Oxford University Materials 2005 Fusion materials Fission materials
Materials for Fusion and Fission Power 2013 Fusion materials Fission materials CCFE
Materials for Fission & Fusion Power Steve Roberts Sergei Dudarev CCFE Felix Hofmann Gordon Tatlock Liverpool Sergio Lozano- Perez Michael Moody James Marrow Angus Wilkinson Patrick Grant Andrew Jones Liverpool Steve Donnelly Huddersfield Paul Bagot Chris Grovenor Steve Fitzgerald EPSRC: 2009-2015, 5.8M
Materials for Fission & Fusion Power
Research Student Numbers Total Nuclear Materials MFFP
Publications & Conferences Journal Papers Conference Attendances Invited Talks Contrib. Talks 2009-10 24 55 28 21 2011 29 56 23 25 2012 31 69 17 39 2013 45 98 23 59 2014 68 76 22 40
MFFP workshops and courses Nuclear materials Micromechanics Ion implantation ODS alloys Radiation damage modelling Tungsten Zirconium
National Nuclear User Facility 15M NNUF initial capital spend (2013) 60M NNUF additional funding in 2014 Autumn Statement
Active Materials Library Magnox surveillance specimens EFDA / CEA (Phénix) Steels, SiC, Ni alloys EXTREMAT (Petten) W, SiC, Graphite, ODS steels NEUP / IRP (BOR-60) ODS steels, FeCr, Ni alloys STFC (ISIS) W targets RaDIATE (CERN,FermiLab) Be targets & windows UCSB / ANL (INL ATR) ODS steels, FeCr
CCFE Materials Research Facility Opens October 2015
MFFP: Hot topics ODS alloy bulk processing Small-scale <-> large scale mechanics Alloy stability under irradiation Temperature stability of radiation damage Helium and radiation damage Neutrons Ions Protons Crack chemistry and fracture Zirconium: Hydrides Oxide layers Coatings SiC Composites and Reaction-Bonded High-entropy and Nano-structured alloys
Active Material: Fe-6%Cr N-irradiated to 1.7 dpa at 288 C, dose rate ~1 x 10-7 dpa/s 1mm 0.1mm Activity: 37MBq 66 cantilever beams with depths from 0.82 to 7.3μm Also made in un-irradiated Fe-6%Cr FIB work at CAES, Idaho
Micromechanical testing Fe-6%Cr yield stress Yield Stress (GPa) 6 0.1mm 5 4 Neutronirradiated 3 2 1 0 Unirradiated 0 1 2 3 4 5 6 7 8 Beam Depth (mm)
Testing an oxidised Ni-600 grain boundary Sample of Ni600 autoclaved for 2700hrs at 360 o C in simulated primary coolant water Surface and grain boundary oxidation Microcantilevers manufactured on g.b. (with adjacent TEM foil)
Zirconium Aidan Robinson 2013 Kr bubble lattice in Zr 12nA, 12 kev Room temperature Micromechanical testing of zirconium hydride Howard Chan 2013
Micro-mechanical Testing: Tungsten 20mm 1mm Unimplanted W Implanted W&He Implanted Yield Stress (GPa) 2.0±0.9 (4 Cantilevers) 3.1±0.7 (4 Cantilevers) 3.1±0.7 (7 Cantilevers) Fracture Toughness (MPa m) >29±12 (0/2 Cantilevers) >15±3 (0/4 Cantilevers) 17 (1/7 Cantilevers)
Micro-mechanical Testing: Temperature Si: 500 C Si: 700 C -100 C +750 C World-unique
Oxide-Dispersion-Strengthened Alloy Processing Mechanical Alloying in Planetary Ball mill Metallic powders: Fe, Cr, and Ti. + Y 2 O 3 powder Insoluble oxide dissolves in Steel Hot-press or Hot Isostatic Press Hot-pressed 1100 C, 50MPa, 3hr Oxide Re-precipitates in Steel
electrons ions
Oxide Dispersion - Strengthened alloys: radiation resistance No irradiation 0.5 dpa 1 dpa 2 dpa Particles stable, and no radiation damage was visible below 1 dpa ODS PM2000, RT irradiated with 150 kev Fe+, room temperature
Developments and Future projects Innovative Accident-Tolerant Fuel Cladding (DoE / EPSRC) FUNDED Ion Irradiation Simulation of Neutron Damage (DoE / EPSRC) RaDIATE damage in high-energy accelerators (Fermilab/STFC/PNNL) MUZIC2 zirconium (BIS) Radiation Damage in Perovskites (EPSRC) HEXMAT Ti & Zr (EPSRC) Micro-Engineering Advanced Alloys for Nuclear Power (RAEng) Bristol-Oxford Nuclear Research Centre Platform grant : neutron- irradiated materials (EPSRC) Ion Irradiations for Nuclear Materials (EPSRC) Irradiated SiC-SiC composites (DoE/EPSRC) Localized strain mapping and mechanical properties (DoE/EPSRC) Radiation tolerance by surface modification (EPSRC) Center for the Stability of Radiation Resistant Nanostructures (DoE) TRITON: triple-beam ion radiation facility (NNUF?) FETS-HIPSTER: High-Current Proton Irradiation Source (NNUF?) Microstructure Effects on SiC Ceramic Matrix Composites (EPSRC) Graphite for Advanced Nuclear Fission (EPSRC) PENDING
Mechanics Modelling Microanalysis Microscopy
Load 5mm Mechanics Focussed Ion Beam Machining Modelling Microanalysis Microscopy 10mm
Mechanics Oxidised Ni-600 grain boundaries Modelling Microanalysis Microscopy Zirconium oxide zirconium