VTT Technical Research Centre of Finland is the biggest multi-technological applied research organisation in Northern Europe, and is a part of the Finnish innovation system under the domain of the Ministry of Employment and the Economy. VTT is a non-profit organisation that employs around 3,200 people and has an annual turnover of approx. 300 M€. out of which about 200 are active in nuclear energy R&D. VTT performs comprehensive contracted research in industry driven programmes on nuclear waste management, plant life management, operational and structural safety as well as on nuclear fuel performance. VTT is the major technical support organisation for the nuclear safety authority STUK as well as for the power companies. VTT has participated in numerous European projects on various aspects of nuclear power plant safety. The Nuclear Reactor Materials group in particular has been involved in the European projects PERFECT, LONGLIFE and PERFORM 60, where we have brought to bear our long track record in studying the fundamentals of reactor pressure vessel and reactor internals materials degradation. Particularly our literacy in modelling and strong experimental capability for testing and characterisation of neutron irradiated materials has produced important practical results utilised in past projects to support multiscale modelling efforts. These efforts will be sharpened and more focused in our contribution to the current project.
VTT participates in generating focused experimental data to support the modelling of RPV radiation embrittlement on the one hand, and initiation of irradiation assisted stress corrosion cracks (IASCC) on the other. Specific to RPV embrittlement, VTT utilises its field-emission gun equipped analytical transmission electron microscope and capacity to handle neutron irradiated materials, to characterise the microstructure and microchemistry of RPV material and isolate the influence of metallurgical macroscopic heterogeneities at initial state on RPV fracture behaviour upon subsequent neutron irradiation. For IASCC initiation, VTT employs its world-class autoclave test facilities to conduct carefully instrumented crack initiation tests of neutron irradiated stainless steel in simulated reactor environment, to assess environmental effects on the internals crack initiation process.
|Wade Karlsen, PhD, Senior Scientist and Research Team Leader of Nuclear Reactor Materials team
Expert in nuclear power plant materials degradation due to environmental effects, thermal aging and neutron irradiation. Expert in analytical transmission electron microscopy, particularly with radiation defects and radiation-induced segregation. Familiar with utilisation of mechanical testing, autoclave exposure and bellows-driven special mechanical testing devices for study of materials performance, particularly of neutron-irradiated materials. Granted a Ph.D. in Materials Science and Engineering in 1997 from Oregon Graduate Institute of Science and Technology, U.S.A.
|Mykola Ivanchenko, PhD, Research Scientist
Principle operator of transmission electron microscope for characterisation of irradiated metals. Expert in mechanical testing, mechanical spectroscopy (internal friction), hardness and microhardness tests, optical and scanning electron microscopy, electrochemical materials treatment, heat treatment. Scope of research interest includes mechanical properties and characterisation of austenitic and ferritic stainless steels, Ni-base alloys and their welds, copper and different copper welds. Dr.Tech. in Engineering Materials awarded by Aalto University School of Science and Technology in 2010.
|Caitlin Hurley, PhD, Research Scientist
Scope of research includes hydrogen material interactions and effects, hydrogen diffusion and trapping and stress corrosion cracking. Expert in thermal desorption mass spectroscopy. Framilar with mechanical testing, optical and scanning electron microscopy. Awarded a Ph.D. in Materials Science and Engieering in 2015 from the Institut National Polytechnique de Toulouse, France.