Flow distribution in the primary circuit of a fast reactor: Impact with reduced number of subassemblies in the core

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2025-01-06 DOI:10.1016/j.nucengdes.2024.113813
G. Vikram , Amit Kumar Chauhan , M. Rajendrakumar , K. Natesan
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Abstract

The primary circuit of a typical pool-type sodium-cooled fast reactor (SFR) is a complex flow network with multiple flow paths. The resistances of these flow paths vary significantly from very low to very high values. Estimation of flow fractions in these paths is essential for the design and analysis of various components in the primary circuit under various operating conditions. In the present work, the primary circuit of a typical medium-sized pool-type SFR has been modeled using the Flownex code, a commercial system dynamics code. The steady-state flow distribution in the primary circuit has been first studied and an overall flow balance has been established. Out of the total flow supplied by the primary pumps, ∼91 % flows through the core, and ∼ 93 % flows through the Intermediate Heat Exchanger (IHX). Notably, in the storage locations of the core, there is no leakage from the Grid Plate (GP, the structure on which the core subassemblies (SAs) are supported) to the bottom Core Support Structure (CSS) plenum. Instead, flow is in the reverse direction due to the high resistance offered by the sleeve holes in the storage locations.
Then, the effect of removing SAs from the fuel and storage locations of the core has been studied. The empty sleeves in the GP were modeled in 3D using Ansys® Fluent and have been coupled with the Flownex model of the primary circuit. Two different flow configurations were observed in the empty GP sleeves when the fuel SAs were removed and when the storage SAs were removed. When fuel SAs are removed, the sodium flows downwards in the empty sleeve bottom opening. However, when storage SAs are removed, the sodium flows upwards in the empty sleeve bottom opening. This happens because of the high hydraulic resistance offered by the storage SA sleeve holes. As a result, when fuel SAs are removed, the flow rates in the paths fed by the CSS plenum (main vessel cooling system path, shielding SA flow path, etc.) increase. When storage SAs are removed, the flows in these paths decrease. There is no significant change in the pump operating point when a single fuel or storage SA is removed from the core. However, when more fuel SAs are removed from the core, a change in the pump operating point is observed. For instance, the pump flow decreases by ∼ 4.1 % when seven fuel SAs are removed from the core.
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快堆一次回路的流量分布:减少堆芯组件数量的影响
池式钠冷快堆的一次回路是一个具有多流道的复杂流动网络。这些流道的阻力变化很大,从非常低的值到非常高的值。估计这些路径中的流量分数对于设计和分析不同工作条件下初级电路中的各种元件是必不可少的。在目前的工作中,使用Flownex代码(商业系统动力学代码)对典型中型池型SFR的初级电路进行了建模。首先研究了一次回路的稳态流量分布,建立了总体流量平衡。在主泵提供的总流量中,约91%流经堆芯,约93%流经中间热交换器(IHX)。值得注意的是,在堆芯的存储位置,没有从栅格板(GP,支撑堆芯组件(SAs)的结构)到底部堆芯支撑结构(CSS)静压室的泄漏。相反,由于存储位置的套筒孔提供的高阻力,流动方向相反。在此基础上,研究了从堆芯燃料和储存库中去除sa的影响。利用Ansys®Fluent对GP中的空套进行了三维建模,并与主回路的Flownex模型相结合。当燃料sa被移除和存储sa被移除时,在空GP套筒中观察到两种不同的流动结构。当燃料sa被移除时,钠在空的套筒底部开口向下流动。然而,当储存的sa被移除时,钠在空的套筒底部开口向上流动。这种情况的发生是由于储SA套筒孔提供的高液压阻力。因此,当燃料SA被移除时,由CSS静压室(主容器冷却系统路径,屏蔽SA流路等)馈送的路径中的流量增加。移除存储sa后,这些路径中的流减少。当从堆芯中取出单个燃料或存储SA时,泵的工作点没有明显变化。然而,当更多的燃料sa从堆芯中移除时,泵的工作点会发生变化。例如,如果从堆芯中取出7个燃料sa,泵流量将减少~ 4.1%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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