三瓣花瓣型燃料棒热-机耦合性能初步分析

IF 2.5 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-18 DOI:10.1016/j.nucengdes.2024.113792
Binxian He , Shusong Qin , Aobo Han , Wenchao Zhang , Lipeng Du , Xiangfei Meng , Jianchuang Sun , Weihua Cai
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引用次数: 0

摘要

基于有限元方法,建立了三叶瓣和四叶瓣花瓣形燃料棒辐照的热-力学耦合分析模型,研究了花瓣形燃料棒在正常工况和RIA工况下的热-力学特性。结果表明:三瓣PSFR的轴向温度中间大,两侧小,瓣瓣根部在周向温度最大;正常工作时,熔覆层应力随时间不断增大,且中心区应力最大。在第200天和第600天,当RIA突然发生时,包层分别在1.003 s和0.763 s超过屈服强度。三瓣PSFR中心的包层瓣根是塑性变形最大的位置。三瓣和四瓣PSFRs在温度、热流密度、应力等方面有异同,但可以相互替代。上述研究为三瓣PSFR的实际应用提供了指导。
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Preliminary thermo-mechanical coupling performance analysis of a three-lobe petal-shaped fuel rod
In this paper, an analytical model of thermal–mechanical coupling performance of three-lobe and four-lobe petal-shaped fuel rods (PSFRs) irradiation is established based on the finite element method, and the thermo-mechanical characteristics of PSFR during normal operation and RIA condition are investigated. The results show that the temperature of three-lobe PSFR is large in the middle and small on both sides in the axial direction, and the petal lobe root is the largest in the circumferential direction. During normal operation, the cladding stress increases continuously with time, and the stress in the center region is the largest. At the 200th day and the 600th day, when RIA occurs suddenly, the cladding will exceed the yield strength in 1.003 s and 0.763 s, respectively. The cladding lobe root at the center of three-lobe PSFR is the location of maximum plastic deformation. There are similarities and differences in temperature, heat flux, and stress between three-lobe and four-lobe PSFRs, but they can be substituted for each other. The above study provides guidance for practical application of three-lobe PSFR.
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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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