Crack Opening Area of Pressurized Pipe for Leak-before-Break Evaluation

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概要

• 論文の詳細を見る

• The prediction method for analyzing the crack opening area of a pipe is essential for leak-before-break evaluation. Several theoretical approaches are proposed for predicting crack opening areas. One approach is the Tada and Paris formula, developed based on the linear elastic fracture mechanics. Another is the engineering approach developed by German and Kumar. Round-robin analyses for crack opening areas are performed using these two methods. The pipe analyzed is a 6-inch-diameter Type 304 stainless steel pipe with a circumferential through-wall crack. The applied load is bending moment. The crack opening areas calculated by Tada and Paris method coincided among the four participants. However, the areas using German and Kumar method were quite different. It is concluded that in the present situation, Tada and Paris method is suitable for a leak-before-break standard to predict the crack opening area. In addition, material properties used in the calculation of the standard are discussed compared with the results of the pipe bending experiment.

• 一般社団法人日本機械学会の論文
• 1991-07-15

著者

• Yamamoto Yoshio

  Nuclear Plant Design And Engineering Dept. Toshiba Corp.

• Okamoto Asao

  Engineering Administration And Development Dept. Ihi

• HASEGAWA Kunio

  Mechanical Engineering Research Laboratory, Hitachi Ltd.

• YOKOTA Hiroshi

  Reactor Component Engineering Dept., Mitsubishi Atomic Power Industries, Inc.

• SHIBATA Katsuyuki

  Dept. of Reactor Safety Research, Japan Atomic Energy Research Institute

• OSHIBE Toshihiro

  The Kansai Electric Power Co., Inc.

• MATSUMURA Kazuhiro

  The Tokyo Electric Power Co., Inc.

• Hasegawa Kunio

  Mechanical Engineering Research Laboratory Hitachi Ltd.

• Oshibe Toshihiro

  The Kansai Electric Power Co. Inc.

• Shibata Katsuyuki

  Department Of Reactor Safety Research Japan Atomic Energy Research Institute

• Matsumura Kazuhiro

  The Tokyo Electric Power Co. Inc.

• Yokota Hiroshi

  Reactor Component Engineering Dept. Mitsubishi Atomic Power Industries Inc.

関連論文

• Probabilistic Fracture Mechanics Analyses of Reactor Pressure Vessel under PTS Transients
• ICONE11-36081 PROBABILISTIC FRACTURE MECHANICS ANALYSES OF RPV UNDER SOME PTS TRANSIENTS
• Sensitivity Analysis of Failure Probability on PTS Benchmark Problems of Pressure Vessel Using a Probabilistic Fracture Mechanics Analysis Code
• Crack Opening Area of Pressurized Pipe for Leak-before-Break Evaluation

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