電子線照射下における原子炉圧力容器モデル合金Ｆｅ‐１．４Ｍｎのその場観察

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  • In Situ Observation of the Effect of Stress on A533B Model Alloy Fe-1.4Mn under Electron Irradiation

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  PWR type nuclear reactor pressure vessels are neutron irradiated with stress during reactor operation. Therefore, it is important to know the effect of irradiation embrittlement of the material with and without stress conditions. It is already known that radiation hardening of the materials controlled by dislocation density in many materials. In the pressure vessel steels and model alloys, dislocation loop density is very sensitive to solutes (namely, Mn, Ni, Si etc.) levels containing in the alloy. Formation of small dislocation loops is prominent without applied stress in the matrix and also in the vicinity of dislocation in Mn containing alloys. These dislocation loops were identified as interstitial type dislocation loops. In this study, Microstructure evolution of Fe-1.4 mass% Mn alloy was studied in high voltage electron microscope (HVEM) by using a tensile sample holder. With stress condition, I-loop density was suppressed. But growth of I-loop becomes prominent.<br>

収録刊行物

  • 日本金属学会誌

    日本金属学会誌 75 (3), 173-178, 2011

    公益社団法人 日本金属学会

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