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Annual Report

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Atomistic Simulation of Dislocation Creep in<br />

UO2 Nuclear Fuel<br />

Researcher: Dr Paul Fossati<br />

Supervisor: Prof Robin Grimes<br />

Sponsors: EPSRC<br />

Understanding the behaviour of fission gas in<br />

nuclear fuel is critical to improving the simulation<br />

of fuel performance. Indeed, fission gases<br />

can be detrimental in different ways whether<br />

they accumulate in bubbles in the fuel or between<br />

the fuel pellets and the clad. This projects<br />

aims at simulating two aspects of the interaction<br />

between dislocations and fission gases,<br />

particularly xenon. The first one is the change<br />

in the mechanical behaviour of UO2 caused by<br />

individual xenon atoms or small bubbles slowing<br />

and pinning dislocations. The other facet<br />

is the enhanced mobility of xenon caused by<br />

the strain fields surrounding the dislocations<br />

cores, and its effect on long-range xenon diffusion.<br />

Both aspects are also of significant interest<br />

for the description of the formation of the<br />

high-burnup structure, which involves both dislocations<br />

piling up and gas bubbles but is not<br />

yet understood at the atomistic scale. This project<br />

is part of the Consortium for Advanced Simulation<br />

of Light Water Reactors (CASL), which is<br />

focused on fuel performance simulation.<br />

Fundamental Properties of Thoria Based Mixed<br />

Oxides<br />

Researcher: Dr Navaratnarajah Kuganathan<br />

Supervisor: Prof Robin Grimes<br />

Sponsors: EPSRC<br />

Thoria (ThO2) has attracted a great deal of interest<br />

as the next generation nuclear reactor fuel<br />

due to its higher abundance, higher thermal<br />

conductivity, higher chemical stability, higher<br />

melting temperature, higher corrosion resistance<br />

and lower thermal expansion compared<br />

to uranium based fuels. During operation in reactor,<br />

uranium, thorium and plutonium atoms<br />

undergo fission producing a variety of fission<br />

products such as Xe, Kr, Cs, Ba, Br and I. Fission<br />

product inert gases (Xe and Kr), produced during<br />

fission in nuclear fuels, are estimated to be<br />

15% of the total fission yield but are insoluble<br />

in the fuel matrix. These inert gases are initially<br />

accommodated at defect sites in the fuel lattice<br />

and are known to have a deleterious effect on<br />

fuel performance, particularly at high levels of<br />

burn-up.<br />

Using first-principles density functional theory<br />

(DFT), we calculate perfect lattice properties<br />

of ThO2, the energetics of defects and the interaction<br />

of Xe and Kr atoms and clusters with<br />

the defects. This project aims to calculate the<br />

structures of atoms and clusters of noble gases<br />

with defective ThO2 to provide soundly based<br />

models for the experimentalist to use in the<br />

interpretation of experimental data. Quantum<br />

mechanical calculations, in addition to giving<br />

structural information, have the added bonus<br />

of elucidating electronic structure and properties.<br />

Our simulation results are validated with<br />

experiments carried out by our collaborators at<br />

Bhabha Atomic Research Centre (BARC) in India.<br />

This projects is funded by EPSRC as part of<br />

the INDO-UK project.<br />

ZrC and MAX Phases for Future Fission<br />

Environments<br />

Researcher: Dr Eugenio Zapata-Solvas<br />

Supervisor: Prof Bill Lee<br />

Sponsors: EPSRC CAFFE Consortium<br />

The aim of this project is to develop new Zrbased<br />

carbides, including Zr-based MAX phases,<br />

for coating Zr-alloys cladding, providing<br />

accident tolerance in fission reactors of future<br />

nuclear power plants. Powders are synthesised<br />

and densified by hot press and spark plasma<br />

33 http://www.imperial.ac.uk/nuclear-engineering

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