M&M材料力学カンファレンス
Online ISSN : 2424-2845
セッションID: 1006
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1006 Ni基合金円筒溶接継手の破壊強度評価(OS10-2 供用エネルギー機器の経年変化と健全性評価-破壊評価-)
小川 和夫北条 公伸室屋 格小川 直輝
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会議録・要旨集 フリー

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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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