Stress Intensity Factors for Reactor Vessel Nozzle Cracks

Author:

Smith C. W.1,Peters W. H.1,Jolles M. I.2

Affiliation:

1. Department of Engineering Science and Mechanics, Virginia Polytechnic Institute and State University, Blacksburg, Va.

2. Department of Aerospace and Mechanical Engineering, University of Notre Dame, Notre Dame, Ind.

Abstract

A method consisting of a marriage between frozen stress photoelasticity and a computerized least-squares data analysis for extracting stress intensity factor (SIF) distributions in three-dimensional cracked body problems is reviewed. Results from the application of the method to three programs dealing with nozzle corner cracks are discussed. The importance of using actual flaw shapes in analysis is stressed. It is concluded that the flaw growth in such problems is generally not self-similar due to the complexity and variety of boundary shapes. The experimental technique described appears to offer a viable independent estimate of SIF distributions for such problems.

Publisher

ASME International

Subject

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

Cited by 8 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. Fracture analysis for nozzle cracks in nuclear reactor pressure vessel using FCPAS;Nuclear Engineering and Technology;2024-06

2. Experiments in three-dimensional fracture problems;Experimental Mechanics;1993-09

3. Approximate stress-intensity factor solutions for nozzle corner cracks;International Journal of Pressure Vessels and Piping;1990-01

4. Methods of calculating stress intensity factors for nozzle corner cracks;International Journal of Pressure Vessels and Piping;1983-01

5. Opening and Mixed-Mode Fatigue Crack Growth of Surface Cracks in a Hollow Tube;Proceedings of an international conference on Analytical and Experimental Fracture Mechanics;1981

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