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

2018

Why do secondary cracks preferentially form in hot-rolled ODS steels in comparison with hot-extruded ODS steels?
Das, A.ORC; Viehrig, H. W.; Altstadt, E.ORC; Bergner, F.ORC; Hoffmann, J.ORC

Determining the ultimate tensile strength of fuel cladding tubes by small punch testing
Simonovski, I.; Baraldi, D.; Holmström, S.; Altstadt, E.ORC; Delville, R.; Bruchhausen, M.

Effect of ausforming temperature on creep strength of G91 investigated by means of small punch creep tests
Vivas, J.; Capdevila, C.ORC; Altstadt, E.ORC; Houska, M.; Serrano, M.ORC; De-Castro, D.; San-Martin, D.

Importance of austenitization temperature and ausforming on creep strength in 9Cr ferritic/martensitic steel
Vivas, J.; Capdevila, C.ORC; Altstadt, E.ORC; Houska, M.; San-Martin, D.

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.ORC; Ulbricht, A.; Altstadt, E.

On the estimation of ultimate tensile stress from small punch testing
Altstadt, E.; Houska, M.; Simonovski, I.; Bruchhausen, M.; Holmström, S.; Lacalle, R.

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.

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.

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.

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.

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.

Ion irradiation combined with nanoindentation as a screening test procedure for irradiation hardening
Heintze, C.; Bergner, F.; Akhmadaliev, S.; Altstadt, E.

2015

Towards safe long-term operation of reactor pressure vessels
Rouden, J.; Hein, H.; May, J.; Planman, T.; Todeschini, P.; Brumovsky, M.; Ballesteros, A.; Gillemot, F.; Chaouadi, R.; Efsing, P.; Altstadt, E.
  • atw - International Journal for Nuclear Power 60(2015)5, 287-293

Contributions of Cu-rich clusters, dislocation loops and nanovoids to the irradiation-induced hardening of Cu-bearing low-Ni reactor pressure vessel steels
Bergner, F.; Gillemot, F.; Hernández-Mayoral, M.; Serrano, M.; Török, G.; Ulbricht, A.; Altstadt, E.

Radiation and annealing response of WWER 440 beltline welding seams
Viehrig, H.-W.; Houska, M.; Altstadt, E.

Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor
Tusheva, P.; Altstadt, E.; Willschütz, H.-G.; Fridman, E.; Weiß, F.-P.

Radiation response of the overlay cladding from the decommissioned WWER-440 Greifswald unit 4 reactor pressure vessel
Viehrig, H.-W.; Altstadt, E.; Houska, M.

2014

Reactor pressure vessel surveillance
Ballesteros, A.; Hein, H.; May, J.; Planman, T.; Todeschini, P.; Brumovsky, M.; Gillemot, F.; Chaouadi, R.; Rouden, J.; Efsing, P.; Altstadt, E.
  • Nuclear Engineering International 59(2014)724, 19-20

FP7 Project LONGLIFE: Overview of Results and Implications
Altstadt, E.; Keim, E.; Hein, H.; Serrano, M.; Bergner, F.; Viehrig, H.-W.; Ballesteros, A.; Chaouadi, R.; Wilford, K.

Monitoring radiation embrittlement during life extension periods
Ballesteros, A.; Altstadt, E.; Gillemot, F.; Hein, H.; Wagemans, J.; Rouden, J.; Barthelmes, J.; Wilford, K.; Serrano, M.; Brumovsky, M.; Chaouadi, R.; Ortner, S.