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Fabrication, characterization, and irradiation of an austenitic oxide dispersion strengthened steel suited for next generation nuclear applications.

机译：奥氏体氧化物弥散强化钢的制造，表征和辐照，适用于下一代核应用。

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作者
Brooks, Adam J.;
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作者单位

Queen's University (Canada).;

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授予单位 Queen's University (Canada).;
学科 Materials science.;Nuclear engineering.
学位 M.A.Sc.
年度 2016
页码 146 p.
总页数 146
原文格式 PDF
正文语种 eng
中图分类
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1. Processing and characterization of a hipped oxide dispersion strengthened austenitic steel (Conference Paper) [J] . Zhou Z., Yang S., Chen W., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2012,第1a3期

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2. Irradiation creep of oxide dispersion strengthened (ODS) steels for advanced nuclear applications [J] . Chen JC, Hoffelner W Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2009,第2期

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3. Fabrication and characterization of oxide dispersion strengthened (ODS) 14Cr steels consolidated by means of hot isostatic pressing, hot extrusion and spark plasma sintering [J] . Hilger I., Boulnat X., Hoffmann J., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2016,第Null期

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4. Development of High Irradiation Resistant and Corrosion Resistant Oxide Dispersion Strengthened Austenitic Stainless Steels [C] . Takahiro Ishizaki, Yusaku Maruno, Kiyohiro Yabuuchi, International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors . 2018

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Fabrication, characterization, and irradiation of an austenitic oxide dispersion strengthened steel suited for next generation nuclear applications.

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