[HTML][HTML] Consideration of Cr-doped UO2 fuel performance for a Fluoride-Cooled High Temperature Reactor concept

A de Lara, P Van Uffelen, G Nicodemo, G Zullo… - Annals of Nuclear …, 2024 - Elsevier
This work follows the AGR-like FHR ongoing research that proposes to adopt the British
Advanced Gas cooled Reactor (AGR) geometry combined with the molten salt Fluoride …

Reactivity-initiated accidents in two pressurized water reactor high burnup core designs

MA Fox, IO Lindsay, JP Gorton, NR Brown - Nuclear Engineering and …, 2023 - Elsevier
This paper presents a safety analysis of two proposed core loadings for 24-month
Pressurized Water Reactor (PWR) fuel cycles. This analysis focuses on reactivity-initiated …

Mesoscale modeling of the effects of accelerated burnup on UO2 microstructural evolution

A Cheniour, FW Hilty, CM Petrie, NA Capps - Journal of Nuclear Materials, 2024 - Elsevier
Accelerating the nuclear fuel qualification process will rely on some combination of
advanced modeling and simulation techniques with accelerated irradiation testing and …

Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2

AJ Terricabras, SM Drewry, K Campbell… - Journal of Nuclear …, 2024 - Elsevier
Chromium-doped UO 2 fuel has received significant interest due to the ability for chromium
to produce pellets with large average grain size (> 30 μm), which has shown to increase …

Using in situ UO2 bicrystal sintering to understand grain boundary dislocation nucleation kinetics and creep

SJ Dillon, SC Finkeldei, E Lang… - Journal of the …, 2024 - Wiley Online Library
Capillary evolution at bicrystal UO2 grain boundaries is characterized using in situ
transmission electron microscopy. The discontinuous nature of the densification process …

Effects of second phase particles and pores on grain boundary migration during solid-state sintering: A phase-field study

X Qi, Y Jiang, W Shen, J Cao, Y Liao, W Liu - Nuclear Engineering and …, 2025 - Elsevier
In the present work, a new phase-field model was developed to simulate the effects of
second phase particles and pores on grain boundary (GB) removement during solid-state …

Multiscale Modeling of Radiation Damage in UO2 under Accelerated Burnup Conditions

A Cheniour, I Greenquist, NA Capps, CM Petrie - 2023 - osti.gov
Accelerated fuel qualification (AFQ) is a methodology by which new nuclear fuels are
developed in an accelerated time frame compared with historical fuel qualification …

Consideration of fuel behaviour in AGR-like FHR reactor design

A De Lara - 2025 - repository.cam.ac.uk
Abstract The Fluoride Salt-cooled High-temperature Reactor (FHR) is a subclass of Molten
Salt Reactor (MSR) that uses solid fuel separated from the molten coolant salt. Previous …

[PDF][PDF] Fuel Performance Calculations of Tagged UO¬ 2 MiniFuel Disks

I Greenquist, A Shields - 2024 - osti.gov
Isotopic taggants are being considered as a novel form of forensic identifiers for nuclear
fuels. As part of this effort, eighteen tagged MiniFuel disks were irradiated in the High Flux …

[PDF][PDF] Intentional Forensics: Tagging Strategies for Rapid Nuclear Material Provenance Assessment

SM Scott, NE Marks, AE Shields, MS Wellons… - 2023 - resources.inmm.org
Intentional Forensics is the strategy of deliberately introducing benign and persistent
material signatures during nuclear fuel fabrication and processing. The purpose is to reduce …