【開催報告】2026.9.30 -第201回構材ゼミ- Dr. David E.J. Armstrong (Department of Materials and Corpus Christi College University of Oxford)
講演後の集合写真
Professor David E.J. Armstrong (前列右から4番目)
- 日時
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2026年9月30日（水曜日）11：00-12:00
- 場所
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NIMS千現地区 先進構造材料研究棟5階カンファレンスルーム
- 講演題目
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High Resolution Microstructural and Mechanical Properties Evolution in
Radiation Damaged Tungsten - 講演者
-
Dr.David E.J. Armstrong
Department of Materials and Corpus Christi College
University of Oxford
https://www.materials.ox.ac.uk/peoplepages/armstrong.html
Abstract:
Tungsten is the leading candidate material for the plasma facing components of future fusion reactors. During operation it will be
subjected to extremes of: temperature, up to 3000 oC, radiation damage, up to 100 dpa, and high stresses in, several GPa. These
conditions are well understood in pristine material but much less understood in irradiated materials. During irradiation the tungsten
will transmute to rhenium, osmium and tantalum, with an initially pure tungsten sample containing up to 5 at% alloying element by the
end of life.
In this work I will give an overview of our efforts to characterise the effects that high heat flux’s and radiation damage has on the
microstructure and mechanical behaviour of tungsten using a combination of analytical SEM and TEM, diffraction imaging, atom probe
tomography and macro and nano mechanical testing methods. Samples studied will include fission neutron and ion irradiated samples and
surveillance samples from the JET tokamak.
Two key questions answered will be: 1) Does ion irradiation adequately mimic neutron damage, 2) are neutron irradiated microstructures
metastable?