Intermediate range order effects in radioactive waste glasses: implications for aqueous durability and mechanical properties

Lead Research Organisation: University of Liverpool
Department Name: Mech, Materials & Aerospace Engineering

Abstract

Radioactive waste occurs as a wide variety of radioactive elements that must be immobilised in a matrix of glass or ceramic or a composite, before disposal in a geological repository. This matrix, commonly known as the waste form, must be able to accommodate the wide range of species present in the waste and be resistant to leaching and mechanical fracture for the lifetime of radioactive species, typically 10,000 years or more. Glass, having an amorphous structure, is able to accommodate a wide range of radioactive waste species. In addition, glass fabrication technology is well established to produce these waste forms at large scale and this has been carried out for some years in both the UK and India, among several other countries.
The proposed project aims to understand the phase stability, thermal and radiation effects in radioactive waste glasses, in light of atomic scale structural changes due to radiation effects. These modifications will then be correlated with glass dissolution and mechanical properties such as cracking/fracture. The glasses selected are critical to the radioactive waste management programs in the UK and India, thus complementing methods and scientific expertise to realise clean, safe and economical energy from nuclear technology whilst presenting the most robust safety case for waste disposal. Our specific aims will be to: (1) understand the phase stability of glasses as a function of different divalent cations and addition of waste species; (2) define 'radiation damage' in an already amorphous/disordered material system and predict how radiation-induced modifications will affect dissolution properties over long timescales; and (3) understand the evolution of glass structure and properties under a temperature gradient and after undergoing annealing treatments.
In order that radioactive waste should no longer be deemed as an 'issue' rather than a practice that can be trusted by public opinion, the methods and materials employed to immobilise radioactive waste must be fundamentally understood and scientifically verified. This project aims at improving this confidence. Our detailed User Engagement Strategy will ensure that groups from the public and members of communities that may be involved in selection of a geological disposal facility, as well as the nuclear industry and supply chain, government and civil servants, and a wide range of academics, will be engaged throughout and beyond this project to deliver maximum impact from our proposed research.

Planned Impact

Radioactive waste is a problem affecting future generations. Hence, radioactive waste management is of primary concern for successful implementation of next generation nuclear technologies and safe clean-up and decommissioning of nuclear facilities. Radioactive waste destined for geological disposal must be immobilized in a waste-form. The primary requirements for qualifying any waste-form are high waste loading (the amount of waste immobilized as a proportion of waste form volume), and superior long-term durability under radiation and corrosion conditions. The results obtained from this project will improve our understanding of phase stability and durability of waste-forms, thus helping the design of new waste-forms with enhanced waste loading whilst providing the required properties. Unlike metals and, to some extent, simple crystalline ceramics, radiation effects in complex glasses is still an area which requires much research in order to more fully understand - and therefore be able to accurately predict - its effects. Thus, the novel approach taken in this project will actively fill critical gaps in our understanding of radiation effects in glasses. The research in this project is therefore of great national importance to both the UK and India since they share common challenges in radioactive waste management.
Our User Engagement Strategy will ensure that each of the following UK and international groups will be engaged and gain impact from the proposed research: (i) the nuclear industry, government and policymakers; (ii) academic researchers (see also 'Academic Beneficiaries' section of JeS form); and (iii) the public and society. This will be achieved through multiple mechanisms, detailed in the Pathways to Impact.
(i) Several industrial, governmental and policy organisations will directly benefit from the project outputs, creating impact in many areas including: enhanced safety case for geological disposal of radioactive waste forms, support for delivery of UK Industrial Strategy and Nuclear Sector Deal, improved understanding of waste form behaviour, and greater knowledge of alternative glass formulations and processes. The organisations benefiting from the impact of this work include some of the largest and most important in the UK nuclear sector (NDA, Sellafield Ltd, NNL, RWM, BEIS, and members of the supply chain).
(ii) Impact for UK, Indian and international academic researchers from the proposed research will be achieved through enhanced mechanistic understanding of the effects of radiation on (a) radioactive waste forms (nuclear researchers); and (b) glasses (glass scientists); and through improved, validated molecular dynamics and atomistic simulations of glasses and amorphous materials. Further impact will be delivered through exchange and training programmes for Early Career Researchers, in training the next generation of nuclear experts. Finally, additional impact will arise in the UK through transfer of knowledge in alternative waste form host materials and processing technologies from India, providing improved understanding of these factors in the UK; and impact in India through transfer of UK expertise in advanced synchrotron and neutron techniques and computer simulations of highly complex disordered materials.
(iii) Impact for the public and society will be achieved through activities aimed at communicating our research to a wide section of the public via multiple channels (events, social media, popular press and online). The UK Nuclear Sector Deal of the Industrial Strategy highlights the need to improve public confidence to accelerate implementation of geological disposal of radioactive waste forms. Our impact and user engagement activities will contribute towards meeting this national strategic need, and our public engagement will thus focus on how our research will be used to help assess risks, to a local community that may host the geological disposal facility.

