The Effect of Prior Cold Work on Tensile Residual Stress Development in Nuclear Weldments

Author:

Hornbach Douglas J.1,Preve´y Paul S.1

Affiliation:

1. Lambda Research, Cincinnati, OH 45227

Abstract

Austenitic alloy weldments in nuclear reactor systems are susceptible to stress corrosion cracking (SCC) failures. SCC has been observed for decades and continues to be a primary maintenance concern for both pressurized water and boiling water reactors. SCC can occur if the sum of residual stress and applied stress exceeds a critical threshold tensile stress. Residual stresses developed by prior machining and welding can accelerate or retard SCC depending on their sign and magnitude. The residual stress, cold work and yield strength distributions on the inside diameter of an Alloy 600 tube J-welded into a pressure vessel were determined by a combination of X-ray diffraction (XRD) and mechanical techniques. A new method was used to relate the XRD line broadening to the percent cold work or true plastic strain in the Alloy 600 tube. The accumulated cold work in the layers deformed by prior machining, in combination with the true stress-strain relationship for Alloy 600, was used to determine the increase in yield strength as a result of deformation due to machining and weld shrinkage. The yield strength of the deformed layer was found to be well in excess of the bulk yield for the alloy, and is therefore capable of supporting residual stresses correspondingly higher. Tension as high as +700 MPa, exceeding the SCC threshold stress, was observed in both the hoop and axial directions on the inside diameter of the Alloy 600 tubing adjacent to the weld heat affected zone (HAZ). The cold worked high tensile zones correlated with the locations of field SCC failures. The tensile residual stresses are shown to result from a combination of the high cold working from initial machining followed by weld shrinkage. The development of surface tension during weld shrinkage has been modeled using finite element methods, and the benefits of minimizing or removing the cold worked layer prior to welding are demonstrated. Further laboratory studies showing the influence of prior cold working on the formation of residual stresses following bulk plastic deformation are presented.

Publisher

ASME International

Subject

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

Reference25 articles.

1. Hall, J. F., and Scott, D. B., 1989, “Destructive Examination of Pressurizer Heater Sleeves from Calvert Cliffs Unit 2,” Report CE-NPSD-577.

2. Gorman, J. A., 1986, “Status and Suggested Course of Action for Nondenting-Related Primary-Side IGSCD of Westinghouse-Type Steam Generators,” EPRI, Report MP-4594-LD.

3. Hall, J. F., Molkenthin, J. P., and Preve´y, P. S., 1993, “XRD Residual Stress Measurements on Alloy 600 Pressurizer Heater Sleeve Mockups,” Proc., Sixth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, San Diego, CA: TMS, ANS, NACE, pp. 855–861.

4. Hall, J. F., Molkenthin, J. P., Preve´y, P. S., and Pathania, R. S., 1994, “Measurement of Residual Stresses in Alloy 600 Pressurizer Penetrations,” Conf. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, Paris: Societe Francaise d’Energie Nucleare, September 12–16.

5. US Patent 5,826,453, Oct. 1998.

Cited by 16 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

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