The Proceedings of the Materials and Mechanics Conference
Online ISSN : 2424-2845
2010
Session ID : 1006
Conference information
[title in Japanese]
Kazuo OGAWAKiminobu HOJOItaru MUROYANaoki OGAWA
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CONFERENCE PROCEEDINGS FREE ACCESS

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Abstract
For the purpose of establishing fracture evaluation method of Alloy 600 weld of nuclear power plants, fracture tests using pipe model(8B and 14B) with alloy 600 weld joint have been perfonned at RT and 325℃. Predicted loads calculated by limit load evaluation method using measured and code regulated flow stresses were compared with the maximum test loads. And the predicted loads of the pipe at 325℃(8B and 14B) and at RT(8B), the initial crack depth of which is 75% of the pipe thickness, were in good agreement with the maximum test loads.
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© 2010 The Japan Society of Mechanical Engineers
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