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Annual Report

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Research<br />

CNE academics perform internationally-leading research in a number<br />

of fields. This section summarises our research in five theme<br />

areas: Fuel Design and Performance; Reactor Operation, Design<br />

and Monitoring; Spent Fuel and Waste Management; Repository<br />

Science and Engineering and Nuclear Policy, Safety, Security &<br />

Regulation.<br />

Fuel Design and Performance<br />

CNE research in the fuel area covers both<br />

performance and degradation mechanisms<br />

of current ceramic PWR fuels and<br />

metal cladding systems and development<br />

of accident tolerant fuels new fuel<br />

systems for Generation IV reactors.<br />

PDRA Projects<br />

MAX Phases for Accident-Tolerant Fuels<br />

Researcher: Dr Denis Horlait<br />

Supervisor: Prof Bill Lee<br />

Sponsor: EPSRC through XMat and CAFFE programme grants<br />

A loss-of-coolant accident (LOCA) leads to temperature<br />

building-up in the reactor core, leading<br />

to a chain reaction between steam and the<br />

Zr-based alloy constituting fuel cladding. This<br />

reaction between H2O and Zr produces massive<br />

amount of H2 and associated explosion risks.<br />

Recent Fukushima events for which this scenario<br />

happened had led to increase R&D efforts for<br />

the “Accident Tolerant Fuel” (ATF) concept. The<br />

ATF goal is to develop clad and fuels that can<br />

prevent or at least postpone such events.<br />

For cladding, some ternary layered carbides<br />

belonging to the “MAX phases” family display<br />

interesting characteristics, such as irradiation,<br />

thermal shock and high-temperature oxidation<br />

resistance (notably for the Al-based ones). One<br />

of these carbides could thus possibly be used<br />

as an external protective coating for the Zr cladding.<br />

The global aim of this project was thus to prospect<br />

for MAX phases materials for ATF. This was<br />

done by selecting promising composition then<br />

attempting to synthesize them and finally testing<br />

their oxidation resistance above 1200°C.<br />

The research focused on Zr2AlC and derived<br />

compositions, (Cr,Ti)n+1AlCn, and pre-oxidised<br />

Ti3SiC2. If the latter subject was a dead-end,<br />

the work on Zr2AlC derived compositions led to<br />

the synthesis of several new quaternary MAX<br />

phases, some even including new elements in<br />

the MAX phases family (Sb and Bi), while the<br />

research on the Cr-Ti-Al-C system evidenced the<br />

possible reinforcement of oxidation resistance<br />

of MAX phases by the deliberate addition of Al-<br />

Cr alloys.<br />

Centre for Nuclear Engineering <strong>Annual</strong> <strong>Report</strong> 2014-2016 32

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