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Eberhard Altstadt
Eberhard Altstadt
Hemholtz-Zentrum Dresden-Rossendorf
Verified email at hzdr.de
Title
Cited by
Cited by
Year
On the estimation of ultimate tensile stress from small punch testing
E Altstadt, M Houska, I Simonovski, M Bruchhausen, R Lacalle
International Journal of Mechanical Sciences 136, 85-93, 2018
962018
Critical evaluation of the small punch test as a screening procedure for mechanical properties
E Altstadt, HE Ge, V Kuksenko, M Serrano, M Houska, M Lasan, ...
Journal of Nuclear Materials 472, 186-195, 2016
882016
Ion irradiation combined with nanoindentation as a screening test procedure for irradiation hardening
C Heintze, F Bergner, S Akhmadaliev, E Altstadt
Journal of Nuclear Materials 472, 196-205, 2016
862016
European standard on small punch testing of metallic materials
M Bruchhausen, T Austin, S Holmström, E Altstadt, P Dymacek, S Jeffs, ...
Pressure Vessels and Piping Conference 57908, V01AT01A065, 2017
832017
Contributions of Cu-rich clusters, dislocation loops and nanovoids to the irradiation-induced hardening of Cu-bearing low-Ni reactor pressure vessel steels
F Bergner, F Gillemot, M Hernández-Mayoral, M Serrano, G Török, ...
Journal of Nuclear Materials 461, 37-44, 2015
692015
Development of a neutron time-of-flight source at the ELBE accelerator
J Klug, E Altstadt, C Beckert, R Beyer, H Freiesleben, V Galindo, E Grosse, ...
Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2007
692007
Coupled thermal structural analysis of LWR vessel creep failure experiments
HG Willschütz, E Altstadt, BR Sehgal, FP Weiss
Nuclear Engineering and Design 208 (3), 265-282, 2001
592001
A photo-neutron source for time-of-flight measurements at the radiation source ELBE
E Altstadt, C Beckert, H Freiesleben, V Galindo, E Grosse, AR Junghans, ...
Annals of Nuclear Energy 34 (1-2), 36-50, 2007
582007
Effect of neutron flux on the characteristics of irradiation-induced nanofeatures and hardening in pressure vessel steels
A Wagner, F Bergner, R Chaouadi, H Hein, M Hernández-Mayoral, ...
Acta Materialia 104, 131-142, 2016
502016
Effect of anisotropic microstructure of a 12Cr-ODS steel on the fracture behaviour in the small punch test
E Altstadt, M Serrano, M Houska, A García-Junceda
Materials Science and Engineering: A 654, 309-316, 2016
452016
Recursively coupled thermal and mechanical FEM-analysis of lower plenum creep failure experiments
HG Willschütz, E Altstadt, BR Sehgal, FP Weiss
Annals of Nuclear Energy 33 (2), 126-148, 2006
452006
Simulation of creep tests with French or German RPV-steel and investigation of a RPV-support against failure
HG Willschütz, E Altstadt, BR Sehgal, FP Weiss
Annals of Nuclear Energy 30 (10), 1033-1063, 2003
432003
Importance of austenitization temperature and ausforming on creep strength in 9Cr ferritic/martensitic steel
J Vivas, C Capdevila, E Altstadt, M Houska, D San-Martín
Scripta Materialia 153, 14-18, 2018
402018
Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor
P Tusheva, E Altstadt, HG Willschuetz, E Fridman, FP Weiss
Annals of Nuclear Energy 75, 249-260, 2015
382015
Influence of the copper impurity level on the irradiation response of reactor pressure vessel steels investigated by SANS
A Wagner, A Ulbricht, F Bergner, E Altstadt
Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2012
362012
Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels
E Altstadt, F Bergner, M Houska
Nuclear Materials and Energy 26, 100918, 2021
352021
Extension of the ANSYS® creep and damage simulation capabilities
E Altstadt, T Mössner
342000
Effect of microstructural anisotropy on fracture toughness of hot rolled 13Cr ODS steel–The role of primary and secondary cracking
A Das, HW Viehrig, F Bergner, C Heintze, E Altstadt, J Hoffmann
Journal of Nuclear Materials 491, 83-93, 2017
312017
Developments in the estimation of tensile strength by small punch testing
S Holmström, I Simonovski, D Baraldi, M Bruchhausen, E Altstadt, ...
Theoretical and Applied Fracture Mechanics 101, 25-34, 2019
302019
Experimental study of interactions between suboxidized corium and reactor vessel steel
SV Bechta, VB Khabensky, VS Granovsky, EV Krushinov, SA Vitol, ...
Proceedings of the International Congress on Advances in Nuclear Power …, 2006
292006
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