Publications

10 25 50
 
Description GREEN CDT-PhD project "Assessing stored energy due to radiation effects in UK's nuclear waste forms "
Amount £55,000 (GBP)
Organisation National Nuclear Laboratory 
Sector Public
Country United Kingdom
Start 10/2020 
End 10/2024
 
Description Collaboration with Huddersfield University Nuclear Materials Group 
Organisation University of Huddersfield
Country United Kingdom 
Sector Academic/University 
PI Contribution Contact and discussions with Huddersfield Nuclear Materials group, directly enabled by this project. Discussions are at an early stage but reciprocal visits and discussions underway and future funding bids in consideration.
Collaborator Contribution Contact and discussions with Huddersfield Nuclear Materials group, directly enabled by this project. Discussions are at an early stage but reciprocal visits and discussions underway and future funding bids in consideration.
Impact Too early - no outcomes yet as collaboration has just begun.
Start Year 2023
 
Description Ion irradiation studies with Centre for Micro Analysis of Materials-Spain (CMAM) 
Organisation Autonomous University of Madrid
Country Spain 
Sector Academic/University 
PI Contribution Our research team at Univ. Liverpool lead the conceptualization of the scientific objectives for the beamtime through the submission of a beamtime proposal to Centre for Micro Analysis of Materials (CMAM). The objective is to simulate radiation damage by recoils of alpha decay using heavy ions and to correlate the changes in density to diffusion and local structure changes in CaZn and MW glasses. Glass compositions simulating full nuclear waste compositions but with fewer cations were discussed and fabricated at Sheffield Hallam Univ. (Prof. Bingham and Dr. Scrimshire (PDRA). These glasses were cut and polished at Univ. Liverpool and sent for irradiations to CMAM. The glasses are now being characterised using Raman and IR microscopy at the University of Liverpool
Collaborator Contribution Collaborators at CMAM ( M. L. Crespillo, P. Sanchez-Morillas, J. Sanchez-Prieto, J. Olivares, O. Peña-Rodríguez) have performed 8 MeV Au irradiations on 8 different glasses and characterised them using (1) profilometry to quantify swelling/densification (2) optical absorption spectroscopy to study defect centres and (2) several ion beam analysis i.e. Rutherford Back Scattering (RBS) , Proton Induced X-ray Emission (PIXE) and Nuclear Reaction Analysis (NRA) to study diffusion of heavy and light elements upon irradiation. They are currently performing analysis of the data obtained.
Impact One conference paper has been accepted at the International Conference on Physics of Non-Crystalline Solids (PNCS16). Radiation induced diffusion in UK-nuclear waste glasses P. Sanchez-Morillas, Aine Black, J. Sanchez-Prieto, Alex Scrimshire, M. L. Crespillo, J. Olivares, O. Peña-Rodríguez, Paul Bingham & Maulik Patel
Start Year 2021
 
