原子炉構造要素の破壊力学的評価技術に関する研究 : 第1章凝縮起因水撃による配管荷重 : 第2章動的強度および動的破壊靭性の評価

概要

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In the normal operation and transients of a light water power reactor, the structural components such as the pressure vessel and the primary loop piping suffer from various damages by neutrons, thermal aging, fatigue and dynamic loads. The evaluation methods applied for those effects up to now are based on the conservative assumptions. This research was carried out to improve those evaluation methods. For this purpose, three kinds of experiments were conducted. The first is the test of condensation-induced waterhammer in which large loads as well as sharp pressure spikes exerting on the pipe line were measured, and the mechanism and the loads following a condensation-induced waterhammer were made clear. The second is the dynamic loading test for structural materials and welding joints in which the dynamic strength and fracture toughness were investigated, and the evaluation method for those strength was discussed. In the third, an impact pressure testing machine was equipped and the strength properties of pressurized pipe were measured.
独立行政法人海上技術安全研究所の論文
1996-01-10