Probabilistic burst pressure estimation for steam generator tubes with fretting wear

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 Epub Date: 2024-12-14 DOI:10.1016/j.nucengdes.2024.113789
Daeyeop Kwon , Heejae Shin , Young-Jin Oh , Kuk-Hee Lee , Chi Bum Bahn
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Abstract

Considering steam generator (SG) tubes form the boundaries between the primary and secondary sides of nuclear power plants, maintaining their structural integrity, even in the presence of defects in tubes, is crucial. In this study, six burst pressure models were compared using available burst pressure test data for SG tubes with wear defects. The model that accounted for both the maximum and minimum depths of wear defects exhibited the best performance in predicting the burst pressure of flat and tapered wear defects. With the most suitable burst pressure model selected, probabilistic methods were applied to evaluate the structural integrity of SG tubes with wear defects. The proposed defect repair criteria, which consider inspection intervals of 1.5 or 3.0 effective full power years and a 5% burst probability, resulted in a less conservative evaluation compared to the existing repair criteria (40% through-wall).
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微动磨损蒸汽发生器管的概率爆破压力估计
考虑到蒸汽发生器(SG)管是核电站一次侧和二次侧的边界,即使在管中存在缺陷的情况下,保持其结构完整性至关重要。在本研究中,利用现有的SG管磨损缺陷的破裂压力试验数据,对六种破裂压力模型进行了比较。同时考虑最大和最小磨损缺陷深度的模型在预测扁平和锥形磨损缺陷的破裂压力方面表现出最好的性能。在选取最合适的爆破压力模型的基础上,采用概率方法对具有磨损缺陷的SG管进行结构完整性评估。所提出的缺陷修复标准,考虑到检查间隔为1.5或3.0有效全功率年和5%的爆裂概率,与现有的修复标准(40%穿壁)相比,产生了更保守的评估。
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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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