Funke Dacosta-Salu , Michael E Fitzpatrick , Xiang Zhang , Michael Roy , James Jewkes
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引用次数: 0
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.
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.