India - UK Civil Nuclear Collaboration: Development of Radiation Damage Resistant High Entropy Alloys for Advanced Nuclear Systems

Lead Research Organisation: University of Sheffield
Department Name: Materials Science and Engineering

Abstract

High entropy alloys (HEAs) are a novel and recently developed class of materials that do not contain one dominant element. Rather, four or more elements are combined together in equal or near equal measures with each element being randomly arranged. They have been reported to have a large number of desirable properties, including high strengths at high temperatures, good corrosion resistance and ability to withstand irradiation damage. These properties make HEAs strong candidate materials for use as structural materials in future nuclear fission and fusion reactors. These reactors are being designed to operate at higher temperatures, use less fuel and can be made safer and more efficient than current reactors.

For HEAs to be utilised in this highly harsh and demanding environment there are three key needs that must be addressed.

First, we must identify promising alloys, have them manufactured on a small scale, and characterise their mechanical behaviour and the stabilities of their microstructures. This will be carried out using advanced microscopes capable of studying the chemistry and structure of these alloys at the atomic level.

Second, the underlying materials physics of HEAs that provide the excellent resistance to irradiation damage need to be fully understood. To assess radiation damage resistance, we will perform ion implantations rather than using neutrons. This allows us to perform a large number of experiments and the samples are not radioactive so can be easily handled in a laboratory. The damage caused will be studied using mechanical testing methods capable of probing the small damage regions produced by these heavy ions. Results from experiments, combined with computational modelling of damage effects in these novel alloys, will allow us to describe radiation damage accumulation and recovery mechanisms in these materials, which can be used to design even more advanced alloys.

Finally, we must determine how well the materials will behave in service by assessing how they react when placed under load at high temperatures for long periods of time. We will work with Indian partners, utilising their unique facilities, to perform these tests on our most promising compositions. These compositions will be manufactured in large-scale quantities, tested, and returned to the UK for further study.

Planned Impact

The next generation of nuclear reactors (either Gen-IV fission or fusion) will be more efficient and considerably safer than the current generation of gas or water-cooled systems. Current designs are hampered by a lack of suitable materials to use in structural reactor components that experience high temperatures and neutron fluxes. Examples of such components include fuel claddings in fission reactors, or blankets in tokomak fusion reactors. Current generation materials such as zirconium alloys, which are widely used in fuel cladding for PWRs, cannot be used in advanced reactor systems, as the operational temperatures are too high. Whilst steels have been used in several test systems, and there continues to be development in this area, they suffer from swelling under irradiation and a significant deterioration of mechanical performance after irradiation. This is of a primary concern as the future reactors are designed to have longer lifetimes and are likely to have higher neutron fluxes (hence higher radiation damage levels in structural components). The so-called high entropy alloys (HEAs) are a relatively new and novel class of alloys where no single element dominates, as is the case in traditional metallic alloys. Instead four or more elements are used in near equal amounts. Preliminary work carried out by partners in this project has shown some HEAs are exceptionally resistant to the radiation damage which compromises conventional nuclear materials. This grant will accelerate the development of HEAs in the UK and India and assess their ability to act under the extreme environments envisaged for future reactors, studying both their properties after high levels of radiation damage and their creep behaviour at operational temperatures. By developing safer nuclear materials this grant will allow the deployment of more advanced nuclear power plants, in the UK and India, in an effort to reduce the emissions of greenhouse hence reducing the effect of climate change. This will have a positive impact on not just the collaborators countries, but also on the wellbeing of the global population.

HEAs are of interest to a wide range of end users across the nuclear, aerospace and automotive industries. In particular, the UK Atomic Energy Authority (UKAEA) and the Culham Centre For Fusion Energy (CCFE) are investigating them as potential structural materials in future nuclear fusion devices, and Rolls Royce plc are pursuing them for potential aero engine applications. Researchers in this project already have existing projects with these industrial partners and we will disseminate all key finding with them, by means of our regular meetings as well as larger public workshops. By doing so we will aim to find synergistic links across the nuclear and aero industries and accelerate the design of novel alloys in this developing area of research. We will work with the innovation arms of all three universities and our Indian partners, to maximise the use of any commercial aspects of our research.

Publications

10 25 50
 
Description By combining different computational modelling methods with alloy production, testing and characterisation, we have produced and investigated numerous new alloys, designed as candidates for use in the nuclear reactors of the future, specifically compositionally complex alloys (CCAs), including the so-called high entropy alloys (HEAs). We have demonstrated that density functional theory (DFT) can be used to accurately predict the crystal structures formed by some low-activation quaternary HEAs. We have shown that by adding Al to the low-activation VCrMnFe alloy we can supress the formation of the brittle intermetallic sigma-phase at high temperatures, demonstrating that control or suppression of the formation of these undesirable phases at reactor operating temperatures can be achieved through careful alloys composition design. We have also undertook preliminary assessments of how some of these novel alloys may behave in the high radiation and temperature environments of a Gen-IV fission or fusion reactor, with results from some of our alloys suggesting they display excellent radiation damage resistance. Results from this project has led to further grant and studentship funding in order to develop the alloys and methodologies further.
Exploitation Route The main outcomes can be used in the theoretical design and experimental development of novel alloys for a wide range of (not just nuclear) applications. The approaches reported in the papers linked to this funding will alloy for faster novel alloy development.
Sectors Aerospace, Defence and Marine,Energy,Environment

