Thermal energy transport in oxide nuclear fuel

DH Hurley, A El-Azab, MS Bryan, MWD Cooper… - Chemical …, 2021 - ACS Publications
To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts
seek solid fuels that must withstand unprecedented temperature and radiation extremes. In …

Multiphysics analysis of fuel fragmentation, relocation, and dispersal susceptibility–Part 1: Overview and code coupling strategies

I Greenquist, A Wysocki, J Hirschhorn, N Capps - Annals of Nuclear Energy, 2023 - Elsevier
The US nuclear energy industry is investigating strategies to increase the reactor operating
cycle to 24 months, resulting in peak rod average burnups exceeding the current limit of 62 …

TRISO particle fuel performance and failure analysis with BISON

W Jiang, JD Hales, BW Spencer, BP Collin… - Journal of Nuclear …, 2021 - Elsevier
Because of its widespread use in multiple advanced reactor concepts, the ability to
accurately simulate tri-structural isotropic (TRISO) fuel performance is essential for ensuring …

ALCYONE: the fuel performance code of the PLEIADES platform dedicated to PWR fuel rods behavior

C Introïni, I Ramière, J Sercombe, B Michel… - Annals of Nuclear …, 2024 - Elsevier
The aim of this contribution is to deeply introduce the ALCYONE Fuel Performance Code.
ALCYONE is being implemented within the PLEIADES numerical framework and is …

[HTML][HTML] Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding

CP Massey, KA Kane, RT Sweet, SB Bell… - Materials & Design, 2023 - Elsevier
Oxide dispersion–strengthened (ODS) FeCrAl alloys are an advanced cladding material that
combines the high-temperature steam oxidation resistance of conventional wrought FeCrAl …

Moose reactor module: An open-source capability for meshing nuclear reactor geometries

E Shemon, Y Miao, S Kumar, K Mo… - Nuclear Science and …, 2023 - Taylor & Francis
Abstract The US Department of Energy (DOE) Nuclear Energy Advanced Modeling and
Simulation (NEAMS) program has developed numerous physics solvers utilizing the open …

Multi-objective optimization design of TRISO-based fully ceramic microencapsulated fuel

C Zhang, J Liu, X Li, C Wei, C Zheng, H Liao… - Journal of Nuclear …, 2023 - Elsevier
Abstract Fully Ceramic Microencapsulated (FCM) fuel is a new type of material in nuclear
energy field. It has become a promising accident tolerant fuel (ATF) candidate due to its …

Asymptotic hydrogen redistribution analysis in yttrium-hydride-moderated heat-pipe-cooled microreactors using DireWolf

S Terlizzi, V Labouré - Annals of Nuclear Energy, 2023 - Elsevier
Yttrium hydride (YH x) is one of the materials being considered for moderating thermal and
epithermal nuclear microreactors. One potential issue with YH x use is that the hydrogen …

Reliability estimation of an advanced nuclear fuel using coupled active learning, multifidelity modeling, and subset simulation

SLN Dhulipala, MD Shields, P Chakroborty… - Reliability Engineering & …, 2022 - Elsevier
Tristructural isotropic (TRISO)-coated particle fuel is a robust nuclear fuel and determining its
reliability is critical for the success of advanced nuclear technologies. However, TRISO …

A multiphysics model of the versatile test reactor based on the MOOSE framework

N Martin, R Stewart, S Bays - Annals of Nuclear Energy, 2022 - Elsevier
The traditional modeling approach for sodium fast reactor cores relies on separate physics
models, where the fuel performance, thermal–hydraulics, and neutronics calculations …