Oxford University Materials 2005

Transcription

1 Oxford University Materials 2005 Fusion materials Fission materials

2 Materials for Fusion and Fission Power 2013 Fusion materials Fission materials CCFE

3 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: , 5.8M

4 Materials for Fission & Fusion Power

5 Research Student Numbers Total Nuclear Materials MFFP

6 Publications & Conferences Journal Papers Conference Attendances Invited Talks Contrib. Talks

7 MFFP workshops and courses Nuclear materials Micromechanics Ion implantation ODS alloys Radiation damage modelling Tungsten Zirconium

8

9 National Nuclear User Facility 15M NNUF initial capital spend (2013) 60M NNUF additional funding in 2014 Autumn Statement

10 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

11 CCFE Materials Research Facility Opens October 2015

12 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

13 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

14 Micromechanical testing Fe-6%Cr yield stress Yield Stress (GPa) 6 0.1mm 5 4 Neutronirradiated Unirradiated Beam Depth (mm)

15 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)

16 Zirconium Aidan Robinson 2013 Kr bubble lattice in Zr 12nA, 12 kev Room temperature Micromechanical testing of zirconium hydride Howard Chan 2013

17 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)

18 Micro-mechanical Testing: Temperature Si: 500 C Si: 700 C -100 C +750 C World-unique

19 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

20 electrons ions

21 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

22 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

23 Mechanics Modelling Microanalysis Microscopy

24 Load 5mm Mechanics Focussed Ion Beam Machining Modelling Microanalysis Microscopy 10mm

25 Mechanics Oxidised Ni-600 grain boundaries Modelling Microanalysis Microscopy Zirconium oxide zirconium