Description Oral presentation at BRSG NMR Christmas meeting, 15th December 2022, online: Understanding Complex Nuclear Waste Glass Structures from NMR 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach National
Primary Audience Professional Practitioners
Results and Impact The audience comprised of a wider national community of experts that use nuclear magnetic resonance (NMR) for understanding how chemistry tailors the structure of materials. In this case they were able to appreciate the using of NMR for understading the efect of Lithium on the Network Connectivity in UK's Nuclear Waste Glasses. This helps how durability of glasses is dependent on glass structure and the chemistry. These studies provide the scientific basis for using glasses for immobilisation of nuclear waste.
Year(s) Of Engagement Activity 2022
 
Description Oral presentation at Condensed Matter Division conference (CMD29), 22nd-26th August 2022, Manchester (UK): New pair distribution function analysis of International Simple Glass (ISG) from neutron and X-ray diffraction. 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Other audiences
Results and Impact The audience comprised of a wider international community of glass experts could appreciate how complex glass structure can be characterised by combined use of synchrotron based x-ray scattering and neutron scattering. Glasses used in this study being multi component (more than 6-7 elements) are by far the most complex ones that have been setudeied using pair distribution analysis (pdf). These studies provide the scientific basis for using glasses for immobilisation of nuclear waste.

Multicomponent borosilicate base glass is used to vitrify high level radioactive waste. To ensure the glass is able to contain all radioactive elements until radiation has decayed to safe levels, an understanding of glass structure is necessary to model long term glass performance in a geological disposal facility. A range of base and simulant glasses are used to study glass behaviour, preventing direct comparison between many different studies. To enable standardised glass leaching studies an aluminoborosilicate glass formulation known as ISG (mol%: 60.2 SiO2, 16.0 B2O3, 12.6 Na2O, 3.8 Al2O3,5.7 CaO, 1.7 ZrO2) has been created. The structure of ISG has previously been studied though atomistic modeling with the aid of Pair Distribution Function (PDF) data, but a direct fit of X-ray and Neutron PDF data for ISG has never previously been reported. Here for the first time structural data has been extracted by directly fitting high Qmax PDF data collected using an 11B isotopically enriched ISG sample using simultaneous fitting of X-ray and Neutron PDF aided by solid state 27Al and 11B NMR.
Year(s) Of Engagement Activity 2022
 
Description Oral presentation at Condensed Matter Division conference (CMD29), 22nd-26th August 2022, Manchester (UK): The Effect of Lithium Concentration on the Network Connectivity in Pristine UK Nuclear Waste Glasses 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Other audiences
Results and Impact The audience comprised of a wider international community of condensed matter physicists who were interested in how disorder can be used as a functionality in materials to immobilise nuclear waste. Hence they were able to appreciate the importance of glass in the nuclear technology and nuclear waste management. They could also appreciate Effect of Lithium on the Network Connectivity in UK's Nuclear Waste Glasses. This helps how durability of glasses is dependent on glass structure and the chemistry. These studies provide the scientific basis for using glasses for immobilisation of nuclear waste.
Year(s) Of Engagement Activity 2022
 
Description Oral presentation at Physics of Non-Crystalline Solids conference, 11th-15th July 2022, Canterbury, University of Kent (UK): Effect of glass chemistry on alpha recoil damage and induced diffusion effects 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Other audiences
Results and Impact The audience comprised of experts from UK's glass community so they were able to appreciate the importance of glass in the nuclear technology and nuclear waste management. They could also appreciate how to long term damage (1000+ years) processed are accelerated by novel experimental tools in a day that then helps in prediction of glass evolution. These studies provide the scientific basis for using glasses for immobilisation of nuclear waste.

