Search Results - "KLIMENKOV, M"

New insights into microstructure of neutron-irradiated tungsten by Dürrschnabel, M., Klimenkov, M., Jäntsch, U., Rieth, M., Schneider, H. C., Terentyev, D.

“…The development of appropriate materials for fusion reactors that can sustain high neutron fluence at elevated temperatures remains a great challenge. Tungsten…”
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Correlation of microstructural and mechanical properties of neutron irradiated EUROFER97 steel by Klimenkov, M., Jäntsch, U., Rieth, M., Möslang, A.

“…The reduced activation ferritic-martensitic (RAFM) steel EUROFER97 was neutron irradiated to an average dose of 16.3 dpa at temperatures from 250 °C to 415 °C…”
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Investigation of a high-dose irradiated beryllium microstructure by Zimber, N., Vladimirov, P., Klimenkov, M., Kuksenko, V.

“…The present paper studies the evolving Be microstructure after high-dose neutron irradiation at 660 K, 753 K and 873 K up to 34 dpa and generation of 5524 appm…”
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Effect of irradiation temperature on microstructure of ferritic-martensitic ODS steel by Klimenkov, M., Lindau, R., Jäntsch, U., Möslang, A.

“…The EUROFER-ODS alloy with 0.5% Y2O3 was neutron irradiated with doses up to 16.2 dpa at 250 °C, 350 °C and 450 °C. The radiation induced changes in the…”
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Quantitative measurement of argon inside of nano-sized bubbles in ODS steels by Klimenkov, M.

“…Quantitative analysis of Ar gas in nano-sized bubbles in ODS steel was performed using spatially resolved energy-dispersive X-ray spectroscopy. The Ar Kα line…”
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Effects of neutron irradiation on the brittle to ductile transition in single crystal tungsten by Abernethy, R.G., Gibson, J.S.K.-L., Giannattasio, A., Murphy, J.D., Wouters, O., Bradnam, S., Packer, L.W., Gilbert, M.R., Klimenkov, M., Rieth, M., Schneider, H.-C., Hardie, C.D., Roberts, S.G., Armstrong, D.E.J.

“…Only limited data exist on the effect of neutron irradiation on the brittle to ductile transition (BDT) in tungsten. This work investigates the increase in…”
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First simultaneous detection of helium and tritium inside bubbles in beryllium by Klimenkov, M., Vladimirov, P., Hoffmann, J., Zimber, N., Möslang, A., Kuksenko, V.

“…•First simultaneous EELS detection of helium and tritium enclosed inside flat bubbles formed in irradiated beryllium.•Observation of tritium absorption on…”
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Helium influence on the microstructure and swelling of 9%Cr ferritic steel after neutron irradiation to 16.3 dpa by Klimenkov, M., Möslang, A., Materna-Morris, E.

“…Specially fabricated samples of the European reference 9Cr-WTaV steel EUROFER 97 alloyed with 0.081 mass% natural B and 0.081 and 0.114 mass% pure isotope…”
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TEM study of hydrogen-containing precipitates in Al-containing ODS steel by Klimenkov, M.

“…The production process of ODS steels for application in fusion technology includes mechanical alloying as a preparation step where hydrogen is used as a…”
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New insights into microstructure of irradiated beryllium based on experiments and computer simulations by Klimenkov, M., Vladimirov, P., Jäntsch, U., Kuksenko, V., Rolli, R., Möslang, A., Zimber, N.

“…The microstructural response of beryllium after neutron irradiation at various temperatures (643–923 K) was systematically studied using analytical…”
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Post-irradiation microstructural examination of EUROFER-ODS steel irradiated at 300°C and 400°C by Klimenkov, M., Jäntsch, U., Rieth, M., Dürrschnabel, M., Möslang, A., Schneider, H.C.

“…The effect of neutron irradiation on the microstructure of EUROFER-ODS alloy reinforced with an addition of 0.5% Y2O3 was analyzed by transmission electron…”
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New insights into the structure of ODS particles in the ODS-Eurofer alloy by Klimenkov, M., Lindau, R., Möslang, A.

“…An oxide dispersion-strengthened alloy with 0.35% yttrium oxide produced on the basis of Eurofer steel was characterised by analytical transmission electron…”
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TEM study of beryllium pebbles after neutron irradiation up to 3000 appm helium production by KLIMENKOV, M, CHAKIN, V, MOESLANG, A, ROLLI, R

“…Beryllium is planned to be used as a neutron multiplier in the Helium Cooled Pebble Bed (HCPB) European concept of a breeding blanket of DEMO. In order to…”
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Microstructural evolution of three potential fusion candidate steels under ion-irradiation by Zimber, N., Vladimirov, P., Klimenkov, M., Jäntsch, U., Vila, R., Chakin, V., Mota, F.

“…The present paper studies the gas bubble distribution in triple beam irradiated (Fe+, He+, H+) EUROFER97, ODS-EUROFER and a 13%Cr ODS-steel. All materials were…”
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Radiation damage studies in fusion reactor steels by means of small-angle neutron scattering (SANS) by Coppola, R., Klimenkov, M., Lindau, R., Möslang, A., Rieth, M., Valli, M.

“…In this contribution, small-angle neutron scattering (SANS) studies of the micro-structural radiation damage in technical steels, developed for application in…”
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Author Correction: New insights into microstructure of irradiated beryllium based on experiments and computer simulations by Klimenkov, M., Vladimirov, P., Jäntsch, U., Kuksenko, V., Rolli, R., Möslang, A., Zimber, N.

“…An amendment to this paper has been published and can be accessed via a link at the top of the paper…”
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Evolution of the EUROFER97 microstructure during thermal treatment up to 122,000 h by Klimenkov, M., Jäntsch, U., Rieth, M., Möslang, A.

“…•Comprehensive study of the microstructure and precipitates evolution in EUROFER97 after annealing up to 122,000 h in the range between 450 °C and…”
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Characterization of precipitates in nano structured 14% Cr ODS alloys for fusion application by He, P., Klimenkov, M., Lindau, R., Möslang, A.

“…► We examine Ti influence on microstructure and mechanical properties of ODS steels. ► Ti addition leads to bimodal grain size distribution. ► The formation of…”
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Boron effect on the microstructure of 9% Cr ferritic–martensitic steels by Klimenkov, M., Materna-Morris, E., Möslang, A.

“…•Detailed TEM characterization of BN, M23C6, VN and TaC precipitates in B-alloyed EUROFER97.•Determination of B content influence on density and composition of…”
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Mechanical and microstructural properties of a hipped RAFM ODS-steel by Lindau, R., Möslang, A., Schirra, M., Schlossmacher, P., Klimenkov, M.

“…Oxide dispersion strengthened (ODS) materials for structural applications in future fusion power reactors would allow to increase the operating temperature to…”
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