Energy > Nuclear Waste Management and Safety as well as Radiation Research - All Topics
Although Germany decided to shut down all nuclear reactors for energy production until 2022, own reactor safety research is needed in future. The preservation of competence in nuclear engineering is essential for the safety assessment of nuclear power plants and nuclear projects in Germany and abroad. Only in that way Germany is able to influence international safety standards and to participate in international research projects.
Based on this background the work within the topic “Reactor Safety” is concentrated on the research on safety aspects of currently operating nuclear reactors and new reactor types being under development in the neighboring countries. It covers the development of methods for analyses of transients and postulated accidents, the investigation of ageing phenomena in materials and integrity of components, and the safety related aspects connected with the thermal fluid dynamics of cooling water or liquid metal flows. Especially after the Fukushima accident in 2011, the efforts on the investigation of accident management measures in nuclear reactors have been increased.
- Development and validation of neutron kinetic and thermal hydraulic methods for the analysis of design basis and severe accidents for nuclear reactors.
- Development and qualification of predictive Computational Fluid Dynamics (CFD) models for two-phase flows
- Conduction of industry-grade experiments for code validation using innovative measuring techniques (TOPFLOW facility)
- Exploration of the mechanisms of irradiation effects in reactor pressure vessel steels and Gen-IV candidate materials by means of nanostructural characterization, atomistic modelling and mechanical testing
- Grahn, A.; Gommlich, A.; Kliem, S. et.al.
Simulation of an MSLB scenario using the 3D neutron kinetic core model Dyn3D coupled with the CFD software Trio U
Nuclear Engineering and Design 315(2017), 117-127
- Höhne, T.; Gasiunas, S.; Šeporaitis, M.
Numerical Modelling of a Direct Contact Condensation Experiment using the AIAD Framework
International Journal of Heat and Mass Transfer 111(2017), 211-222
- Liao, Y.; Lucas, D.
Computational modelling of flashing flows: a literature survey
International Journal of Heat and Mass Transfer 111(2017), 246-265
- Das, A.; Viehrig, H. W.; Bergner, F. et.al.
Effect of microstructural anisotropy on fracture toughness of hot rolled 13Cr ODS steel – the role of primary and secondary cracking
Journal of Nuclear Materials 491(2017), 83-93
Involved HZDR institutes
- HZDR is a member of the "Kompetenzverbund Ost für Kerntechnik".
- HZDR participates in the NURESAFE project of the EU.