Prospects for additive manufacturing of nuclear fuel forms

AT Nelson - Progress in Nuclear Energy, 2023 - Elsevier
Additive manufacturing (AM) is viewed as a critical enabling technology for achieving
superior performance and improved economics across many sectors. Although the past …

BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms

RL Williamson, JD Hales, SR Novascone… - Nuclear …, 2021 - Taylor & Francis
BISON is a nuclear fuel performance application built using the Multiphysics Object-Oriented
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …

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 …

Multiphysics phase-field modeling of quasi-static cracking in urania ceramic nuclear fuel

W Li, K Shirvan - Ceramics International, 2021 - Elsevier
This work presents phase-field modeling of quasi-static cracking in urania (UO 2) ceramic
nuclear fuel under neutron radiation at high temperatures. Considering the tightly coupled …

[HTML][HTML] A review on the thermo-mechanical modelling needs in system codes

J Sanchez-Torrijos, P Aragón, C Queral, F Feria… - … Engineering and Design, 2023 - Elsevier
A review of the current thermomechanical needs along with a recommendation of the most
urgent ones to be implemented in system codes are presented in this paper as part of the …

Sensitivity of UO2 fuel performance to microstructural evolutions driven by dilute additives

A Cheniour, RT Sweet, AT Nelson, BA Wilson… - … Engineering and Design, 2023 - Elsevier
Use of dilute additives to nuclear fuel is being considered to increase the security of
commercial fuel management through traceability of fabricated fuel elements. Taggants, as …

Application of Kriging and Variational Bayesian Monte Carlo method for improved prediction of doped UO2 fission gas release

Y Che, X Wu, G Pastore, W Li, K Shirvan - Annals of Nuclear Energy, 2021 - Elsevier
One of the advanced nuclear fuel concepts for current commercial water-cooled reactors
focuses on microstructural modification of UO 2 fuel via dopants. Dopants can effectively …

[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 …

Grand potential sintering simulations of doped UO2 accident-tolerant fuel concepts

I Greenquist, M Tonks, M Cooper, D Andersson… - Journal of Nuclear …, 2020 - Elsevier
Chromium-doped UO is a widely-studied near-term deployable accident-tolerant fuel
concept because it results in a dense, large-grain structure that increases the fuel resistance …

Risk-informed safety analysis for accident tolerant fuels

C Parisi, Z Ma, D Mandelli, N Anderson… - Nuclear Science and …, 2020 - Taylor & Francis
Accident tolerant fuels (ATFs) are being tested by different nuclear vendors and research
organizations, and their introduction into the US light water reactor fleet is planned for the …