Helmholtz-Zentrum Dresden-Rossendorf
Structural Materials
Dr. Eberhard Altstadt
Head
Phone
+49 351 260 2276
e.altstadthzdr.de
Link
ORCID: 0000-0002-1177-2650
Address
Building/Office
Bautzner Landstraße 400 - 01328 Dresden
801/P151
Professional record
- Since 2004: Head of Department Structural Materials
- 1992-2003: Senior scientist at Hemholtz-Zentrum Dresden-Rossendorf, Germany
- 1989-1991: Scientist at Central Institute of Nuclear Research of the Academy of Science, Germany
- 1985-1989: Scientist at Dresden University of Technology, Germany
- 1989: PhD in Applied Mechanics, Dresden University of Technology, Germany
- 1985: Diploma in Engineering, Dresden University of Technology, Germany
Research fields
- Irradiation effects in structural materials
- Materials testing
- Fracture mechanics
- Small punch test
Memberships / Board activities
- Since 2008: member of project committee "Components safety" of the Project Management Agency "Reactor Safety Research"
- Since 2011: member of the steering committee of the EERA Joint Programme of Nuclear Materials
- Since 2016: member of the working group "Creep and relaxation testing" of the DIN
Recent publications
Scopus Author ID: 6602673970; ORCID: 0000-0002-1177-2650
2021
Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels
Altstadt, E.; Bergner, F.; Houska, M.
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Nuclear Materials and Energy 26(2021), 100918
DOI: 10.1016/j.nme.2021.100918
ISSN: 2352-1791
Cited 8 times in Scopus
2020
Development of New 14 Cr ODS Steels by Using New Oxides Formers and B as an Inhibitor of the Grain Growth
Meza, A.; Macía, E.; García-Junceda, A.; Antonio Díaz, L.; Chekhonin, P.; Altstadt, E.; Serrano, M.; Eugenia Rabanal, M.; Campos, M.
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Metals 10(2020)10, 1344
DOI: 10.3390/met10101344
Cited 3 times in Scopus
Brittle-ductile transition temperature of recrystallized tungsten following exposure to fusion relevant cyclic high heat load
Shah, V.; van Dommelen, J. A. W.; Altstadt, E.; Das, A.; Geers, M. G. D.
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Journal of Nuclear Materials 541(2020), 152416
DOI: 10.1016/j.jnucmat.2020.152416
Cited 14 times in Scopus
Design and high temperature behavior of novel heat resistant steels strengthened by high density of stable nanoprecipitates
Vivas, J.; De-Castro, D.; Altstadt, E.; Houska, M.; San-Martin, D.; Capdevila, C.
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Materials Science and Engineering A 739(2020), 139799
DOI: 10.1016/j.msea.2020.139799
Cited 5 times in Scopus
Microstructure and fracture toughness characterization of three 9Cr ODS EUROFER steels with different thermo-mechanical treatments
Das, A.; Chekhonin, P.; Altstadt, E.; Mcclintock, D.; Bergner, F.; Heintze, C.; Lindau, R.
Related publications
- DOI: 10.17815/jlsrf-3-159 is cited by this (Id 31183) publication
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Journal of Nuclear Materials 542(2020), 152464
Online First (2020) DOI: 10.1016/j.jnucmat.2020.152464
Cited 7 times in Scopus
Relationships between depth-resolved primary radiation damage, irradiation-induced nanostructure and nanoindentation response of ion-irradiated Fe-Cr and ODS Fe-Cr alloys
Vogel, K.; Heintze, C.; Chekhonin, P.; Akhmadaliev, S.; Altstadt, E.; Bergner, F.
Related publications
- DOI: 10.17815/jlsrf-3-159 is cited by this (Id 30720) publication
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Nuclear Materials and Energy 24(2020), 100759
DOI: 10.1016/j.nme.2020.100759
Cited 8 times in Scopus
Microstructural characterization of inhomogeneity in 9Cr ODS EUROFER steel
Das, A.; Chekhonin, P.; Altstadt, E.; Bergner, F.; Heintze, C.; Lindau, R.
Related publications
- DOI: 10.17815/jlsrf-3-159 is cited by this (Id 29964) publication
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Journal of Nuclear Materials 533(2020), 152083
Online First (2020) DOI: 10.1016/j.jnucmat.2020.152083
ISSN: 0022-3115
Cited 8 times in Scopus
2019
Developments in the estimation of tensile strength by small punch testing
Holmström, S.; Simonovski, I.; Baraldi, D.; Bruchhausen, M.; Altstadt, E.; Delville, R.
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Theoretical and Applied Fracture Mechanics 101(2019), 25-34
DOI: 10.1016/j.tafmec.2019.01.020
Cited 18 times in Scopus
Effect of anisotropic microstructure of ODS steels on small punch test results
Altstadt, E.; Bergner, F.; Das, A.; Houska, M.
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Theoretical and Applied Fracture Mechanics 100(2019), 191-199
DOI: 10.1016/j.tafmec.2019.01.014
Cited 12 times in Scopus
Microstructural degradation and creep fracture behavior of conventionally and thermomechanically treated 9% Chromium Heat Resistant steel
Vivas, J.; Capdevila, C.; Altstadt, E.; Houska, M.; Sabirov, I.; San-Martín, D.
