Fe-Mn合金の応力下での欠陥形成のその場観察

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タイトル別名
  • In-situ observation of damage formation in Fe-Mn alloy
  • Fe Mn ゴウキン ノ オウリョク カ デ ノ ケッカン ケイセイ ノ ソノバ カンサツ

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抄録

PWR type nuclear reactor pressure vessels is added stress when it during operation. Therefore it is important to know the effect of irradiation brittleness of the material. To study the influence of the stress on the nuclear reactor pressure vessel steal, the sample was irradiated under applied stress by using a high voltage electron microscope. Fe-1.4(w %) Mn alloy was used in this study as model alloy of A533B steel. The influence of the damage formation process was discussed in this paper.

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