Thermal energy transport in oxide nuclear fuel
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 …
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
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 …
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
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 …
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
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 …
ALCYONE is being implemented within the PLEIADES numerical framework and is …
[HTML][HTML] Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding
Oxide dispersion–strengthened (ODS) FeCrAl alloys are an advanced cladding material that
combines the high-temperature steam oxidation resistance of conventional wrought FeCrAl …
combines the high-temperature steam oxidation resistance of conventional wrought FeCrAl …
Moose reactor module: An open-source capability for meshing nuclear reactor geometries
Abstract The US Department of Energy (DOE) Nuclear Energy Advanced Modeling and
Simulation (NEAMS) program has developed numerous physics solvers utilizing the open …
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 …
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
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 …
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
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 …
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
The traditional modeling approach for sodium fast reactor cores relies on separate physics
models, where the fuel performance, thermal–hydraulics, and neutronics calculations …
models, where the fuel performance, thermal–hydraulics, and neutronics calculations …