123 citations · 144 across the 5 of their papers we have counts for
5 papers
Development of a Model for Irradiation-Assisted Grain Growth for Nanocrystalline UO2
Md Ali Muntaha, Larry Aagesen, Michael Tonks
In this work, we have developed a model for irradiation-assisted grain growth in nanocrystalline UO using the MARMOT code. We include the impact of irradiation on UO grain…
Impact of grain boundary and surface diffusion on predicted fission gas bubble behavior and release in UO fuel
Md Ali Muntaha, Sourav Chatterjee, Sophie Blondel +4
In this work, we quantify the impact of grain boundary (GB) and surface diffusion on fission gas bubble evolution and fission gas release in UO nuclear fuel using simulations w…
Understanding Fission Gas Bubble Distribution, Lanthanide Transportation, and Thermal Conductivity Degradation in Neutron-irradiated α-U Using Machine Learning
Lu Cai, Fei Xu, Fidelma Dilemma +6
UZr based metallic nuclear fuel is the leading candidate for next-generation sodium-cooled fast reactors in the United States. US research reactors have been using and testing this…
A Sublattice Phase-Field Model for Direct CALPHAD Database Coupling
D. Schwen, C. Jiang, L. K. Aagesen
The phase-field method has been established as a de facto standard for simulating the microstructural evolution of materials. In quantitative modeling the assessment and compilatio…
Rapid multiphase-field model development using a modular free energy based approach with automatic differentiation in MOOSE/MARMOT
Daniel Schwen, Larry K. Aagesen, John W. Peterson +1
We present a novel phase-field model development capability in the open source MOOSE finite element framework. This facility is based on the 'modular free energy' approach in which…