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 …
BISON: A flexible code for advanced simulation of the performance of multiple nuclear fuel forms
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 …
Simulation Environment (MOOSE) finite element library. One of its major goals is to have a …
Experimentally known properties of U-10Zr alloys: A critical review
DE Janney, SL Hayes - Nuclear Technology, 2018 - Taylor & Francis
Abstract More than 14 000 U-10Zr fuel rods (alloys of U with 10 wt% Zr) were irradiated in
the Experimental Breeder Reactor II and Fast Flux Test Facility, with some irradiated to …
the Experimental Breeder Reactor II and Fast Flux Test Facility, with some irradiated to …
Coupled multiphysics simulations of heat pipe microreactors using DireWolf
DireWolf is a multiphysics software driver application designed to simulate heat pipe–cooled
nuclear microreactors. Developed under the US Department of Energy, Office of Nuclear …
nuclear microreactors. Developed under the US Department of Energy, Office of Nuclear …
[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 …
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 …
fuel at the scale of the grain. The code predominantly employs mechanistic approaches …
Automatic differentiation in MetaPhysicL and its applications in MOOSE
Efficient solution via Newton's method of nonlinear systems of equations requires an
accurate representation of the Jacobian, corresponding to the derivatives of the component …
accurate representation of the Jacobian, corresponding to the derivatives of the component …
Accelerating nuclear fuel development and qualification: Modeling and simulation integrated with separate-effects testing
An approach to transform and accelerate nuclear fuel development and qualification is
outlined. The approach exploits advanced modeling and simulation at the outset to inform …
outlined. The approach exploits advanced modeling and simulation at the outset to inform …
Density functional theory calculations of self-and Xe diffusion in U3Si2
Abstract Uranium silicide, U 3 Si 2, has been proposed as an advanced nuclear fuel to be
used in light water reactors (LWRs). Development of this alternative to the predominant …
used in light water reactors (LWRs). Development of this alternative to the predominant …
Physics-guided machine learning from simulation data: An application in modeling lake and river systems
This paper proposes a new physics-guided machine learning approach that incorporates
the scientific knowledge in physics-based models into machine learning models. Physics …
the scientific knowledge in physics-based models into machine learning models. Physics …