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[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 …
Nationale Supérieure Polytechnique de Grenoble (France) with a master degree in …
Multidimensional multiphysics simulation of nuclear fuel behavior
Nuclear fuel operates in an environment that induces complex multiphysics phenomena,
occurring over distances ranging from inter-atomic spacing to meters, and times scales …
occurring over distances ranging from inter-atomic spacing to meters, and times scales …
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 …
The OFFBEAT multi-dimensional fuel behavior solver
Abstract The OpenFOAM Fuel BEhavior Analysis Tool, or OFFBEAT, is a multi-dimensional
fuel performance code under collaborative development at the Laboratory for Reactor …
fuel performance code under collaborative development at the Laboratory for Reactor …
Simulation of pellet-cladding interaction with the pleiades fuel performance software environment
This paper focuses on the PLEIADES fuel performance software environment and its
application to the modeling of pellet-cladding interaction (PCI). The PLEIADES platform has …
application to the modeling of pellet-cladding interaction (PCI). The PLEIADES platform has …
Pellet-clad interaction behavior in zirconium alloy fuel cladding
MHA Piro, D Sunderland, S Livingstone… - Comprehensive …, 2020 - inl.elsevierpure.com
Abstract Pellet-Clad Interaction (PCI) in zirconium alloy cladding has been a long-standing
concern in the context of nuclear fuel reliability. Mitigation measures have constrained …
concern in the context of nuclear fuel reliability. Mitigation measures have constrained …
Modeling constituent redistribution in U–Pu–Zr metallic fuel using the advanced fuel performance code BISON
J Galloway, C Unal, N Carlson, D Porter… - Nuclear Engineering and …, 2015 - Elsevier
An improved robust formulation for constituent distribution in metallic nuclear fuels is
developed and implemented into the advanced fuel performance framework BISON. The …
developed and implemented into the advanced fuel performance framework BISON. The …
Enhancing the ABAQUS thermomechanics code to simulate multipellet steady and transient LWR fuel rod behavior
RL Williamson - Journal of Nuclear Materials, 2011 - Elsevier
A powerful multidimensional fuels performance analysis capability, applicable to both steady
and transient fuel behavior, is developed based on enhancements to the commercially …
and transient fuel behavior, is developed based on enhancements to the commercially …
Power ramped cladding stresses and strains in 3D simulations with burnup-dependent pellet–clad friction
J Sercombe, I Aubrun, C Nonon - Nuclear Engineering and Design, 2012 - Elsevier
This paper presents 2D (r, θ) plane strain and 3D simulations of PCI during base irradiation
and ramp tests. Inverse analysis is used to estimate the evolution of friction at the pellet–clad …
and ramp tests. Inverse analysis is used to estimate the evolution of friction at the pellet–clad …
Calculation of threshold displacement energies in UO2
Despite the extensive utilization of uranium dioxide (UO 2) as a fuel in commercial nuclear
reactors, there is only minimal information regarding the fundamental nature of radiation …
reactors, there is only minimal information regarding the fundamental nature of radiation …