Prediction of Fully Plastic Collapse Stresses for Pipes With Two Circumferential Flaws

Author:

Hasegawa Kunio1,Saito Koichi2,Iwamatsu Fuminori3,Miyazaki Katsumasa3

Affiliation:

1. Japan Nuclear Energy Safety Organization (JNES), Toranomon 3-17-1, Minatoku, Tokyo 105-0001, Japan

2. Hitachi Works, Hitachi GE Nuclear Energy, Ltd., Saiwai-cho 3-1-1, Hitachi-shi 317-8511, Japan

3. Hitachi Research Laboratory, Hitachi, Ltd., Saiwai-cho 3-1-1, Hitachi-shi 317-8511, Japan

Abstract

Fully plastic collapse stress for a single circumferential flaw on a pipe is evaluated by the limit load criteria in accordance with the JSME Code S NA-1-2004 and the ASME Code Section XI. However, multiple flaws such as stress corrosion cracking are frequently detected in the same circumferential cross section in a pipe. If the distance between adjacent flaws is short, the two flaws are combined as a single flaw in compliance with combination rules. If the two flaws separated by a large distance, it is not required to combine two flaws. However, there is no evaluation method for two separated flaws in a pipe in the JSME and ASME Codes. Plastic collapse stresses for pipes with two symmetrical circumferential flaws based on net-stress approach had been proposed by one of the authors. Bending tests were performed on Type 304 stainless steel pipes with two symmetrical circumferential flaws. Consequently, it was shown that the proposed method can predict well the plastic collapse stresses for pipes with two flaws. In addition, it is also shown that this method is appropriate to use in fitness-for-service procedures, and higher plastic collapse stresses are expected, compared with current prediction methods for pipes with two flaws.

Publisher

ASME International

Subject

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

Reference8 articles.

1. Kanninen, M. F., Broek, D., Marschall, C. W., Rybicki, E. F., Sampath, S. G., Simonen, F. A., and Wilkowski, G. M., 1976, “Mechanical Fracture Predictions for Sensitized Stainless Steel Piping With Circumferential Cracks,” Paper No. EPRI NP-192.

2. Japanese Society of Mechanical Engineers, 2004, “Rules on Fitness-for-Service for Nuclear Power Plants,” Paper No. JSME S NA-1-2004.

3. 2004, ASME B&PV Code Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.

4. Nuclear and Industry Safety Agency, 2003, Interim Report.

5. Hasegawa, K., and Kobayashi, H., 2004, “Failure Stresses for Pipes With Multiple Circumferential Flaws,” ASME Paper No. PVP2004-2712.

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