A. Moeslang - Concepedia

Author

A. Moeslang

Karlsruhe Institute of Technology

Also Known As

A Moeslang, A. Moeslang, Anton Moeslang, Moeslang, A., Möslang, A.

Publications

1.7K

Citations

H-Index

Concepts

All Affiliations

Karlsruhe Institute of Technology FZI Research Center for Information Technology Nuclear Research and Consultancy Group National Research Nuclear University MEPhI Fusion for Energy

About

A. Moeslang is an author at Karlsruhe Institute of Technology specializing in engineering, materials science, and nuclear engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	18	32	1.5K
2	Natural Sciences	7	7	172
3	Applied Physics	4	4	54
4	Chemical Engineering	2	2	61
5	Computer Engineering	1	1	84

A. Moeslang

Publications

1.6K

Citations

H-Index

Page 1

	Year	Citations
Materials research for fusion J. Knaster, A. Moeslang, T. Muroga Nature Physics Materials EngineeringMaterials ScienceEngineeringFusion PowerFusion Energy	2016	500
Development of a helium-cooled divertor: Material choice and technological studies P. Norajitra, L.V. Boccaccini, A. Gervash, Journal of Nuclear Materials Materials ScienceEngineeringDivertor PhysicsHelium-cooled DivertorMechanical Engineering	2007	164
Development of a helium-cooled divertor concept: design-related requirements on materials and fabrication technology P. Norajitra, L.V. Boccaccini, E. Diegele, Journal of Nuclear Materials EngineeringHelium-cooled Divertor ConceptDivertor PhysicsMechanical EngineeringFabrication Technology	2004	131
The IFMIF test facilities design A. Moeslang, V. Heinzel, H. Matsui, Fusion Engineering and Design Reliability EngineeringEngineeringSoftware TestingComputer EngineeringSystems Engineering	2006	84
Development of brazing foils to join monocrystalline tungsten alloys with ODS-EUROFER steel B. A. Kalin, O.N. Sevrjukov, A. N. Kalashnikov, Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringPowder MetallurgyCorrosion	2007	65
Towards a programme of testing and qualification for structural and plasma-facing materials in ‘fusion neutron’ environments D. Stork, R. Heidinger, T. Muroga, Nuclear Fusion EngineeringNuclear PhysicsRadiation Materials ScienceReactor PhysicsFusion Materials	2017	57
Development of rapidly quenched brazing foils to join tungsten alloys with ferritic steel B. A. Kalin, O.N. Sevrjukov, A. Moeslang, Journal of Nuclear Materials Materials EngineeringTungsten AlloysMaterials ScienceFerritic SteelEngineering	2004	43
Current Status of Beryllium Materials for Fusion Blanket Applications P. Vladimirov, V. Chakin, Maria Ganchenkova, Fusion Science & Technology Materials ScienceMaterials EngineeringChemical EngineeringBeryllium PebblesBeryllium Behavior	2014	38
TEM study of beryllium pebbles after neutron irradiation up to 3000appm helium production M. Klimenkov, V. Chakin, A. Moeslang, Journal of Nuclear Materials Materials ScienceNuclear CeramicBeryllium PebblesEngineeringPhysics	2013	37
Characteristics of microstructure, swelling and mechanical behaviour of titanium beryllide samples after high-dose neutron irradiation at 740 and 873K P. Kurinskiy, A. Moeslang, V. Chakin, Fusion Engineering and Design Materials ScienceNuclear CeramicEngineeringMechanical EngineeringNeutron Source	2013	31

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