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.
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e-mail: li-yinsheng@jnes.go.jp
e-mail: hasegawa-kunio@jnes.go.jp
e-mail: onizawa.kunio@jaea.go.jp
e-mail: ncofie@structint.com
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December 2010
Research Papers
Prediction of Collapse Stress for Pipes With Arbitrary Multiple Circumferential Surface Flaws
Yinsheng Li,
Yinsheng Li
Seismic Safety Division,
e-mail: li-yinsheng@jnes.go.jp
Japan Nuclear Energy Safety Organization
, Toranomon 4-3-20, Minato-ku, Tokyo 105-0001, Japan
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Kunio Hasegawa,
Kunio Hasegawa
Nuclear Energy System Safety Division,
e-mail: hasegawa-kunio@jnes.go.jp
Japan Nuclear Energy Safety Organization
, Toranomon 3-7-11, Minato-ku, Tokyo 105-0001, Japan
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Kunio Onizawa,
Kunio Onizawa
Nuclear Safety Research Center,
e-mail: onizawa.kunio@jaea.go.jp
Japan Atomic Energy Agency
, Shirakata-Shirane 2-4, Tokai, Ibaraki, 319-1195, Japan
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Nathaniel G. Cofie
e-mail: ncofie@structint.com
Nathaniel G. Cofie
Structural Integrity Associates
, 5215 Hellyer Avenue, Suite 210, San Jose, CA 95138
Search for other works by this author on:
Yinsheng Li
Seismic Safety Division,
Japan Nuclear Energy Safety Organization
, Toranomon 4-3-20, Minato-ku, Tokyo 105-0001, Japane-mail: li-yinsheng@jnes.go.jp
Kunio Hasegawa
Nuclear Energy System Safety Division,
Japan Nuclear Energy Safety Organization
, Toranomon 3-7-11, Minato-ku, Tokyo 105-0001, Japane-mail: hasegawa-kunio@jnes.go.jp
Kunio Onizawa
Nuclear Safety Research Center,
Japan Atomic Energy Agency
, Shirakata-Shirane 2-4, Tokai, Ibaraki, 319-1195, Japane-mail: onizawa.kunio@jaea.go.jp
Nathaniel G. Cofie
Structural Integrity Associates
, 5215 Hellyer Avenue, Suite 210, San Jose, CA 95138e-mail: ncofie@structint.com
J. Pressure Vessel Technol. Dec 2010, 132(6): 061204 (7 pages)
Published Online: October 14, 2010
Article history
Received:
November 9, 2009
Revised:
April 20, 2010
Online:
October 14, 2010
Published:
October 14, 2010
Citation
Li, Y., Hasegawa, K., Onizawa, K., and Cofie, N. G. (October 14, 2010). "Prediction of Collapse Stress for Pipes With Arbitrary Multiple Circumferential Surface Flaws." ASME. J. Pressure Vessel Technol. December 2010; 132(6): 061204. https://doi.org/10.1115/1.4001732
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