Completed Materials & Manufacturing Clean Energy

Development of an in-situ characterisation facility for both proton and neutron irradiation

In plain English

AI plain-English summary

The University of Birmingham is building a suite of equipment that will test nuclear reactor materials while they are actively being bombarded with radiation. This matters because the UK currently has no way to test how reactor components corrode, crack, or weaken under the combined stress of heat, pressure, and ongoing irradiation—conditions that real reactors impose. Since the DIDO test reactors shut down, researchers have lacked a domestic neutron source for such work. The new facility will use Birmingham’s existing proton cyclotron and a developing neutron source to fill that gap. If successful, the facility will let engineers and scientists study stress corrosion cracking under conditions mimicking current pressurised water reactors, as well as next-generation designs such as super-critical water and molten salt reactors. It will also help evaluate new materials for fusion reactors being developed in UK universities. The equipment can operate with or without simultaneous irradiation, so it will remain in near-constant use. The practical outcome is safer, longer-lived nuclear power plants—critical for the UK’s clean energy strategy—and a stronger domestic research capacity that reduces reliance on overseas test facilities.

View original technical description
Nuclear research underpins the national energy strategy and plays a critical role in reducing the world's CO2 emissions. The currently world dominant nuclear reactor is the pressurised water-cooled reactors (PWR) which operates at high temperature and pressure using light water coolant, such as those at Sizewell B and Hinkley Point C in the UK. However, Generation IV reactors will have even higher operating temperatures and the Super-critical water-cooled reactor (SCWR) and molten salt reactor (MSR) are two of them. Both PWR and Generation IV reactors operate under extreme conditions such as high temperature, high stress and corrosive environments. Most importantly however, is the inevitable irradiation damage which the reactors must simultaneously endure. Therefore, to assess the reliability and lifetime of these reactors it is critical that the mechanical and corrosion performance of structural materials are conducted under relevant service conditions (e.g. under irradiation). Since the decommissioning of DIDO test reactors, there is no suitable neutron sources in the UK for materials irradiation and testing. The University of Birmingham has a high energy proton source (MC40 Cyclotron) and an accelerator-based intense neutron source under development. Building on the Birmingham irradiation facility, this proposal will develop a suite of world unique characterisation equipment for assessing the mechanical properties and corrosion resistance of nuclear materials under simultaneous irradiation, offering a range of important capabilities that currently do not exist. The proposed facility will enable the tackling of a range of scientific challenges. It will enable the industry and universities to study the stress corrosion cracking under both PWR, SCWR and MSR conditions, to evaluate the new nuclear (both nuclear fission and fusion) materials currently being developed in many UK universities. The novel capabilities will benefit the wide UK and international nuclear research community. The proposed facility can be operated with or without simultaneous irradiation, thus will have a high duty cycle and strengthen the UK nuclear material research capacity.

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Researchers

Alexander Knowles (Co-Investigator)Biao Cai (Co-Investigator)Carl Wheldon (Co-Investigator)David Collins (Co-Investigator)Martin Freer (Co-Investigator)Sergio Lozano-Perez (Co-Investigator)Yu-Lung Chiu (Principal Investigator)Yulong Ding (Co-Investigator)Zhenyu Zhang (Co-Investigator)

Related Research

Grants with similar aims, by meaning.

Development of a High Flux Accelerator-Driven Neutron Irradiation Facility for Nuclear Plant Materials and Applied Neutron Science
An Atomic-Scale Characterisation Facility for Active Nuclear Materials
Bridging the gap between small scale mechanical testing and bulk material property measurements of advanced, structural nuclear materials
Simultaneous Corrosion/Irradiation Testing in Lead and Lead-Bismuth Eutectic: The Radiation Decelerated Corrosion Hypothesis (RC-3)
Core UK Equipment Base for Characterisation and Analysis of Highly Radioactive Materials

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.