List of abstracts (oral)
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Aqueous Leaching of Very High Burnup UO₂ Spent Nuclear Fuel Under Hydrogen Pressure.
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Application of Mössbauer spectroscopy to the solution of radioactive waste vitrification challenges
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Disposition of separated plutonium: current and historical perspectives
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Purpose and capabilities of the ThermoChimie database, a recent history of key developments, and some examples of benchmarking
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The Corrosion of UO2-based Spent Nuclear Fuel under Storage and Disposal Conditions: A comparison of real irradiated fuel and SIMFUEL Studies
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Evaluating Disposal of Plutonium Wasteforms
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What Can You Do with a PhD in the Nuclear Industry?
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Towards the Disposability of the UK’s Plutonium Inventory
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Developing opportunities for vitrification of complex radioactive wastes from the Sellafield site
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The ILW Thermal Treatment Landscape at Sellafield Ltd. 2026
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Ceramic Wasteform and Process Development for Pu Disposition
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Boron isotope diffusion during glass-fluid interactions: Effects of glass composition and solution renewal
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Plutonium Science at Sellafield Limited
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Simulating Water Radiolysis with H2O2 in Leaching Tests of Candidate Pu Wasteforms
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Magnesium and the chemical durability of UK HLW glasses
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Challenges for the Treatment of High Heat Generating Waste (HHGW) at Sellafield
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Plutonium Immobilisation Research at Manchester: DMOX Wasteforms and Novel Sintering Technologies
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Mechanistic aspects of radiation-induced dissolution of UO2-based used nuclear fuel
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Atomistic insights into the interactions of small molecules with PuO2 surfaces
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Operando Observation of Dissolution Kinetics and Alterations Layer Formation of Heavy Ion Irradiated Borosilicate Glass by Fluid-cell Raman Spectroscopy
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From Knowledge Gaps to Disposal Confidence: A Multidisciplinary Approach to Actinide Waste Disposal.
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NWS R&D for UK GDF
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Studies on Waste Management and Disposal: Applications to Fukushima (1F) Decommissioning and Nuclear Fuel Cycle Systems
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Safety and Security cases for GDF - Overview and case study for criticality safety
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Influence of helium ions irradiation on leaching behaviours of borosilicate glasses
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Toward an integrative Approach of Nuclear Glass alteration in a Reactive environment from MultiscAle Modelling
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The use of isotopic tracing to study the formation of the alteration layer on corroded glass
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Electrochemical Corrosion Rate Studies of MOX SIMFuels
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Disposal MOX – A Combined Study of its Fabrication and Disposability
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Time-of-Flight Elastic Recoil Detection Analysis for Simulated Radiation Induced Diffusion Effects on Nuclear Waste Glasses
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Lessons from nature; insights into long-term vitrified waste corrosion mechanisms from natural analogue systems
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Impact of α-damage and radiogenic helium formation on the properties of actinide based oxides: implications for their use, waste storage and disposal.
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Coupling Effects of Irradiation and Corrosion on Borosilicate Glass and Prospects for Laboratory Simulation Methods
List of abstracts (poster)
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Influence of Processing Route (HIP vs CPS) on the Properties of Titanate Wasteforms
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Analysis of Vitrified Simulant Plutonium Contaminated Material from Industrial Trials
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Criticality Safety: Investigating the co-mobility of actinides and neutron absorbers in radioactive waste disposal
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High Level Waste Nepheline Precipitation Boundary: Investigating Worst and Best Case Scenarios
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Disposal MOX for the immobilisation of the UK’s plutonium inventory
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Effect of MOx Composition and Homogeneity on Disposal Performance
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Effect of Temperature and pH on the Corrosion of Ceramics and the Role of Secondary Phases and Grain Boundaries
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Probing Radiation Damage Mechanisms in Zirconolite Systems
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Investigating the Use of Thorium Within Disposal-MOX (DMOX) for Corrosion Inhibition
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Spent Fuel Leaching in Challenging Groundwaters: Development & Validation of a Fast Throughput, Corrosion-based Dissolution Rate Measurement Methodology
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The Synthesis and Aqueous Durability of Ce.Gd doped and non-doped Zirconolite
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Assessment of D-MOX Manufacturing Parameters on Product Microstructure
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Disposability Assessments of Multiphase Synroc Ceramics for the Thermal Treatment of UK Radioactive Wastes
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Novel Characterisation of Disposal Materials for High Level Waste Using Time-of-Flight Elastic Recoil Detection Analysis
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Ni retention during devitrification of high-level radioactive waste glasses
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Exploring the development and corrosion behaviour of Se-doped SIMFUELs
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Precursor and Phase Development of Zirconolite Wasteforms
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Underpinning Laboratory-Based High-Level Waste Glass Dissolution Tests
Advisory Panel and Organising Committee
Yingjie Zhang - ANSTO Australia. Mats Jonsson - KTH Sweden. Sylvain Peuget - CEA Marcoule France. Mara Iris Lonartz - University of Bonn, Germany. Clare Thorpe - University of Sheffield. Ian Farnan - University of Cambridge. Mir Anamul Haq - University of Cambridge. Paul Heath - NWS