Structure Materials for Innovat - OECD Nuclear Energy Agency

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