Completed Materials & Manufacturing Clean Energy

MIDAS - Mechanistic understanding of Irradiation Damage in fuel Assemblies

In plain English

AI plain-English summary

Nuclear fuel assemblies are being pulled from reactors years before the fuel is spent, because engineers do not know enough about how the cladding material—zirconium—degrades under radiation. This project aims to close that knowledge gap. Currently, reactor operators must adopt a highly cautious approach, replacing fuel assemblies prematurely to guarantee safety. That drives up operating costs and creates extra nuclear waste that must be handled and stored at great expense. The problem is urgent for the UK because the country is shifting from ageing advanced gas-cooled reactors to a new fleet of light-water reactors, which use zirconium as the primary cladding material—a fundamental change from past practice. If the research succeeds, it will produce the data needed to build more accurate safety cases for longer fuel assembly lifetimes. That would allow reactors to run more efficiently, cutting the cost of nuclear power and reducing the volume of radioactive waste. The work also explores whether zirconium alloys could serve in critical components for future fusion reactors, helping the UK maintain its leading role in international fusion projects like ITER and DEMO.

View original technical description
In order to meet the UK's carbon reduction targets, and achieve an energy mix that produces less CO2, we must continue to investigate ways in which to make nuclear power cleaner, cheaper and safer. At the same time, as new reactors such as Hinkley Point C are built, the UK needs to develop the work force who will operate, regulate and solve technical problems in civil nuclear power, in order to capitalise on our investment in nuclear energy. Important in this respect is that the UK currently operates mainly old advanced gas-cooled reactors, fundamentally different from the next fleet of UK nuclear power stations, which will be light-water reactors. Key to this change, in terms of this research project, is that Zirconium is a preferred fuel cladding material in LWRs. A major part of a nuclear reactor is the fuel assembly - the structure that encapsulates the highly radioactive nuclear fuel. Understanding the performance of the materials used to make these assemblies is critical for safe, efficient operation, and they must be able to maintain their structure during normal operation, handling and storage, as well as survive in the unlikely event of an accident, when they become crucial in preventing the escape of radioactive materials. Because of the need to operate nuclear reactors as safely as possible, fuel is often removed well before it is spent, as we currently do not know enough about fuel assembly materials, so must adopt a highly cautious, safety-first approach. This does mean, however, that it is more costly to run a reactor, as assemblies must be replaced well before all the fuel is consumed, and this also means the assembly then - prematurely - becomes additional nuclear waste, which must be safely handed and stored, at further high cost. By gaining greater understanding of how assembly materials perform when irradiated, we will be able to make more accurate safety cases, which will mean that fuel assemblies can be used for longer periods without additional risk. Such knowledge will enable the UK to operate the next generation of reactors far more efficiently, significantly reducing the cost of nuclear power. This is particularly important now, given that the UK is going to have light-water, instead of advanced gas-cooled, reactors, and with it the fuel assembly and its material will change very fundamentally. This research effort will also significantly benefit other countries using nuclear energy, which will establish the UK as a centre of expertise in the area. This will further attract inward investment in research and development in the UK, creating future wealth and employment alongside cleaner energy. A second key theme of the project will be to explore the use of zirconium alloys in critical components for future fusion reactors. The UK has a leading position in defining the materials that will be chosen for the ITER and DEMO international fusion projects, and this theme will contribute to maintaining the UK's reputation as a centre of excellence in fusion research.

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Researchers

Angus Wilkinson (Co-Investigator)Chris Grovenor (Co-Investigator)Christopher Race (Co-Investigator)Daniel Balint (Co-Investigator)Edmund Tarleton (Co-Investigator)Fionn Dunne (Co-Investigator)Joseph Robson (Co-Investigator)Katie Moore (Co-Investigator)Mark Wenman (Co-Investigator)Mia Maric (Co-Investigator)Michael Moody (Co-Investigator)Michael Preuss (Principal Investigator)Philipp Frankel (Principal Investigator)Robert Harrison (Co-Investigator)Sergei Dudarev (Co-Investigator)Thomas Britton (Co-Investigator)

Related Research

Grants with similar aims, by meaning.

New Fuel Assemblies for Advanced Nuclear Technologies
From Processing to Simulated In-Reactor Performance of Zr Cladding.
Enhancing nuclear fuel efficiency through improved understanding of irradiation damage in zirconium cladding
Reducing risk through uncertainty quantification for past, present and future generations of nuclear power plants
High Temperature Zirconium Alloys for Nuclear Fusion and Generation IV Fission Reactors

Original classification

Research Grant

Plain English summaries and category classifications on this site are generated by AI and may not perfectly reflect the original research.