brittle behaviorとは 意味・読み方・使い方

MARINE STEEL WITH EXCELLENT CORROSION RESISTANCE AND BRITTLE CRACK ARREST BEHAVIOR例文帳に追加

耐食性および脆性亀裂停止特性に優れた船舶用鋼材 - 特許庁

In this fatigue characteristic determination method of a material, a fatigue test of a brittle material is performed by increasing the amplitude of a stress to be applied to the brittle material at a fixed rate together with a cycle as shown in Fig.1(b), and the optimum value of a parameter of a fatigue behavior is acquired by analysis by using the result of the fatigue test.例文帳に追加

図１(b)に示すように、脆性材料に与える応力の振幅をサイクルとともに一定割合で増加させて脆性材料の疲労試験を行い、この疲労試験の結果を用い、解析により疲労挙動のパラメータの最適値を得る。 - 特許庁

A composite material in which a continuum, such as a ceramic wire material, etc. having conductivity and showing brittle rupture behavior is installed in a resin molding of a long fiber-reinforced plastic, etc, is synthesized.例文帳に追加

導電性を有し且つ脆性的な破壊挙動を示すセラミックス線材等の連続体を長繊維強化プラスチックス等の樹脂成形体中に設置した複合材料を合成した。 - 特許庁

Concerning the reactor coolant pressure boundary, the Regulatory Guide for Reviewing Safety Design specifies the following: the reactor coolant pressure boundary shall be so designed that its integrity will be ensured during normal operation and abnormal conditions, the reactor coolant pressure boundary shall be designed not to exhibit brittle behavior and develop any quickly propagative failure during normal operation, maintenance, testing, and abnormal conditions, the leakage of the reactor coolant, if any, from the reactor coolant pressure boundary shall be designed to provide for quick and proper detection, the reactor coolant pressure boundary shall be designed to be capable of being tested and inspected to verify its integrity throughout the service life of the nuclear reactor, pressure on the reactor coolant pressure boundary shall not exceed the specified value during reactivity insertion events.例文帳に追加

原子炉冷却材圧力バウンダリ原子炉冷却材圧力バウンダリについては、通常運転時及び異常状態において、その健全性を確保できる設計であること、 通常運転時、保修時、試験時、及び異常状態において、脆性的挙動を示さず、かつ、急速な伝播型破断を生じない設計であること、 漏えいがあった場合その漏えいを速やかに確実に検出できる設計である子と 原子炉の供用期間中に試験及び検査ができる設計であること、反応度投入事象に対して、原子炉冷却材圧力バウンダリにかかる圧力が規定値を超えない設計であることが安全設計審査指針で求められている。 - 経済産業省