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Generation IV Reactor Safety and Material Research by the Institute for Energy and Transport at the European Commission’s Joint Research Centre

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The Institute for Energy and Transport (IET) is one of the seven scientific institutes of the Joint Research Centre of the European Commission. Its mission is to provide support to definition, implementation, and monitoring of European Union policies related to both nuclear and non-nuclear energy, and to transport. The IET is based both in Petten, the Netherlands, and Ispra, Italy, and has a multidisciplinary team of around 300 academic, technical, and support staff. The research areas include, among others, sustainable transport, renewable energies incl. solar, photovoltaics and biomass, sustainable & safe nuclear energy for present & future reactor system, pre-normative materials testing, energy techno-economic assessment, hydrogen and fuel cells, energy efficiency, and security of energy supply. To support implementation of the European Strategic Energy Technology Plan (SET-plan) and the Industrial Initiatives of the Sustainable Nuclear Energy Technology Platform (ESNII and NC2I, under construction) the IET works on performance assessment, design optimization, and safety evaluation of various next generation nuclear fission (Generation IV) energy systems. In collaboration with the Generation IV International Forum (GIF) and with European Technical Support Organizations, IET participates in development of an integrated safety assessment methodology for Generation-IV reactor systems aiming at establishment of a widely applicable, technology-neutral concept. Mostly as part of European collaborative projects, IET is also engaged in safety-relevant experimental research on advanced fuels, components and materials, in simulation as well as modelling to support experimental research and to assess performance of Generation-IV systems. This includes irradiation testing of fuels for fast reactors and high temperature reactors, of transmutation fuels and candidate structural materials for several advanced reactor concepts. Out-of-pile testing and qualification methods in corrosive environments up to very high temperatures are also being developed and applied. This work contributes to several European collaborative projects, to certain GIF projects, to the Joint Research Program on Nuclear Materials of the European Energy Research Alliance, and to related IAEA and OECD/NEA activities.
2013-03-21
IAEA
JRC67276
https://publications.jrc.ec.europa.eu/repository/handle/JRC67276,   
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