Nuclear Science Structural Materials for Innovative Nuclear Systems (SMINS)

Description

Structural materials research is a field of growing relevance in the nuclear sector, especially for the different innovative reactor systems being developed within the Generation IV International Forum (GIF), for critical and subcritical transmutation systems, and of interest to the Global Nuclear Energy Partnership (GNEP). Under the auspices of the NEA Nuclear Science Committee (NSC) the Workshop on Structural Materials for Innovative Nuclear Systems (SMINS) was organised in collaboration with the Forschungszentrum Karlsruhe in Germany. The objectives of the workshop were to exchange informat.  Read more... Foreword CONTENTS Executive summary OVERVIEW EURATOM RDDD in Innovative Reactor Systems and Fuel Cycles SESSION I KEYNOTE LECTURES Innovative Reactor Systems and Requirements for Structural Materials Ageing Management and Knowledge Base for Safe Long-termOperation of Japanese Light Water Reactors Modelling, Microstructures, Radiation Damage and Understandingof Irradiation Data SESSION II GAS-COOLED SYSTEMS Material Research for VHTR Design Codes Evaluation of Nickel-based Materials for VHTR Heat Exchanger An Uncertainty Assessment Methodology for Materials Behaviourin Advanced Fast ReactorsSESSION III LIQUID-METAL-COOLED SYSTEMS High-Cr ODS Steels R&D for High Burn-up Fuel Cladding Influence of Normalising Temperature on MX PrecipitationBehaviour in High-chromium Steel Development of ODS Ferritic-martensitic Steels for InnovativeNuclear Fast Breeder Reactors Void Swelling and Defect Processes in Ti-modified SteelsUsing Accelerator Irradiation First Results on T91 Claddings with and Without Modified FeCrAlY CoatingsExposed in PbBi Under Varying Conditions SESSION IV FUSION, HIGH-POWER ACCELERATOR TARGETSAND OTHER FISSION REACTOR SYSTEMSAssessing SCC and IASCC of Austenitic Alloys for Applicationto the SCWR Concept Oxidation and Stress Corrosion Cracking of Stainless Steels in SCWRs Microstructural Influence on the Corrosion Behaviour ofStructural Materials for Nuclear Power Systems Influence of Stacking Fault Energy (SFE) on the Deformation Modeof Stainless Steels Evolution of Structural Materials in Nuclear Reactors SESSION V FUNDAMENTAL RESEARCH Qualification of Structural Materials for Reactor Systems: Synergies inMaterials for Fusion/Fission Reactors and Advanced Fission ReactorsUnderstanding Radiation Damage in FECR Alloys A New Computational Method for Studies of 3-D Dislocation-precipitate Interactions in Reactor Steels On the Theoretical Development of New Creep Resistant Alloys andTheir Empirical Validation Modelling of Nuclear-grade Graphite Using X-ray Tomography Data Basic Experiments for Understanding Microstructure Evolution UnderIrradiation: TEM and KMC Characterisation of Irradiated Pure Iron Combined TEM, PAS and SANS Investigation of Neutron-irradiatedPure IronSynchrotron Light Techniques for the Investigation of AdvancedNuclear Reactor Structural Materials First-principles Modelling of Advanced Nuclear Fuels: Problemsand Prospects POSTER SESSIONS High Temperature Corrosion Properties of Alloy 230 in theEnvironment of Gas-cooled Reactors Materials Modelling -- A Possible Design Tool for AdvancedNuclear Applications Characterisation of Oxidation and Oxide Layers of Nickel-baseSuperalloys at High Temperature