P2M Simulation Exercise on Past Fuel Melting Irradiation Experiments

Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests

(2022) A. Germain et al.   JOURNAL OF NUCLEAR MATERIALS

Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data

(2021) A. Magni et al.   JOURNAL OF NUCLEAR MATERIALS

Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications

(2020) A. Magni et al.   JOURNAL OF NUCLEAR MATERIALS

Development of a robust, accurate and efficient coupling between PLEIADES/ALCYONE 2.1 fuel performance code and the OpenCalphad thermo-chemical solver

(2020) C. Introïni et al.   NUCLEAR ENGINEERING AND DESIGN

TAF-ID: An international thermodynamic database for nuclear fuels applications

(2020) C. Guéneau et al.   CALPHAD-COMPUTER COUPLING OF PHASE DIAGRAMS AND THERMOCHEMISTRY

Model updates and performance evaluations on fuel performance code FEMAXI-8 for light water reactor fuel analysis

(2019) Yutaka Udagawa et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method

(2018) Stephen Novascone et al.   JOURNAL OF NUCLEAR MATERIALS

Technical note: On modelling central void formation in LWR fuel pellets due to high-temperature restructuring

(2018) Grigori Khvostov   Nuclear Engineering and Technology

Phase-field simulations of pore migration and morphology change in thermal gradients

(2017) Ian W. Vance et al.   JOURNAL OF NUCLEAR MATERIALS

Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment

(2017) B. Michel et al.   NUCLEAR TECHNOLOGY

Modelling actinide redistribution in mixed oxide fuel for sodium fast reactors

(2013) Valentino Di Marcello et al.   PROGRESS IN NUCLEAR ENERGY

Multidimensional multiphysics simulation of nuclear fuel behavior

(2012) R.L. Williamson et al.   JOURNAL OF NUCLEAR MATERIALS

In-Core Fuel Performance and Material Characterization in the Halden Reactor

(2010) Rudi Van Nieuwenhove et al.   IEEE TRANSACTIONS ON NUCLEAR SCIENCE

Overview of experimental programs on core melt progression and fission product release behaviour

(2008) B.J. Lewis et al.   JOURNAL OF NUCLEAR MATERIALS