NuMat-2020-Masthead

NuMat2020: The Nuclear Materials Conference

Track Topics

Track 1A Metallic alloys

  • Steels for reactor pressure vessel and other structural components in NPP
  • Austenitic alloys including Ni-base; F/M alloys
  • Creep-strength enhanced F/M steels, ODS alloys incl. Ni-base ODS, alumina forming alloys (AFA)
  • High entropy alloys
  • Mechanical behaviour in nuclear environment: testing and modelling
  • Irradiation creep and swelling including relevant modelling
  • Environmental effects: corrosion, stress-corrosion cracking, dissolution, erosion, liquid metal embrittlement, relevant modelling
  • Microstructural and microchemical changes and evolution in nuclear environment: experimental characterization and modelling
  • Ion irradiation experiments and issues of transferability of results to neutron irradiation
  • Advanced manufacturing: powder metallurgy, spark plasma sintering, additive manufacturing, new welding techniques
  • Advanced methods for NDT, FIB-assisted microstructural/mechanical characterization
  • General materials technology aspects and cross cutting issues: Remelting, dilution, refabrication, considerations on raw materials abundance

Track 1B Refractory materials

  • Refractory materials for fusion reactor applications: tungsten and its alloys, vanadium alloys, SiC/SiCSiC and SiC/SiC, oxides,Max phases, W-based composites or Cu-Nb alloys
  • Refractory materials for fission reactor applications (AGR, VHTR): graphite, vanadium alloys, molybdenum alloys (incl. ODS), SiC/SiC
  • Prospective materials: Max phases, W-based composites, Cu-Nb alloys
  • Irradiation embrittlement, recrystallization, electrical/thermal conductivity, fatigue, phase separation/precipitation/segregation, swelling, oxidation and corrosion and relevant modeling
  • Advanced manufacturing: additive manufacturing, accelerated CVD/CVI, composites (fiber/laminar), 3D-printing, joining technology
  • Microstructural evolution in nuclear environment: characterization (In-situ and ex-situ TEM, atom probe) and integrated modeling
  • Accelerated Ion irradiation experiments and issues of transferability of results to neutron irradiation
  • Advanced methods for NDT, instrumented hardness tests, FIB-assisted microstructural/mechanical characterization
  • General materials technology aspects and cross cutting issues: Considerations on raw materials abundance, development of welding/joining technology, application of synchrotrons/neutron beams

Track 2A Cladding materials including coatings

  • Cladding and fuel assembly materials for fission reactors (GenIII, GenIV, MTR):
  • Currently deployed or near-term evolutions in Zr alloys, coated Zr alloys, stainless steel claddings
  • Long term evolutions: SiC/SiC, Fe-Cr-Al and Fe-Cr-Al ODS alloys incl. Mo ODS
  • Operational experience including laboratory and irradiation testing of cladding materials for fission reactors (GenIII, GenIV, MTR):
  • Corrosion, hydriding, fretting
  • Dimensional stability, physical and mechanical properties and property evolution
  • Microstructural evolution of materials: dislocation loops, void formation, point defects, radiation induced precipitation/dissolution, segregation of alloying elements, interfaces between substrate and coating
  • Cladding evolution under long term storage conditions
  • Innovative fabrication processes

Track 2B Fuel materials, absorbers and fuel cladding interaction

  • Fuel and absorber materials for fission reactors (GenIII, GenIV, MTR):
  • UO2, MOX, ThO2, UN, UC, TRISO, UMo, U-Zr, ATF concepts
  • Absorbers: Gd, Sm, B4C, AIC, including absorber materials used for shielding (fuel storage related)
  • Operational experience of fuel and absorber materials for fission reactors (GenIII, GenIV, MTR):
  • Dimensional stability, physical and chemical property evolution, high burnup effects, advanced techniques for fuel investigation
  • Fuel cladding interaction, spent fuel material evolution under long term storage conditions
  • Innovative fabrication processes
  • Fuel thermo-physical properties, Fuel mechanical properties, Thermodynamic properties modelling
  • Non-destructive PIE techniques, fuel online monitoring, NDT on spent fuel (stored in reactor pool)
  • General materials technology aspects and cross cutting issues: Fuel reprocessing, LOCA and severe accidents

Track 3A Cement

  • Development of cement-based matrix for waste encapsulation, special concrete for NPP’s
  • Innovative materials: Blended cementitious materials for nuclear related structures, application of non-Portland cements for waste encapsulation (e.g. calcium aluminate cements, phosphate cement)
  • Advanced materials: Geopolymers for waste immobilization: performance under extreme conditions (e.g. high temperature, high relative humidity, irradiation, aggressive environments)
  • Environmental effects: Internal swelling reactions (e.g. ASR, DEF) of concrete used in NPPs, corrosion of reinforced structures (e.g. carbonation, chloride attack), leaching experiments
  • Non-destructive testing, inspection and online monitoring (LTO)
  • General materials technology aspects and cross cutting issues: Molten core - concrete interaction

Track 3B Polymers

  • General properties of cable polymers – (EPDM, EPR), Composites - properties of interfaces, Advanced polymer characterization, End-of–life criteria
  • New cable polymers and advanced materials: Inorganic polymers as binder materials (cement, storage)
  • Degradation of materials exposed to a nuclear environment - cable ageing: microstructural evolution, physicochemical properties, the role of additives (antioxidants), multiscale modeling, End-of–life criteria
  • New manufacturing processes
  • General materials technology aspects and cross cutting issues: NDE, online  monitoring of ageing