Numerical modelling of thermal fatigue at pipe mixing points in nuclear power plants

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Funke Dacosta-Salu , Michael E Fitzpatrick , Xiang Zhang , Michael Roy , James Jewkes
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Abstract

In nuclear power plants, thermal fatigue can occur at pipe mixing points where hot and cold water combine, leading to failure at these critical locations. This study investigates the effect of temperature fluctuations on fatigue failure at critical locations and welded joints, which has received limited attention in previous research. A numerical approach was used, starting with highly-resolved unsteady conjugate heat transfer simulations to assess heat flux at the pipe wall. This was followed by structural analysis using the finite element method, and finally, a fatigue assessment to predict failure locations and estimate component lifespan. Temperature differences of 80 °C and 160 °C were investigated at the different weld locations. Results showed that at a temperature difference of 160 °C between the main pipe and the branch pipe, a full penetration butt weld would fail after 1462 to 19,119 h. A shorter failure time was observed at the stress concentration area upstream of the T-junction under the same conditions. These findings were applied to the well-documented 1998 failure at the Civaux1 plant in France, to help understand the potential causes of that failure.
核电厂管道混合点热疲劳数值模拟
在核电站中,热疲劳可能发生在冷热水结合的管道混合点,导致这些关键位置的故障。本研究探讨了温度波动对关键部位和焊接接头疲劳失效的影响,这在以往的研究中受到有限的关注。采用数值方法,从高分辨率非定常共轭传热模拟出发,计算管壁处的热流密度。接下来是使用有限元方法进行结构分析,最后是疲劳评估,以预测失效位置和估计部件寿命。在不同的焊接位置研究了80°C和160°C的温差。结果表明:当主支管温差为160℃时,全熔透对接焊缝在1462 ~ 19119 h后失效,而在相同条件下,t型接头上游应力集中区域的对接焊缝失效时间较短。这些发现被应用到1998年法国Civaux1工厂的故障中,以帮助了解该故障的潜在原因。
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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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