Borosilicate glasses are the most common choices for nuclear waste glass due to their low processing temperature and ability to create a durable product capable of incorporating a vast range of radionuclides. The nuclear waste glass compositions used in the UK are Calcium Zinc (CaZn) and Mixed Windscale (MW) glasses. Nuclear waste glasses are designed to retain radionuclides for thousands of years, yet over time, the radiation produced by the high-level waste will interact with the structure of the glass causing defects in the glass network. These defects may lead to enhanced diffusion of glass species and those comprised of radioactive waste. The present work discussed the diffusionof Li and other species due to damage caused by recoils during alpha-decay of minor actinides. The recoil atoms are low energy heavy ions causing displacement of atoms within the glass matrix. Here, we discussed the effect of Li as well the effect of simulated waste species (base glasses loaded with 25wt% of only selected waste species) in these glasses on radiation induced diffusion. Eight types of glasses were irradiated with 8 MeV Au3+ ions upto a fluence of 1e16 ions-cm-2. These Au ions used simulate the effect of damage caused by recoils of alpha-decay processes where an actinide, eg. 239Pu gets converted to 235U by releasing an alpha-particle. The irradiated glasses were characterized using several complementary Ion Beam Analysis (IBA) techniques to enabled quantification of concentration and diffusion of various species in these glass samples. Rutherford Backscattering Spectrometry (RBS), Nuclear Reaction Analysis (NRA) and PIXE (Particle Induced X-ray Emission) were performed to obtain a depth profile of Li concentration and diffusion of heavy elements in these glasses. Data obtained from IBA will be correlated and presented with swelling observed using a profilometer and local coordination changes using Raman Spec and IR microscopy.
Year(s) Of Engagement Activity 2022
 
Description Poster at Physics of Non-Crystalline Solids conference, 11th-15th July 2022, Canterbury, University of Kent (UK): The Effect of Lithium Concentration on the Network Connectivity in Pristine UK Nuclear Waste Glasses 
Form Of Engagement Activity A talk or presentation
Part Of Official Scheme? No
Geographic Reach International
Primary Audience Other audiences
Results and Impact The audience comprised of experts from UK's glass community so they were able to appreciate the importance of glass in the nuclear technology and nuclear waste management. They could also appreciate Effect of Lithium on the Network Connectivity in UK's Nuclear Waste Glasses. This helps how durability of glasses is dependent on glass structure and the chemistry. These studies provide the scientific basis for using glasses for immobilisation of nuclear waste.

The glass compositions used in the UK to immobilise the highly radioactive waste arising from the reprocessing of used nuclear fuel are termed 'Calcium Zinc' (CaZn) and 'Mixture Windscale' (MW). In this work, CaZn and MW base glasses are studied with their full and half lithium content to evaluate the impact that lithium concentration has network connectivity of the glass network. Previous studies by others have been carried out to determine the role of lithium in the glass network and the impact lithium has on the aqueous durability of the glass. By building upon these works and utilising the advance NMR techniques such as Multi-Quantum Magic Angle Spinning (MQMAS) and Heteronuclear Multiple Quantum Coherence (HMQC) we have been able to pinpoint the position of lithium in the glass network at varying compositions. Alongside NMR spectroscopy, Raman spectroscopy investigations and glass transition (Tg) measurements were carried out to support the NMR data. From the data obtained, we see when the lithium concentration is increased in the glass the number of four-coordinated boron sites increases at the expense of the three-coordinated boron sites, while simultaneously the silicate network becomes increasingly depolymerised. We understand this to be due to the lithium ion being primarily associated with the silicate network in the glass, thus increased lithium, a network modifier, leads to increased depolymerisation and a lower Tg. We believe the increase in four-coordinated boron sites is due to other network modifiers/charge compensators, such as sodium, becoming more readily available as lithium concentration increases. This information is fundamental for determining the long-term evolution of high-level nuclear waste immobilisation in the UK. This thorough study of the pristine glass network will facilitate an understanding of the change in polymerisation when the glass network is exposed to radiation. Studies are currently ongoing to evaluate the effect that lithium concentrations has on the radiation damage in the glass caused by gamma rays.
Year(s) Of Engagement Activity 2022