Recent progress in the development of coarse-mesh nodal methods for the numerical
solution of the neutron diffusion and transport equations is reviewed. In contrast with earlier …

The article provides an overview of the reactor dynamics code DYN3D. The code comprises
various 3D neutron kinetics solvers, a thermal-hydraulics reactor core model and a thermo …

Advances in parallel computing have made possible the development of high-fidelity tools
for the design and analysis of nuclear reactor cores, and such tools require extensive …

Abstract A consistent “2D/1D” neutron transport method is derived from the 3D Boltzmann
transport equation, to calculate fuel-pin-resolved neutron fluxes for realistic full-core …

Advanced reactor concepts span the spectrum from heat pipe–cooled microreactors,
through thermal and fast molten-salt reactors, to gas-and salt-cooled pebble bed reactors …

Methods for solving the time-dependent neutron diffusion equation for nuclear reactor
analysis are discussed. Techniques for treating the spatial variables, as well as techniques …

This study introduces an unstructured variational nodal method (UVNM-S N), also
recognized as the hybridized discontinuous Galerkin (HDG) method, for solving …

We have applied the black-box paradigm to assembly homogenization and introduced
current discontinuity factors (CDFs) for an arbitrary low-order operator in the presence of …

Griffin is a reactor physics application based on the Multiphysics Object-Oriented Simulation
Environment (MOOSE). This work discloses the methods, algorithms, and implementation for …

Rattlesnake is the MOOSE [1, 2](Multiphysics Object-Oriented Simulation Environment)
based application for simulating the physics of radiation transport. Radiation transport …