An Analytical Evaluation of the Full Structural Weld Overlay as a Stress Improving Mitigation Strategy to Prevent Primary Water Stress Corrosion Cracking in Pressurized Water Reactor Piping

Author:

Fredette L. F.1,Scott Paul M.1,Brust F. W.2,Csontos A.3

Affiliation:

1. Battelle Memorial Institute, Columbus, OH

2. Engineering Mechanics Corporation of Columbus, Columbus, OH

3. U. S. Nuclear Regulatory Commission, Washington, DC

Abstract

Full Structural Weld Overlay (FSWOL) has been used successfully to mitigate intergranular stress corrosion cracking in boiling water reactor (BWR) welded stainless steel piping for many years. The FSWOL technique adds structural reinforcement, can add crack resistant material, and can create compressive residual stresses at the inside surface of the welded joint which reduces the possibility of further stress corrosion cracking. Recently, the FSWOL has been applied as a preemptive measure to prevent primary water stress corrosion cracking (PWSCC) in pressurized water reactors (PWR) on susceptible welded pipes with dissimilar metal welds common to PWR primary cooling piping. This study uses finite element models to evaluate the likely residual and operating stress profiles remaining after FSWOL for typical dissimilar metal weld configurations, some of which are approved for leak-before-break (LBB) applications in pressurized water reactors. Circumferential cracks were modeled in the dissimilar metal weld area and forced to grow in order to evaluate their crack opening displacements and stress intensity factors vs. depth before and after weld overlay and before and after application of operating pressure and temperature.

Publisher

ASMEDC

Cited by 5 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. Experimental investigation on residual stress distribution in an austenitic stainless steel weld overlay pipe after local ultrasonic impact treatment;Welding in the World;2022-12-20

2. Improvement of Probabilistic Fracture Mechanics Analysis Code PASCAL-SP With Regardto PWSCC;Journal of Nuclear Engineering and Radiation Science;2019-05-03

3. Development and testing of a high-chromium, Ni-based filler metal resistant to ductility dip cracking and solidification cracking;Welding in the World;2017-01-12

4. NRC/EPRI Welding Residual Stress Validation Program - Phase III;15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors;2012-06-26

5. NRC/EPRI Welding Residual Stress Validation Program — Phase III;Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors;2011

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