Performance of a hydraulic buffer for PWR fuel assemblies: Mathematical modeling, numerical solutions, and experimental comparison

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-10-04 DOI:10.1016/j.nucengdes.2024.113619
Heng Huang, Peng Li, Chenguang Fan
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Abstract

In a Pressurized Water Reactor (PWR), the hydraulic buffer serves as an essential component, significantly mitigating the impact force between the control rod drive mechanism and the fuel assembly in scenarios of emergency shutdown. This paper provides a complete analysis of the dynamical performance of a new type of hydraulic buffer, including its mathematical modeling, numerical solution scheme, and experimental comparison. During the fluid modeling, five typical cases are first classified in terms of both flow directions and coefficients based on the relative positions of the sleeve and the piston. A new flow iterative calculation format encompassing flow directions that can efficiently solve the flow coefficients is proposed during the fluid modeling. A one-way coupling scheme is used for the fluid–structure dynamical solutions. An experimental comparative study is conducted using the standard and reference (SR) case, and the present method shows good agreement with the experiment. In the present analysis: (1) The dynamic characteristics of the buffer are fully demonstrated using time history curves and phase diagrams, the physical parameters of fluid and structural motions, mainly including fluid pressure inside the chamber, dynamic relative displacement and velocity of the piston and sleeve, the rebound disparagement, and system kinetic energy; (2) Typical features of double peaks of the impact force, related to the collision between the piston, the impacted object, and the sleeve, have been captured and well simulated; (3) The variation of the two peaks of the impact forces with parameters and the transformation laws of the maximum impact force between these two peaks have been fully revealed.
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压水堆燃料组件液压缓冲器的性能:数学建模、数值求解和实验对比
在压水堆(PWR)中,液压缓冲器是一个重要的部件,它能在紧急停堆的情况下大大减轻控制棒驱动机构和燃料组件之间的冲击力。本文对新型液压缓冲器的动态性能进行了全面分析,包括其数学建模、数值求解方案和实验对比。在流体建模过程中,首先根据套筒和活塞的相对位置,从流动方向和系数两个方面对五种典型情况进行了分类。在流体建模过程中,提出了一种新的包含流动方向的流动迭代计算格式,可以有效地求解流动系数。流体-结构动力学求解采用单向耦合方案。使用标准和参考(SR)情况进行了实验对比研究,结果表明本方法与实验具有良好的一致性。在本分析中(1) 利用时间历程曲线和相图、流体和结构运动的物理参数,主要包括腔内流体压力、活塞和套筒的动态相对位移和速度、回弹不同步和系统动能,充分展示了缓冲器的动态特性;(2) 捕获并很好地模拟了与活塞、被撞物体和套筒之间碰撞有关的冲击力双峰的典型特征; (3) 充分揭示了冲击力双峰随参数的变化以及双峰之间最大冲击力的变换规律。
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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