Structural Integrity Assessment of Steam Generator Tube by the Use of Heterogeneous Finite Element Method

Author:

Duan Xinjian1,Kozluk Michael J.1,Pagan Sandra2,Mills Brian3

Affiliation:

1. Reactor Engineering Department, Atomic Energy of Canada Limited, 2251 Speakman Drive, Mississauga, ON, L5K 1B2, Canada

2. Steam Generator Section, Ontario Power Generation, 889 Brock Road, Pickering, ON, L1W 3J2, Canada

3. Generation Life Cycle Management, Kinectrics Inc., 800 Kipling Avenue, Toronto, ON, M8Z 6C4, Canada

Abstract

Aging steam generator tubes have been experiencing a variety of degradations such as pitting, fretting wear, erosion-corrosion, thinning, cracking, and denting. To assist with steam generator life cycle management, some defect-specific flaw models have been developed from burst pressure testing results. In this work, an alternative approach; heterogeneous finite element model (HFEM), is explored. The HFEM is first validated by comparing the predicted failure modes and failure pressure with experimental measurements of several tubes. Several issues related to the finite element analyses such as temporal convergence, mesh size effect, and the determination of critical failure parameters are detailed. The HFEM is then applied to predict the failure pressure for use in a fitness-for-service condition monitoring assessment of one removed steam generator tube. HFEM not only calculates the correct failure pressure for a variety of defects, but also predicts the correct change of failure mode. The Taguchi experimental design method is also applied to prioritize the flaw dimensions that affect the integrity of degraded steam generator tubes such as the defect length, depth, and width. It has been shown that the defect depth is the dominant parameter controlling the failure pressure. The failure pressure varies almost linearly with defect depth when the defect length is greater than two times the tube diameter. An axial slot specific flaw model is finally developed.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference15 articles.

1. CANDU Steam Generator Life Management;Tapping;Nucl. Eng. Des.

2. Pagan, S., and Scarth, D., 2005, “Fitness-for-Service Guidelines for Steam Generator Tubes, Section 1: Evaluation Procedures and Acceptance Criteria,” Ontario Power Generation, Report No. N-REP-33110–10000-R001.

3. Canadian Standards Association, 1994, “Periodic Inspection of CANDU Nuclear Power Plant Components,” Report No. N285.4–94.

4. Fitness-for-Service Assessment for Steam Generator Tube Fretting at Darlington Nuclear Generating Station;Pagan

5. Plastic Collapse Analysis of Pipe Bends Under Out-of-Plane Moment and Internal Pressure Loading;Li

Cited by 1 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. Regulatory requirements and considerations for nuclear steam generators;Steam Generators for Nuclear Power Plants;2017

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3