Structure Materials for Innovat - OECD Nuclear Energy Agency

Description

Table of contents......Page 7 Executive summary......Page 13 Opening Session......Page 18 Plenary Session I......Page 25 Summary of international design needs for advanced reactors......Page 27 Novel pathways for improving nuclear reactorstructural materials performance......Page 29 VHTR materials issues......Page 31 Environmental effects of nickel-based superalloys on mechanical properties for VHTR applications......Page 35 Optimisation of Ni-based Alloy 617......Page 41 Fracture toughness of two advanced structural alloys......Page 55 High-temperature fracture toughness of Inconel 617......Page 57 Oxidation behaviour of Alloy 617 during ageingat various temperatures......Page 59 Session II - Ceramics-composite......Page 61 Development of SiCf/SiC composite for innovative structural materials......Page 63 Irradiation-induced property change of C/C composite for application of control rod elements of very-high-temperature reactor (VHTR)......Page 71 Behaviour of irradiated boron carbide......Page 81 Study of heavy ions irradiation on structure of triple titanium nitride basis coating......Page 89 Diffusion of silver in zirconium carbide inside tristructural-isotropic nuclear fuel......Page 91 Session III - Metal − Materials Compatibility − Molten Salt and Sodium......Page 101 Alloys compatibility with selected molten salt environments for molten salt fast reactor breeders and burners......Page 103 Investigation on the compatibility of weldments of main component materials with sodium in the Chinese experimental fast breeder reactor (CEFR)......Page 123 Plenary Session II......Page 133 Innovative fuels state-of-the-art assessment......Page 135 Super ODS steels R&D for fuel cladding of advanced nuclear systems......Page 137 Session IV- Metal − Materials Compatibility − LFR Corrosion......Page 151 Corrosion of structural materials in nuclear systems involving liquid metals......Page 153 Effect of temperature and strain rate on the fracture toughness of T91 steel in lead-bismuth eutectic environment(......Page 155 Effect of welding on corrosion properties of ferritic-martensitic steels in liquid lead-bismuth......Page 157 Development of alumina forming ferritic steels for lead-bismuth eutectic-cooled applications......Page 167 Corrosion barrier development using electron beams for application in lead alloys with focus on recent creep to rupture tests(......Page 177 Development of aluminium powder alloy coating for innovative nuclear systems with lead-bismuth......Page 179 Session V - Fundamental − Radiation Effects......Page 191 ODS ferritic-martensitic alloys for sodium fast reactorfuel pin cladding......Page 193 Materials issues in cladding and duct reactor materials......Page 195 Radiation response of super ODS steels for fuel cladding of advanced nuclear systems......Page 197 Formation of dislocation loops at the onset of plasticity during single crystal nanoindentation(......Page 203 Session VI - General......Page 205 Developing advanced nuclear structural materials for use in high-radiation environments: An Australian perspective(......Page 207 Development of materials for nuclear fusion reactors: Summary of the 14th International Conference on Fusion Reactor Materials(......Page 209 Structural materials research in the Swedish GENIUS Project......Page 211 Plenary Session III......Page 213 Binding of impurities in austenitic iron: An ab initio study......Page 215 Fission-fusion cross-cutting issues related to structural materials......Page 225 Session VII - Novel Materials − Nano-structured Materials......Page 227 Structural control and high-temperature strength of 9 Cr ODS steels......Page 229 Development of cladding materials: Past and present experience......Page 239 Advances in the development of core and out-of-core structural materials for sodium-cooled fast reactors......Page 253 Session VIII- Fundamental Radiation Effects − Helium Effect......Page 263 Challenges of structural materials for applicationsin spallation targets of ADS(......Page 265 Hardening and microstructure of neutron- and ion-irradiated Fe-Cr alloys......Page 267 Microstructural evolution and void swelling in extra high purity Ni-based superalloy under multi-ion irradiation......Page 275 Effects of heat treatments on long-term creep properties of 9Cr-W-Mo-V-Nb steel......Page 283 Poster Session......Page 299 Session - Fundamental - Irradiation......Page 301 Session II - Metal Compatibility......Page 319 Session III - Ceramic......Page 345 Session IV Novel Materials Pathways......Page 367 Session V - General......Page 409 Annex 1: List of participants......Page 435