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Field Assisted Sintering of Nuclear Fuel Simulants

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AI plain-English summary

Britain’s Advanced Gas-cooled Reactors will produce around 5,000 tonnes of spent nuclear fuel, much of it currently stored in ponds at Sellafield. Some fuel pins have corroded cladding, which can leak radioactive material into the water and degrade the uranium dioxide pellets inside. This project tackles two specific unknowns about what happens when wet-stored fuel is moved to dry storage, a transition the Nuclear Decommissioning Authority is considering. First, how do water-exposed fuel pellets corrode, with and without the radiation field that a real spent fuel rod produces? Second, what happens during the drying process itself—especially for pellets that have already been damaged by pond corrosion? If the research succeeds, it will give operators the mechanistic understanding needed to decide whether dry storage is safe, and under what conditions. That directly affects the UK’s multi-decade plan for managing high-level nuclear waste until a permanent geological repository opens around 2075. The work is applied and problem-driven: it fills specific gaps in corrosion and drying science that currently block a major policy decision on nuclear waste management.

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The expected remaining lifetime of the UK's Advanced Gas-cooled Reactors (AGRs) will result in the generation of ~5,000t of AGR Spent Nuclear Fuel (SNF). The UK Nuclear Decommissioning Authority's (NDA's) preferred option for managing AGR SNF is interim storage - currently in ponds at the Sellafield site - prior to consignment to repository ca. 2075. AGR fuel pins consist of UO2 pellets sealed inside steel cladding tubes. Whilst in-reactor, some of the cladding can be rendered susceptible to in-pond corrosion, potentially leading to through-wall cladding failure. This may result in pondwater contamination by the SNF and inter-granular corrosion of the pellets themselves with loss of pellet integrity. Consequently, a transition to dry storage has been proposed - including the drying of wet stored SNF. This may carry further unknown risks which must be understood before implementation. Key knowledge gaps relating to this understanding include: 1. A mechanistic understanding of how pondwater-exposed wet-stored spent UO2 fuel pellets corrode in both the absence and, especially, the presence of a radiation field; and 2. A mechanistic understanding of the possible drying processes of fuel pellets, again both in the presence and absence of radiation fields - but especially in wet-to-dry transitioned fuel with failed cladding and that may have been subject to in-pond corrosion processes.

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Researchers

Jamie Parsonage (Student)

Related Research

Grants with similar aims, by meaning.

The kinetics of new reprocessing routes for nuclear fuel
Effect of burn-up on mechanical and chemical stability of spent fuel during wet and dry storage
Behaviour of UK Specific Spent Fuels Under Conditions Relevant to Geological Disposal.
The Management of Spent Oxide Fuel: Irradiation of AGR SIMfuels in Pond Storage Environments - Consequences for UO2 Corrosion and Water Radiolysis
Simulated Used Nuclear Fuel Dissolution as a Function of Fuel Chemistry and Near Field Conditions

Original classification

Studentship

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