A PSO-based burst pressure equation of super duplex stainless steel pipelines at high temperatures

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-08-29 DOI:10.1016/j.nucengdes.2025.114427

Shuqian Shen , Yan Li , Bao Zhang , Yi Shuai , Liyang Wu , Xiaofu Chen , Zhanfeng Chen

{"title":"A PSO-based burst pressure equation of super duplex stainless steel pipelines at high temperatures","authors":"Shuqian Shen , Yan Li , Bao Zhang , Yi Shuai , Liyang Wu , Xiaofu Chen , Zhanfeng Chen","doi":"10.1016/j.nucengdes.2025.114427","DOIUrl":null,"url":null,"abstract":"<div><div>Pipelines in nuclear, oil and gas, and chemical industries often operate under prolonged high-temperature and high-pressure conditions, which significantly degrade material strength and complicate burst pressure prediction. This study proposes a novel semi-empirical model to estimate the burst pressure of super duplex stainless steel (SDSS) pipelines under high temperature. Temperature-dependent mechanical properties were quantified through experiments and fitted into empirical equations. A new burst pressure equation was then developed, incorporating these thermal effects. A material-specific correction factor for SDSS was calibrated using Particle Swarm Optimization (PSO) based on finite element simulations. The proposed model was validated against both numerical and experimental results, showing a relative error below 4.2%. This method provides a reliable and practical tool for safety assessment of pipelines exposed to high-temperature service environments.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"444 ","pages":"Article 114427"},"PeriodicalIF":2.1000,"publicationDate":"2025-08-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325006041","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

Pipelines in nuclear, oil and gas, and chemical industries often operate under prolonged high-temperature and high-pressure conditions, which significantly degrade material strength and complicate burst pressure prediction. This study proposes a novel semi-empirical model to estimate the burst pressure of super duplex stainless steel (SDSS) pipelines under high temperature. Temperature-dependent mechanical properties were quantified through experiments and fitted into empirical equations. A new burst pressure equation was then developed, incorporating these thermal effects. A material-specific correction factor for SDSS was calibrated using Particle Swarm Optimization (PSO) based on finite element simulations. The proposed model was validated against both numerical and experimental results, showing a relative error below 4.2%. This method provides a reliable and practical tool for safety assessment of pipelines exposed to high-temperature service environments.

查看原文本刊更多论文

基于pso的高温下超级双相不锈钢管道破裂压力方程

核电、油气和化工行业的管道经常在长时间的高温高压条件下运行，这大大降低了材料的强度，并使破裂压力预测复杂化。本文提出了一种新的半经验模型来估计高温下超级双相不锈钢（SDSS）管道的破裂压力。通过实验对温度相关的力学性能进行量化，并拟合到经验方程中。随后，考虑到这些热效应，建立了一个新的爆破压力方程。采用基于有限元模拟的粒子群算法（PSO）对SDSS的材料校正系数进行了标定。通过数值和实验结果验证了该模型的相对误差小于4.2%。该方法为高温使用环境下管道的安全评估提供了可靠实用的工具。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

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.