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

Abstract To support the drafting, development, implementation and monitoring of European energy and transport policy, the Institute for Energy and Transport of the European Commissions’ Joint Research Centre conducts pre-competitive research in the areas of experimental qualification of advanced fuels and materials as well as simulation and modelling of reactor safety and material performance. The work covers assessments, design optimisation and improvements to the safety and performance of new, innovative reactor systems, materials and instrumentation, in order to meet the EU's long-term energy needs while respecting enhanced safety, sustainability, and economic aspects. The research is linked, and contributes, to related EURATOM Framework Programme projects, Generation IV International Forum (GIF), International Atomic Energy Agency as well as OECD's Nuclear Energy Agency (OECD NEA) activities. The current paper gives an overview and examples of past, current, and upcoming activities in the areas of reactor safety assessments, advanced fuel irradiation and materials research.

[1]  H. H. Over,et al.  MatDB Online analysis of HTR materials data from European R&D , 2012 .

[2]  Elena Paffumi,et al.  Experimental and numerical assessment of thermal fatigue in 316 austenitic steel pipes , 2015 .

[3]  Elena Paffumi,et al.  Experimental and numerical assessment of thermal fatigue in 316 austenitic steels , 2013 .

[4]  T. Ozawa,et al.  FUJI: A Comparative Irradiation Test with Pellet, Sphere-Pac, and Vipac Fuels , 2006 .

[5]  Benjamin Klusemann,et al.  Plastic deformation induced microstructure evolution through gradient enhanced crystal plasticity based on a non-convex Helmholtz energy , 2013 .

[6]  M. Laurie,et al.  On-line fission gas release monitoring system in the High Flux Reactor petten , 2013, 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA).

[7]  M. A. Fütterer,et al.  Next generation fuel irradiation capability in the High Flux Reactor Petten , 2009 .

[8]  R. Morice,et al.  New temperature monitoring devices for high-temperature irradiation experiments in the High Flux Reactor Petten , 2009, 2009 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications.

[9]  Fuetterer Michael,et al.  JRC-IE's Research on Gen IV Systems , 2010 .

[10]  D. Struwe,et al.  European lead fast reactor—ELSY , 2011 .

[11]  G. L. Fiorini,et al.  European Commission – 7th Framework Programme: The Collaborative Project on European Sodium Fast Reactor (CP ESFR) , 2011 .

[12]  Schwarz Wolfgang,et al.  Scientific Assessment in Support of the Materials Roadmap Enabling Low Carbon Energy Technologies: Bioenergy , 2011 .

[13]  Peter Hähner,et al.  Anisotropic Mechanical Properties of the MA956 ODS Steel Characterized by the Small Punch Testing Technique , 2012 .

[14]  F. Delage,et al.  The Results of the Irradiation Experiment HELIOS , 2011 .

[15]  Peter Hähner,et al.  NDT Study of Oxide Dispersion Strengthened Steels , 2011 .

[16]  A. Jankowiak,et al.  MARIOS - Irradiation of UO2 Containing 15% Americium at well defined Temperature , 2012 .

[17]  Haileyesus Tsige-Tamirat,et al.  Coupled Neutronics Thermal-Hydraulics Analysis using Monte Carlo and Sub-channel Codes , 2012 .