NuFuel 2021 has finished. Thank you to all of our attendees.
Programme
NuFuel 2021 is being run as a hybrid conference meaning we will be welcoming delegates to Bangor University both in-person and online. The technical programme is shown in the table below. Abstracts are accessed through the links in this table.
Conference Locations
Find your way around NuFuel 2021
Notes for presenters
Presenters have been assigned a 20 minute time-slot. Presentations should be 15 minutes in duration leaving 5 minutes for questions.
To make the NuFuel 2021 conference run as smoothly as possible, conference presentations should be sent to nufuel@bangor.ac.uk in advance of your presentation.
Registration
Attendees will be able to register and collect their conference packs from outside the Main Arts Lecture Theatre during the event.
In addition, there will be a temporary registration desk at the student accommodation where most del- egates are staying. This will allow you to collect your conference material when checking in at the Idwal Building. This registration desk will operate between 12pm-5pm on Monday 13th September 2021.
Conference Dinner
- 7.00pm: Pre-dinner drinks reception (Penrhyn Terrace, Reichel Hall)
- 7.30pm: Dinner (Reichel Hall)
Lunch & Refreshments
- Tea, coffee, water and light snacks will be provided during breaks.
- A buffet lunch will be provided Tuesday-Thursday.
- Lunch and breaks will take place in Prichard Jones room which is by the main conference lecture theatre.
Schedule
Monday - 13th September 2021
Tuesday - 14th September 2021
- Registration
-
- Welcome to Nufuel-2021
-
NuFuel Organising Committee
- Break
-
- Uranium Nitride Synthesis and Fuel Form fabrication at The University of Manchester: Method Development and Observations
-
James Buckley
- Ammonia based routes for the manufacture of uranium nitride
-
Tahera Docrat
- Advances in the synthesis of uranium diboride
-
Fabio Martini
- UN-UB₂ composites
-
Joel Turner
- Lunch
-
- Field assisted sintering of CeO₂, UO₂ and mixed (U,Ce)O₂ pellets
-
Robert W. Harrison
- Synthesis of Simfuel including fission products by Spark Plasma Sintering for oxidation study
-
Emanuele De Bona
- UN-Nb Composite Fuel as an Advanced Technology Fuel for Use in Light Water Reactors
-
Max Salata-Barnett
- Fabrication and characterization of FPs-doped U1-xPuyO2-x SIMfuel
-
Rafael Caprani
- Break
-
- Hydrothermal conversion of uranium(IV)-cerium oxalates into uranium-cerium mixed oxides
-
Sofian Benarib
- Elaboration of (U,Pu)O₂₋ₓ mixed oxides with high plutonium contents: 60, 65 and 70 mol.% Pu.
-
Marie-Margaux Desagulier
- Self-irradiation effects on the structural properties of the MIMAS type of nuclear fuels
-
Orhun Kahraman
Wednesday - 15th September 2021
- Coupling SCIANTIX and TRANSURANUS: assessment of stable and radioactive fission gas behaviour.
-
Giovanni Zullo
- Calibration of fuel performance models - A hierarchical Bayesian approach to account for model inadequacy
-
Gustav Robertson
- Modelling of thermal properties of MOX fuel for fuel performance codes: uncertainty analyses and propagation at the integral pin level
-
Alessio Magni
- Reactivity behaviours and economic effect of enriched Gadolinium oxide
-
Mustafa Bolukbasi
- Break
-
- Empirical potential investigation of activation energies of cationic defects in uranium-plutonium mixed oxides
-
Marjorie Bertolus
- A Study of Defect Behaviour in UO₂ using Adaptive Kinetic Monte Carlo Simulation
-
Laura Swansbury
-
Diffusion in amorphous chromia doped uranium dioxide
-
Megan Owen
- Non-destructive examination of the SALIENT-01 molten fuel salt irradiation
-
Ralph Hania
- Lunch
-
- Experimental results on the U-Zr-Fe-O liquid miscibility gap and its sub-systems
-
Alan Brunel
- Influence of Am on thermodynamic properties of MOX fuels: melting temperature, oxygen potential and heat capacity
-
Pauline Fouquet-Métivier
- JRCMSD - Thermodynamic Database on Molten Salt Reactor Fuel
-
Ondrej Benes
- Thermodynamic assessment of the NaCl-ThCl₄-PuCl₃ system
-
Thomas Dumaire
- Break
-
- Synthesis and characterisation of actinide fluorides molten salt fuel for SALIENT-03 irradiation experiment
-
Pavel Souček
- Investigation of Thorium Tetrafluoride Purification Using the Ammonium Bifluoride method
-
Bernard Fitzpatrick
- Fission Products chemistry in simulated PWR fuel up to 2100°C: Experimental characterization and Thermodynamic modeling with the TAF-ID
-
Ernesto Geiger
- Yellowjacket: Coupling Gibbs Energy Minimisation with Phase Field Method for Corrosion Modelling in Molten Salt Reactors
-
Parikshit Bajpai
Thursday - 16th September 2021
- Impact of lithium accommodation on defect chemistry in ZrO₂
-
Gareth F. Stephens
- Modelling of solute cluster and H-dislocation interactions in zirconium
-
Daniel J M King
- A finite element analysis of the residual stresses arising during the fabrication of TRISO particle fuel
-
Angelo Battistini
- A Linear-Elastic Peridynamic Model for the Fracture of Coated Particle Fuel under Thermal Loads during Idealised Early Life Operation
-
Thomas Haynes
- Break
-
- Modelling Weibull Distributions in Peridynamics for Nuclear Fuel
-
Lloyd Jones
- Defect chemistry and radiation behaviour of Gd-doped UO₂
-
Ritesh Mohun
- TEM observations on fission gas bubbles at high burn up in irradiated UO₂ fuel.
-
Mathieu Angleraud
- Vacancy defects identification in Au 4 MeV irradiated UO₂ using Positron Annihilation Spectroscopy
-
Marie-lyne Amany
- Lunch
-
- Alginated zirconium diboride kernels with sputter-deposited tungsten coatings
-
Phylis Makurunje
- The corrosion of single phase uranium silicide thin films
-
Lottie Harding
- Influence of oxygen content on thermally activated Kr diffusion in UO₂₊ₓ
-
Eric Gilabert