[HTML][HTML] Variational nodal methods for neutron transport: 40 years in review

T Zhang, Z Li - Nuclear Engineering and Technology, 2022 - Elsevier
The variational nodal method for solving the neutron transport equation has evolved over 40
years. Based on a functional form of the Boltzmann neutron transport equation, the method …

Coupled multiphysics simulations of heat pipe microreactors using DireWolf

C Matthews, V Laboure, M DeHart, J Hansel… - Nuclear …, 2021 - Taylor & Francis
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 …

[HTML][HTML] Griffin: A MOOSE-based reactor physics application for multiphysics simulation of advanced nuclear reactors

Y Wang, ZM Prince, H Park, OW Calvin, N Choi… - Annals of Nuclear …, 2025 - Elsevier
Abstract Griffin is a Multiphysics Object-Oriented Simulation Environment (MOOSE) based
reactor physics application for multiphysics simulations of advanced reactor designs jointly …

Automated power-following control for nuclear thermal propulsion startup and shutdown using MOOSE-based applications

VM Labouré, S Schunert, S Terlizzi, ZM Prince… - Progress in Nuclear …, 2023 - Elsevier
This paper describes an investigation of various automated control strategies applied to a
full-core multiphysics Griffin/Bison/RELAP-7 model of a prototypical nuclear thermal …

VITAS: a multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods

T Zhang, W **ao, H Yin, Q Sun, X Liu - Annals of Nuclear Energy, 2022 - Elsevier
Existing neutronic whole-core simulation codes are problem-oriented. With the
advancement of computer technology and the development of complicated micro-nuclear …

A discrete-ordinates variational nodal method for heterogeneous neutron Boltzmann transport problems

Q Sun, X Liu, X Chai, H He, T Zhang - Computers & Mathematics with …, 2024 - Elsevier
This study introduces an unstructured variational nodal method (UVNM-S N), also
recognized as the hybridized discontinuous Galerkin (HDG) method, for solving …

Cardinal: A lower-length-scale multiphysics simulator for pebble-bed reactors

E Merzari, H Yuan, M Min, D Shaver… - Nuclear …, 2021 - Taylor & Francis
This paper demonstrates a multiphysics solver for pebble-bed reactors, in particular, for
Berkeley's pebble-bed-fluoride-salt-cooled high-temperature reactor (PB-FHR)(Mark I …

Asymptotic hydrogen redistribution analysis in yttrium-hydride-moderated heat-pipe-cooled microreactors using DireWolf

S Terlizzi, V Labouré - Annals of Nuclear Energy, 2023 - Elsevier
Yttrium hydride (YH x) is one of the materials being considered for moderating thermal and
epithermal nuclear microreactors. One potential issue with YH x use is that the hydrogen …

A multiphysics model of the versatile test reactor based on the MOOSE framework

N Martin, R Stewart, S Bays - Annals of Nuclear Energy, 2022 - Elsevier
The traditional modeling approach for sodium fast reactor cores relies on separate physics
models, where the fuel performance, thermal–hydraulics, and neutronics calculations …

[HTML][HTML] An equilibrium core depletion algorithm for pebble-bed reactors in the Griffin code

S Schunert, J Ortensi, Y Wang, P Balestra… - Annals of Nuclear …, 2023 - Elsevier
We present a novel deterministic equilibrium core pebble-bed depletion algorithm. It differs
from most other algorithms by distinguishing pebble age directly by burnup instead of using …