[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 …
years. Based on a functional form of the Boltzmann neutron transport equation, the method …
Coupled multiphysics simulations of heat pipe microreactors using DireWolf
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 …
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
Abstract Griffin is a Multiphysics Object-Oriented Simulation Environment (MOOSE) based
reactor physics application for multiphysics simulations of advanced reactor designs jointly …
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
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 …
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
Existing neutronic whole-core simulation codes are problem-oriented. With the
advancement of computer technology and the development of complicated micro-nuclear …
advancement of computer technology and the development of complicated micro-nuclear …
A discrete-ordinates variational nodal method for heterogeneous neutron Boltzmann transport problems
This study introduces an unstructured variational nodal method (UVNM-S N), also
recognized as the hybridized discontinuous Galerkin (HDG) method, for solving …
recognized as the hybridized discontinuous Galerkin (HDG) method, for solving …
Cardinal: A lower-length-scale multiphysics simulator for pebble-bed reactors
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 …
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
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 …
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
The traditional modeling approach for sodium fast reactor cores relies on separate physics
models, where the fuel performance, thermal–hydraulics, and neutronics calculations …
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
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 …
from most other algorithms by distinguishing pebble age directly by burnup instead of using …