Search Results - "MOESLANG, A"

Materials research for fusion by Knaster, J., Moeslang, A., Muroga, T.

“…Fusion materials research started in the early 1970s following the observation of the degradation of irradiated materials used in the first commercial fission…”
Get full text

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…”
Get full text

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…”
Get full text

Tritium and helium release from highly neutron irradiated titanium beryllide by Chakin, V., Rolli, R., Moeslang, A., Kurinskiy, P.

“…•Tritium and helium release from BeTi intermetallic compounds after high dose neutron irradiation was investigated.•Tritium release peaks from irradiated BeTi…”
Get full text

TEM study of impurity segregations in beryllium pebbles 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 European concept of a breeding blanket of demonstration power reactor…”
Get full text

Ab initio static and molecular dynamics studies of helium behavior in beryllium by Vladimirov, P.V., Moeslang, A.

“…Beryllium is an effective neutron multiplier material widely exploited in nuclear applications. It will be used in the helium-cooled beryllium pebble bed of…”
Get full text

Tritium release from highly neutron irradiated constrained and unconstrained beryllium pebbles by Chakin, V., Rolli, R., Vladimirov, P., Moeslang, A.

“…•For the irradiated constrained beryllium pebbles, the tritium release occurs easier than for the unconstrained ones.•Tritium retention in the irradiated…”
Get full text

Microstructure of out-of-pile annealed neutron irradiated beryllium studied by X-ray tomography by Vladimirov, P., Ferrero, C., Chakin, V., Kurinskiy, P., Moeslang, A., Pieritz, R., Weitkamp, T., Brun, E.

“…In fusion reactors, hydrogen isotopes, i.e., tritium and deuterium, will be used as fuel producing energetic neutrons and helium atoms. While deuterium is a…”
Get full text

Development of a helium-cooled divertor: Material choice and technological studies by Norajitra, P., Boccaccini, L.V., Gervash, A., Giniyatulin, R., Holstein, N., Ihli, T., Janeschitz, G., Krauss, W., Kruessmann, R., Kuznetsov, V., Makhankov, A., Mazul, I., Moeslang, A., Ovchinnikov, I., Rieth, M., Zeep, B.

“…Within the framework of the EU power plant conceptual study (PPCS), a He-cooled divertor concept has been investigated at Forschungszentrum Karlsruhe in…”
Get full text

Mechanical compression tests of beryllium pebbles after neutron irradiation up to 3000 appm helium production by Chakin, V., Rolli, R., Moeslang, A., Zmitko, M.

“…Results: of mechanical compression tests of irradiated and non-irradiated beryllium pebbles with diameters of 1 and 2 mm are presented. The neutron irradiation…”
Get full text

Hydrogen effects on tensile properties of EUROFER 97 and ODS-EUROFER steels by Yagodzinskyy, Y., Malitckii, E., Ganchenkova, M., Binyukova, S., Emelyanova, O., Saukkonen, T., Hänninen, H., Lindau, R., Vladimirov, P., Moeslang, A.

“…Hydrogen effects on the mechanical tensile properties of the ferrite–martensite EUROFER 97 and ODS-EUROFER steels were studied after electrochemical hydrogen…”
Get full text

Atom probe characterization of nano-scaled features in irradiated ODS Eurofer steel by Rogozhkin, S.V., Aleev, A.A., Zaluzhnyi, A.G., Nikitin, A.A., Iskandarov, N.A., Vladimirov, P., Lindau, R., Möslang, A.

“…Our previous investigations of unirradiated ODS Eurofer by tomographic atom probe (TAP) revealed numerous nano-scaled features (nanoclusters) enriched in…”
Get full text

Characteristics of microstructure, swelling and mechanical behaviour of titanium beryllide samples after high-dose neutron irradiation at 740 and 873 K by Kurinskiy, P, Moeslang, A, Chakin, V, Klimenkov, M, Rolli, R, van Til, S, Goraieb, A A

“…Titanium beryllide Be sub(12) Ti is one ot the candidate materials for advanced neutron multiplier in the helium-cooled breeding blanket of Demonstration Power…”
Get full text

The influence of thermomechanical processing on the microstructure and mechanical properties of 13.5Cr ODS steels by He, P., Lindau, R., Moeslang, A., Sandim, H.R.Z.

“…•The influence of TMP on microstructure and mechanical properties has been studied.•The HIP+TMP ODS steel has a sharp rotated-cube {100} 〈110〉 texture…”
Get full text

Tritium release and retention properties of highly neutron-irradiated beryllium pebbles from HIDOBE-01 experiment by Chakin, V., Rolli, R., Moeslang, A., Klimenkov, M., Kolb, M., Vladimirov, P., Kurinskiy, P., Schneider, H.-C., van Til, S., Magielsen, A.J., Zmitko, M.

“…The current helium cooled pebble bed (HCPB) tritium breeding blanket concept for fusion reactors includes a bed of 1mm diameter beryllium pebbles to act as a…”
Get full text

Development of a helium-cooled divertor concept: design-related requirements on materials and fabrication technology by Norajitra, P, Boccaccini, L.V, Diegele, E, Filatov, V, Gervash, A, Giniyatulin, R, Gordeev, S, Heinzel, V, Janeschitz, G, Konys, J, Krauss, W, Kruessmann, R, Malang, S, Mazul, I, Moeslang, A, Petersen, C, Reimann, G, Rieth, M, Rizzi, G, Rumyantsev, M, Ruprecht, R, Slobodtchouk, V

“…Within the framework of the EU power plant conceptual study (PPCS), a modular He-cooled divertor concept with integrated pin array (HEMP) is being developed at…”
Get full text

Characteristics of microstructure and tritium release properties of different kinds of beryllium pebbles for application in tritium breeding modules by Kurinskiy, P., Vladimirov, P., Moeslang, A., Rolli, R., Zmitko, M.

“…•Tritium release properties and characteristics of microstructure of beryllium pebbles having different sizes of grains were studied.•Fine-grained beryllium…”
Get full text

Comparative study of hydrogen uptake and diffusion in ODS steels by Malitckii, E., Yagodzinskyy, Y., Ganchenkova, M., Binyukova, S., Hänninen, H., Lindau, R., Vladimirov, P., Moeslang, A.

“…•The effect of strengthening of steels by yttrium oxide nanoparticles on their interaction with hydrogen is studied.•Hydrogen uptake and effective activation…”
Get full text

Investigation of oxide particles in unirradiated ODS Eurofer by tomographic atom probe by Aleev, A.A., Iskandarov, N.A., Klimenkov, M., Lindau, R., Möslang, A., Nikitin, A.A., Rogozhkin, S.V., Vladimirov, P., Zaluzhnyi, A.G.

“…Oxide dispersion strengthened steels possess better high-temperature creep and radiation resistance than conventionally produced ferritic/martensitic steels…”
Get full text

The IFMIF test facilities design by Moeslang, A., Heinzel, V., Matsui, H., Sugimoto, M.

“…IFMIF, the International Fusion Materials Irradiation Facility, is being developed by Europe, Japan, USA and Russia under the umbrella of the IEA. As the…”
Get full text