原子炉容器ノズルコーナーき裂に対する 応力拡大係数解の妥当性検討


英字タイトル:
Study on Adequacy of Stress Intensity Factor Solutions for Nozzle Corner Cracks in Reactor Pressure Vessel
著者:
三浦 直樹 Naoki MIURA 中川 純二 Junji NAKAGAWA
発刊日:
公開日:
カテゴリ: 第11回
キーワードタグ:

概要

Japan Electric Association Code, JEAC4206-2007, “Method of Verification Tests of the Fracture Toughness for Nuclear Power Pla nt Components,” requires the prevention of the non-ductile fracture for supposed cracks in reactor pressure vessels. Structur al integrity for the supposed cracks with the depth of a quarter of the thickness is required for nozzle corner as well as fo r cylindrical body. The quantitative estimation of the margin against fracture with a high degree of accuracy is essential as one of the countermeasures to plant life management of reactor pressure vessels. In this report, stress intensity factor sol ions for nozzle corner cracks were investigated together with their technical basis. The applicability of the solutions was amined through the comparison with a finite element analysis result. It was ascertained that the present stress intensity fa or solution in the JEAC code gave reasonable calculation, and the Fife’s solution could be more promising for codification.


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