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Metals and Materials International 25(2019)2, 343-352
DOI: 10.1007/s12540-018-0192-6
Cited 18 times in Scopus
2018
Why do secondary cracks preferentially form in hot-rolled ODS steels in comparison with hot-extruded ODS steels?
Das, A.; Viehrig, H. W.; Altstadt, E.; Bergner, F.; Hoffmann, J.
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Crystals 8(2018)8, 306
Online First (2018) DOI: 10.3390/cryst8080306
Cited 3 times in Scopus
Determining the ultimate tensile strength of fuel cladding tubes by small punch testing
Simonovski, I.; Baraldi, D.; Holmström, S.; Altstadt, E.; Delville, R.; Bruchhausen, M.
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Journal of Nuclear Materials 509(2018), 620-630
DOI: 10.1016/j.jnucmat.2018.07.041
Cited 14 times in Scopus
Effect of ausforming temperature on creep strength of G91 investigated by means of small punch creep tests
Vivas, J.; Capdevila, C.; Altstadt, E.; Houska, M.; Serrano, M.; De-Castro, D.; San-Martin, D.
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Materials Science and Engineering A 728(2018), 259-265
DOI: 10.1016/j.msea.2018.05.023
Cited 13 times in Scopus
Importance of austenitization temperature and ausforming on creep strength in 9Cr ferritic/martensitic steel
Vivas, J.; Capdevila, C.; Altstadt, E.; Houska, M.; San-Martin, D.
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Scripta Materialia 153(2018), 14-18
DOI: 10.1016/j.scriptamat.2018.04.038
Cited 21 times in Scopus
Nanoindentation of ion-irradiated reactor pressure vessel steels – model-based interpretation and comparison with neutron irradiation
Röder, F.; Heintze, C.; Pecko, S.; Akhmadaliev, S.; Bergner, F.; Ulbricht, A.; Altstadt, E.
Related publications
- DOI: 10.17815/jlsrf-3-159 is cited by this (Id 26396) publication
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Philosophical Magazine 98(2018)11, 911-933
Online First (2018) DOI: 10.1080/14786435.2018.1425007
Cited 18 times in Scopus
On the estimation of ultimate tensile stress from small punch testing
Altstadt, E.; Houska, M.; Simonovski, I.; Bruchhausen, M.; Holmström, S.; Lacalle, R.
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International Journal of Mechanical Sciences 136(2018), 85-93
DOI: 10.1016/j.ijmecsci.2017.12.016
Cited 56 times in Scopus
2017
On the influence of microstructure on fracture behaviour of hot extruded ferritic ODS steels
Das, A.; Viehrig, H. W.; Altstadt, E.; Heintze, C.; Hoffmann, J.
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Journal of Nuclear Materials 497(2017), 60-75
Online First (2017) DOI: 10.1016/j.jnucmat.2017.10.051
Cited 5 times in Scopus
Effect of microstructural anisotropy on fracture toughness of hot rolled 13Cr ODS steel – the role of primary and secondary cracking
Das, A.; Viehrig, H. W.; Bergner, F.; Heintze, C.; Altstadt, E.; Hoffmann, J.
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Journal of Nuclear Materials 491(2017), 83-93
Online First (2017) DOI: 10.1016/j.jnucmat.2017.04.059
Cited 21 times in Scopus
2016
Effect of neutron flux on the characteristics of irradiation-induced nanofeatures and hardening in pressure vessel steels
Wagner, A.; Bergner, F.; Chaouadi, R.; Hein, H.; Hernández-Mayoral, M.; Serrano, M.; Ulbricht, A.; Altstadt, E.
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Acta Materialia 104(2016), 131-142
DOI: 10.1016/j.actamat.2015.11.027
Cited 34 times in Scopus
Effect of anisotropic microstructure of a 12Cr ODS steel on the fracture behaviour in the small punch test
Altstadt, E.; Serrano, M.; Houska, M.; Garcia-Junceda, A.
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Materials Science and Engineering A 654(2016), 309-316
DOI: 10.1016/j.msea.2015.12.055
Cited 31 times in Scopus
Critical evaluation of the small punch test as a screening procedure for mechanical properties
Altstadt, E.; Ge, H. E.; Kuksenko, V.; Serrano, M.; Houska, M.; Lasan, M.; Bruchhausen, M.; Lapetite, J.-M.; Dai, Y.
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Journal of Nuclear Materials 472(2016), 186-195
DOI: 10.1016/j.jnucmat.2015.07.029
Cited 61 times in Scopus
Ion irradiation combined with nanoindentation as a screening test procedure for irradiation hardening
Heintze, C.; Bergner, F.; Akhmadaliev, S.; Altstadt, E.
Related publications
- DOI: 10.17815/jlsrf-3-159 is cited by this (Id 21355) publication
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Journal of Nuclear Materials 472(2016), 196-205
Online First (2015) DOI: 10.1016/j.jnucmat.2015.07.023
Cited 62 times in Scopus