 倍的聚焦效应。靠近自由表面的侧向热通量峰值相当于局部聚焦效应,是自下而上外加热通量的 6 倍。流体动力学主要由反应器壁面的热损失驱动,其特点是侧壁附近的向下加速和与下边界平行的冷射流喷射,形成一个与反应器半径大小相当的大对流单元。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Natural convection in a shallow pool heated from below and implications for the thermal focusing effect at the lateral wall
Convection within shallow pools of liquid metals heated from below is of significant interest for the In-Vessel Retention (IVR) strategy for Pressurised Water Reactors (PWR) as focusing of the lateral heat flux at the reactor wall presents a risk to the thermomechanical integrity of the reactor vessel. Under an IAEA Coordinated Research Project on corium melt retention, various international research institutions have performed CFD simulations to predict the thermal–hydraulic behaviour of a prototypic light metal layer of low Prandtl number (Pr=0.02) and high external Rayleigh number (RaΦ1012) dissipating heat from the free surface and at the lateral reactor wall. Various computational approaches including LES-WALE, LES-Smagorinsky and spectral-DNS were validated under the conditions of two BALI-Metal experiments in water (Pr=6.9), revealing promising agreement in the predicted repartition of the heat flux at the vertical and lateral boundaries. Simulations in a prototypic light metal layer indicated 30–34 % of heat dissipation due to thermal radiation at the free surface. Average thermal losses at the lateral wall corresponded to a focusing effect of 3.3–3.7 times the imposed heat flux. A spike in lateral heat flux close to the free surface equated to a local focusing effect 6-times the imposed heat flux from below. The fluid dynamics, driven largely by thermal losses at the reactor wall, were characterised by downwards acceleration adjacent to the lateral wall and ejection of a cold jet parallel to the lower boundary, forming a large convection cell comparable in size to the radius of the reactor.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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