SB-02-3(046) Creep Failure of Reactor Cooling System Piping of Nuclear Power Plant under Severe Accident Conditions(Materials Performance in Nuclear Application 2)

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概要

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• The integrity of reactor cooling system piping during severe accidents of light water reactors is being investigated at Japan Atomic Energy Research Institute. The investigation is composed of piping failure tests, material property measurement and creep analyses. In the piping failure tests, piping made of stainless steels (SUS316 or CF8M), carbon steel or Inconel 690 is loaded with a constant internal pressure and an elevated temperature. Deformation features and time to failure have been obtained under various pressure and temperature conditions. The creep analyses were performed by ABAQUS code being furnished with creep equations based on the material property measurement. A three -dimensional analysis with shell elements for the test with small-diameter pipe (114.3 mm in an outer diameter) made of nuclear grade SUS316 significantly underes timated the deformation, resulting in a longer time to failure. Two -dimensional analyses with solid and shell elements indicated that this discrepancy would have resulted from the use of shell elements. A two-dimensional analysis with solid elements predicted well the time to failure of a thin steam generator U -tube (22.23 mm in an outer diameter) made of Inconel 690.

• 一般社団法人日本機械学会の論文
• 2001-06-03

著者

• Nakamura H.

  Department of Physics, Osaka University

• HASHIMOTO K.

  Department of Information Physics and Computing, University of Tokyo

• HARADA Y.

  Department of Orthopaedic Surgery, Chiba University School of Medicine

• MARUYAMA Y.

  Department of Plastic and Reconstructive Surgery, and Department of Orthopedic Surgery, Faculty of M

• KUDO T.

  Departments of Surgery Neuro-surgical Division,School of Medicine,Keio University

• Shibazaki H.

  Department Of Reactor Safety Research Japan Atomic Energy Research Institute

• Chino E.

  Department of Reactor Safety Research Japan Atomic Energy Research Institute

• Maeda A.

  System Engineering Department MRI Systems Inc.

• Hidaka A.

  Department of Reactor Safety Research Japan Atomic Energy Research Institute

• Yuchi Y.

  Department of Reactor Safety Research Japan Atomic Energy Research Institute

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