[HTML][HTML] A review of fuel performance modelling

P Van Uffelen, J Hales, W Li, G Rossiter… - Journal of Nuclear …, 2019 - Elsevier
Dr. Paul Van Uffelen graduated from the Vrije Universiteit Brussel (Belgium) and the Ecole
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …

Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects

G Wang, Z Wang, D Yun - Metals, 2023 - mdpi.com
Lead-cooled fast reactors (LFRs) are considered one of the most promising technologies to
meet the requirements introduced for advanced nuclear systems. LFRs have higher neutron …

Development of Cr cold spray–coated fuel cladding with enhanced accident tolerance

M Ševeček, A Gurgen, A Seshadri, Y Che… - Nuclear Engineering …, 2018 - Elsevier
Accident-tolerant fuels (ATFs) are currently of high interest to researchers in the nuclear
industry and in governmental and international organizations. One widely studied accident …

An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions

KA Gamble, T Barani, D Pizzocri, JD Hales… - Journal of nuclear …, 2017 - Elsevier
Abstract Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel
cladding for increased accident tolerance. An analysis of the response of FeCrAl under …

[HTML][HTML] Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors

Y Wang, ZM Prince, H Park, OW Calvin, N Choi… - Annals of Nuclear …, 2025 - Elsevier
Abstract Griffin is a Multiphysics Object-Oriented Simulation Environment (MOOSE) based
reactor physics application for multiphysics simulations of advanced reactor designs jointly …

Validating the BISON fuel performance code to integral LWR experiments

RL Williamson, KA Gamble, DM Perez… - … Engineering and Design, 2016 - Elsevier
BISON is a modern finite element-based nuclear fuel performance code that has been under
development at Idaho National Laboratory (INL) since 2009. The code is applicable to both …

Fission gas diffusion and release for Cr2O3-doped UO2: From the atomic to the engineering scale

MWD Cooper, G Pastore, Y Che, C Matthews… - Journal of Nuclear …, 2021 - Elsevier
The anticipated benefits of large grains in Cr 2 O 3-doped UO 2 pellets include improved
mechanical and fission gas retention properties. To support the assessment of fission gas …

[HTML][HTML] SCIANTIX: a new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes

D Pizzocri, T Barani, L Luzzi - Journal of Nuclear Materials, 2020 - Elsevier
Bridging lower length-scale calculations with the engineering-scale simulations of fuel
performance codes requires the development of dedicated intermediate-scale codes. In this …

[HTML][HTML] The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments

G Zullo, D Pizzocri, L Luzzi - Journal of Nuclear Materials, 2023 - Elsevier
SCIANTIX is a 0D, open-source code designed to model inert gas behaviour within nuclear
fuel at the scale of the grain. The code predominantly employs mechanistic approaches …

Full core LOCA safety analysis for a PWR containing high burnup fuel

N Capps, A Wysocki, A Godfrey, B Collins… - … Engineering and Design, 2021 - Elsevier
For economic reasons, the US nuclear industry is renewing efforts to build a technical basis
to extend peak rod average burnup limits above the current regulatory burnup limit of 62 …