MOOSE: A parallel computational framework for coupled systems of nonlinear equations

D Gaston, C Newman, G Hansen… - Nuclear Engineering and …, 2009 - Elsevier
Systems of coupled, nonlinear partial differential equations (PDEs) often arise in simulation
of nuclear processes. MOOSE: Multiphysics Object Oriented Simulation Environment, a …

Acceleration of k-Eigenvalue/Criticality Calculations Using the Jacobian-Free Newton-Krylov Method

DA Knoll, H Park, C Newman - Nuclear Science and Engineering, 2011 - Taylor & Francis
We present a new approach for the k-eigenvalue problem using a combination of classical
power iteration and the Jacobian-free Newton-Krylov (JFNK) method. The method poses the …

Tightly coupled multiphysics algorithms for pebble bed reactors

H Park, DA Knoll, DR Gaston… - Nuclear science and …, 2010 - Taylor & Francis
We have developed a tightly coupled multiphysics simulation tool for the pebble bed reactor
(PBR) concept, a specific type of very high temperature gas-cooled reactor. The simulation …

The 3-D time-dependent transport code TORT-TD and its coupling with the 3D thermal-hydraulic code ATTICA3D for HTGR applications

A Seubert, A Sureda, J Bader, J Lapins, M Buck… - … Engineering and Design, 2012 - Elsevier
The application of the time-dependent 3-D discrete-ordinates neutron transport code TORT-
TD to HTGR of pebble bed type and its coupling with the 3-D thermal-hydraulic code …

Development of a fast 3D thermal-hydraulic tool for design and safety studies for HTRS

K Hossain, M Buck, NB Said, W Bernnat… - Nuclear Engineering and …, 2008 - Elsevier
A three-dimensional thermal-hydraulic code called TH3D is being developed at the Institute
of Nuclear Technology and Energy Systems (IKE), University of Stuttgart. The objective of …

Individual pebble temperature peaking factor due to local pebble arrangement in a pebble bed reactor core

V Sobes, B Forget, A Kadak - Nuclear engineering and design, 2011 - Elsevier
Scientists at the German AVR pebble bed nuclear reactor discovered that the surface
temperature of some of the pebbles in the AVR core were at least 200K higher than …

[PDF][PDF] INL results for phases I and III of the OECD/NEA MHTGR-350 benchmark

G Strydom, J Ortensi, S Sen… - Idaho National Laboratory …, 2013 - researchgate.net
ABSTRACT The Idaho National Laboratory (INL) Very High Temperature Reactor (VHTR)
Technology Development Office (TDO) Methods Core Simulation group led the construction …

Parallel algorithms and software for nuclear, energy, and environmental applications. Part II: Multiphysics software

D Gaston, L Guo, G Hansen, H Huang… - Communications in …, 2012 - cambridge.org
This paper is the second part of a two part sequence on multiphysics algorithms and
software. The first [1] focused on the algorithms; this part treats the multiphysics software …

MELCOR Accident Progression and Source Term Demonstration Calculations for a HTGR

K Wagner, B Beeny, D Luxat - 2022 - osti.gov
MELCOR is an integrated thermal hydraulics, accident progression, and source term code
for reactor safety analysis that has been developed at Sandia National Laboratories for the …

An improved porous media approach to thermal–hydraulics analysis of high-temperature gas-cooled reactors

A Nouri-Borujerdi, SIT Ghomsheh - Annals of Nuclear Energy, 2015 - Elsevier
A precise thermal–hydraulics model is of great importance for develo** more effective
designs of High Temperature Gas Cooled Reactors (HTGR). Recently, several …