 
Description EPSRC Fusion Advisory Board
Geographic Reach National 
Policy Influence Type Participation in a guidance/advisory committee
 
Description UKAEA National Fusion Roadmap
Geographic Reach National 
Policy Influence Type Contribution to a national consultation/review
URL https://mrf.ukaea.uk/fusion-materials-roadmap-launched/
 
Description EPSRC Advanced Metallic Systems CDT studentship with UKAEA
Amount £135,436 (GBP)
Organisation UK Atomic Energy Authority 
Sector Public
Country United Kingdom
Start 09/2022 
End 09/2026
 
Description RAEng/The Leverhulme Trust Research Fellowships
Amount £54,598 (GBP)
Funding ID LTRF2021\17125 
Organisation Royal Academy of Engineering 
Sector Charity/Non Profit
Country United Kingdom
Start 09/2021 
End 08/2022
 
Title Supplementary information files for Design principles of low-activation high entropy alloys 
Description Supplementary files for article Design principles of low-activation high entropy alloys.The present study combines density functional theory (DFT) based calculations and experimental techniques to investigate the formation of equiatomic quaternary "low-activation" high entropy alloys (HEAs) for nuclear fission/fusion applications. DFT based techniques are adopted to screen the formation of possible single-phase ternary and quaternary alloys in chemical space consisting of the low-activation elements (Ti, V, Cr, Mn, Fe, Ta and W). The results indicate that TaTiVW and CrFeMnV can be formed in a single body centred cubic phase (BCC). Based on the DFT based screening, HEAs are fabricated by a vacuum arc melting process. Further characterisation by X-ray diffraction, energy dispersive X-Ray analysis, X-ray fluorescence and scanning electron microscopy confirms the formation of TaTiVW in a BCC single phase. Microstructures of CrTiVW and CrTaVW in as-cast conditions, consist of two BCC phases with very similar lattice parameters. CrTaTiW and CrTaTiV showed evidence of C15 Laves formation comprising of TaCr2 and TiV2, respectively. 
Type Of Material Database/Collection of data 
Year Produced 2022 
Provided To Others? Yes  
URL https://repository.lboro.ac.uk/articles/dataset/Supplementary_information_files_for_Design_principle...
 
Title Supplementary information files for Design principles of low-activation high entropy alloys 
Description Supplementary files for article Design principles of low-activation high entropy alloys.The present study combines density functional theory (DFT) based calculations and experimental techniques to investigate the formation of equiatomic quaternary "low-activation" high entropy alloys (HEAs) for nuclear fission/fusion applications. DFT based techniques are adopted to screen the formation of possible single-phase ternary and quaternary alloys in chemical space consisting of the low-activation elements (Ti, V, Cr, Mn, Fe, Ta and W). The results indicate that TaTiVW and CrFeMnV can be formed in a single body centred cubic phase (BCC). Based on the DFT based screening, HEAs are fabricated by a vacuum arc melting process. Further characterisation by X-ray diffraction, energy dispersive X-Ray analysis, X-ray fluorescence and scanning electron microscopy confirms the formation of TaTiVW in a BCC single phase. Microstructures of CrTiVW and CrTaVW in as-cast conditions, consist of two BCC phases with very similar lattice parameters. CrTaTiW and CrTaTiV showed evidence of C15 Laves formation comprising of TaCr2 and TiV2, respectively. 
Type Of Material Database/Collection of data 
Year Produced 2022 
Provided To Others? Yes  
URL https://repository.lboro.ac.uk/articles/dataset/Supplementary_information_files_for_Design_principle...
 
Description Bhabha Atomic Research Centre (BARC) 
Organisation Bhabbha Atomic Research Centre
Country India 
Sector Public 
PI Contribution One of the main objectives of this project is to form collaboration between researchers in the UK and in India, to develop new alloys to be used in the construction of advanced civil nuclear reactors. To date we have formed a good working collaboration between ourselves in the UK (universities of Sheffield, Manchester, Loughborough and Oxford), and researchers at Bhabha Atomic Research Centre (BARC), sharing ideas and information, including results from computational and experimental work undertaken in both the UK and India. This collaboration links with our collaboration with Indira Gandhi Centre for Atomic Research (IGCAR).
Collaborator Contribution Computational alloy design, production of phase diagrams, alloy production and characterisation.
Impact This project, and collaboration are ongoing. To date the outputs from our collaboration with BARC include international conference presentations.
Start Year 2018
 
Description Indira Gandhi Centre for Atomic Research (IGCAR) 
Organisation Indira Gandhi Centre for Atomic Research (IGCAR)
Country India 
Sector Academic/University 
PI Contribution One of the main objectives of this project is to form collaboration between researchers in the UK and in India, to develop new alloys to be used in the construction of advanced civil nuclear reactors. To date we have formed a good working collaboration between ourselves in the UK (universities of Sheffield, Manchester, Loughborough and Oxford), and researchers at Indira Gandhi Centre for Atomic Research (IGCAR), sharing ideas and information, including results from computational and experimental work undertaken in both the UK and India. This collaboration is linked to our collaboration with Bhabha Atomic Research Centre (BARC).
Collaborator Contribution The UK and Indian partners offer complimentary skills and expertise. Researchers at IGCAR have created alloy phase diagrams to predict phase changes in our produced alloys, as a function of temperature.
Impact This project, and collaboration are ongoing. To date the outputs from our collaboration with IGCAR include international conference presentations and a joint Indo-UK publication, currently in review, to the Journal of Alloys and Compounds.
Start Year 2018