Dr. Polina Wilhelm
Co-head Reactor Safety Department
Reactor Safety
Phone: +49 351 260 3291

Personal web page of Polina Wilhelm

Scientific career

  • Since 2017/03:
    Co-head of the Reactor Safety Division, Institute of Resource Ecology, HZDR
  • 2016/06-2016/12:
    Consultant, International Atomic Energy Agency (IAEA), Vienna, Austria
  • 2012:
    PhD at TU Dresden, Mechanical Engineering/Nuclear Engineering, Germany
  • Since 2008:
    Scientific researcher, HZDR, Germany
  • 2006-2007:
    Scientific researcher, TU Dresden, Germany
  • 2002-2006:
    Scientific researcher, Energy Institute JSC, Sofia, Bulgaria
  • 2002:
    MSc at TU Sofia, Mechanical Engineering (Power Engineering and Power Machines)/Nuclear Engineering, Bulgaria

Research fields

  • Safety analysis of nuclear reactors
  • Severe accidents
  • Accident management and severe accident management measures and procedures
  • Severe accident management guidelines


Memberships / Board activities

  • NUGENIA Association, Technical Area TA2 Severe Accidents
  • IVMR project Steering Committee

Grants and Awards

  • Best paper award at the Annual Meeting of Nuclear Technology (AMNT), Berlin (2015)
  • HZDR Award for Scientific Communication (2011)
  • HZDR Guest Scientist Fellowship (2007/10-2008/01)
  • Herbert Quandt-Stiftung, ALTANA AG Fellowship (2006/10-2007/09)
  • SARNET Project Fellowship (2006/07-2006/08)
  • DAAD German Academic Exchange Service Graduate Fellowship (2002/04-2002/06)



Statistical Analysis of the Early Phase of SBO Accident for PWR
Kozmenkov, Y.; Jobst, M.; Kliem, S.; Schaefer, F.; Wilhelm, P.


WASA-BOSS: ATHLET-CD model for severe accident analysis for a generic KONVOI reactor
Tusheva, P.; Schäfer, F.; Kozmenkov, Y.; Kliem, S.; Hollands, T.; Trometer, A.; Buck, M.
  • Contribution to proceedings
    Jahrestagung Kerntechnik/Annual Meeting on Nuclear Technology, 05.-07.05.2015, Berlin, Germany
  • Lecture (Conference)
    Jahrestagung Kerntechnik/Annual Meeting on Nuclear Technology, 05.-07.05.2015, Berlin, Germany
  • atw - International Journal for Nuclear Power 60(2015)7, 442

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.


Assessment of accident management measures on early in-vessel station blackout sequence at VVER-1000 pressurized water reactors
Tusheva, P.; Schäfer, F.; Reinke, N.; Kamenov, A.; Mladenov, I.; Kamenov, K.; Kliem, S.


Study on severe accidents and countermeasures for VVER-1000 reactors using the integral code ASTEC
Tusheva, P.; Schäfer, F.; Reinke, N.; Altstadt, E.; Kliem, S.
  • Kerntechnik 77(2012)4, 271-277


Investigation on primary side oriented accident management measures in a station blackout scenario for a VVER-1000 reactor
Tusheva, P.; Schaefer, F.; Reinke, N.; Altstadt, E.; Rohde, U.; Weiss, F.-P.; Hurtado, A.