Prediction of Collapse Stress for Pipes With Arbitrary Multiple Circumferential Surface Flaws-Reference-Cited by-同舟云学术

Prediction of Collapse Stress for Pipes With Arbitrary Multiple Circumferential Surface Flaws

Published:2010-10-14 Issue:6 Volume:132 Page:
ISSN:0094-9930
Container-title:Journal of Pressure Vessel Technology
language:en
Short-container-title:

Author:

Li Yinsheng¹,Hasegawa Kunio²,Onizawa Kunio³,Cofie Nathaniel G.⁴

Affiliation:

1. Seismic Safety Division, Japan Nuclear Energy Safety Organization, Toranomon 4-3-20, Minato-ku, Tokyo 105-0001, Japan

2. Nuclear Energy System Safety Division, Japan Nuclear Energy Safety Organization, Toranomon 3-7-11, Minato-ku, Tokyo 105-0001, Japan

3. Nuclear Safety Research Center, Japan Atomic Energy Agency, Shirakata-Shirane 2-4, Tokai, Ibaraki, 319-1195, Japan

4. Structural Integrity Associates, 5215 Hellyer Avenue, Suite 210, San Jose, CA 95138

Abstract

When a flaw is detected in a stainless steel piping system of a nuclear power plant during in-service inspection, the limit load estimation method provided in codes such as ASME Section XI or JSME S NA-1-2008 can be applied to evaluate the integrity of the pipe. However, in the current editions of these codes, a limit load estimation method is only provided for pipes containing a single flaw. Independent multiple flaws, such as stress corrosion cracks, have actually been detected in the same plane of stainless steel piping systems. In this paper, a failure estimation method by formula is proposed for any number and arbitrary distribution of multiple independent circumferential flaws in the same plane of a pipe. Using the proposed method, numerical solutions are compared with experimental results to validate the model, and several numerical examples are provided to show its effectiveness.

Publisher

ASME International

Subject

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

Link

http://asmedigitalcollection.asme.org/pressurevesseltech/article-pdf/doi/10.1115/1.4001732/5742293/061204_1.pdf

Reference10 articles.

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2. The Japan Society of Mechanical Engineers, 2008, “Rules on Fitness-for-Service for Nuclear Power Plants,” Paper No. JSME S NA1-2008.

3. 2004, Integrity Evaluation About the Core Shroud and the Piping in Primary Loop Recirculation System, Nuclear and Industry Safety Agency.

4. Plastic Collapse Analysis of Pipes With Arbitrarily Shaped Circumferential Cracks;Cofie

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