Zobrazeno 1 - 10
of 142
pro vyhledávání: '"Anton Möslang"'
Publikováno v:
Materials & Design, Vol 213, Iss , Pp 110316- (2022)
Austenitic oxide dispersion strengthened steels were developed to serve as a structural material in power plants. Mechanical alloying is used with the aim to homogeneously distribute rare earth elements like yttrium inside a steel matrix to form stre
Externí odkaz:
https://doaj.org/article/46ee77999e874e5a902d9be6a342bf94
Autor:
Frederik Arbeiter, Eberhard Diegele, Ulrich Fischer, Angela Garcia, Angel Ibarra, Joaquin Molla, Fernando Mota, Anton Möslang, Yuefeng Qiu, Marta Serrano, Florian Schwab
Publikováno v:
Nuclear Materials and Energy, Vol 16, Iss , Pp 245-248 (2018)
IFMIF-DONES (International Fusion Materials Irradiation Facility - DEMO-oriented Neutron Source) is currently being developed in the frame of the EUROfusion Early Neutron Source work package (WPENS), based on the results achieved in the ongoing IFMIF
Externí odkaz:
https://doaj.org/article/a178d956e9e04279830458f316b3e0d0
Autor:
Tim Gräning, Michael Rieth, Anton Möslang, Alexei Kuzmin, Andris Anspoks, Janis Timoshenko, Arturs Cintins, Juris Purans
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 237-243 (2018)
Austenitic oxide dispersion strengthened (ODS) steels are one of the candidates as a structural material for high-temperature applications in future power plants. To guarantee the necessary high production yield, the production process was improved i
Externí odkaz:
https://doaj.org/article/6d50fbc012dd4e7e850e7a533d651877
Publikováno v:
Journal of Nuclear Materials 523(2019), 111-120
Journal of nuclear materials, 523, 111-120
NuMat 2018, 14.-18.10.2018, Seattle, USA
Journal of nuclear materials, 523, 111-120
NuMat 2018, 14.-18.10.2018, Seattle, USA
Introduction: Oxide dispersion strengthened (ODS) steels have proven to be a viable candidate as a structural material in a fusion power plant, due to their enhanced mechanical properties and resilience under irradiation and at high temperatures. A h
Publikováno v:
Computational Materials Science, 195, Art.-Nr.: 110403
Beryllium is considered as a neutron multiplier in the self-sustained fuel cycles of future fusion reactors like ITER and DEMO, thus the retention of tritium generated in transmutation events in beryllium is crucial for the operational safety of such
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ca2873cfd76ee783d640b8ac54cb399f
Publikováno v:
Journal of Nuclear Materials
Beryllium is a proposed neutron multiplier material in future fusion devices like ITER and DEMO. As such, numerous studies of neutron-irradiated beryllium specimen have shown the appearance of facetted bubbles with considerable tritium accumulation a
Autor:
H.-C. Schneider, Michael Dürrschnabel, Michael Rieth, U. Jäntsch, Anton Möslang, Michael Klimenkov
Publikováno v:
Journal of nuclear materials, 557, 153259
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 microscopy. The irradiation of up to 16.2 dpa damage dose at 300°C and 400°C was performed i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::86c5d920e32cdf3612ff9d24047fa1d4
https://publikationen.bibliothek.kit.edu/1000139080
https://publikationen.bibliothek.kit.edu/1000139080
Publikováno v:
Journal of nuclear materials, 538, Art.-Nr. 152231
Journal of Nuclear Materials
Journal of Nuclear Materials
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. Radiation-induced defects such as dislocation loops and voids were characterized by tran
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::56613700d92fb62f515748f1d7952882
https://publikationen.bibliothek.kit.edu/1000125087
https://publikationen.bibliothek.kit.edu/1000125087
Autor:
U. Jäntsch, Thomas Bergfeldt, A.A. Goraieb, Julia Lorenz, Ramil Gaisin, Jan Hoffmann, R. Rolli, Harald Leiste, Michael Klimenkov, V. Chakin, Anton Möslang, Pavel Vladimirov
Publikováno v:
Journal of Alloys and Compounds
According to the recently proposed changes of the HCPB design concept of tritium breeding blanket for the DEMO fusion reactor, massive Be12Ti blocks are considered to be used for neutron multiplication. The paper compares two possible fabrication rou
Autor:
Pavel Vladimirov, Eugene A. Kotomin, Aleksejs Gopejenko, Yuri F. Zhukovskii, Yu. A. Mastrikov, Anton Möslang
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms
Strengthening of the ODS steels by Y2O3 precipitates permits to increase their operation temperature and radiation resistance, which is important in construction materials for future fusion and advanced fission reactors. Both size and spatial distrib