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
Related publications
Why are hot-rolled ODS steels more prone to secondary… (Id 28114) is an alternate identifier of this publication

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.