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ARFC Moltres website migration
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72 changes: 36 additions & 36 deletions doc/content/bib/journal-publications.bib
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@article{park_verification_2022,
title = {Verification of moltres for multiphysics simulations of fast-spectrum molten salt reactors},
volume = {173},
issn = {03064549},
url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454922001463},
doi = {10.1016/j.anucene.2022.109111},
abstract = {Modeling strongly coupled neutronics and thermal–hydraulics in liquid-fueled MSRs requires robust and flexible multiphysics software for accurate simulations at reasonable computational costs. In this paper, we present Moltres and its neutronics and thermal–hydraulics modeling capabilities relevant to multiphysics reactor analysis. As a MOOSE-based application, Moltres provides various multiphysics coupling schemes and time-stepping methods, including fully coupled solves with implicit time-stepping. We verified Moltres’ MSR modeling capabilities against a multiphysics numerical benchmark developed for software dedicated to modeling fast-spectrum MSRs. The results show that Moltres performed comparably to participating software packages in the benchmark; the majority of the relevant quantities fell within one standard deviation of the benchmark average. Among the participating multiphysics tools in the benchmark, Moltres agrees closest to the multiphysics tool from the Delft University of Technology due to similarities in the numerical solution techniques and meshing schemes.},
language = {en},
urldate = {2022-04-26},
journal = {Annals of Nuclear Energy},
author = {Park, Sun Myung and Munk, Madicken},
month = aug,
year = {2022},
pages = {109111},
file = {Park and Munk - 2022 - Verification of moltres for multiphysics simulatio.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\PHNTVU4R\\Park and Munk - 2022 - Verification of moltres for multiphysics simulatio.pdf:application/pdf},
}

@article{lindsay_introduction_2018,
title = {Introduction to {Moltres}: {An} application for simulation of {Molten} {Salt} {Reactors}},
volume = {114},
issn = {0306-4549},
shorttitle = {Introduction to {Moltres}},
url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454917304760},
doi = {10.1016/j.anucene.2017.12.025},
abstract = {Moltres is a new physics application for modeling coupled physics in fluid-fuelled, molten salt reactors. This paper describes its neutronics model, thermal hydraulics model, and their coupling in the MOOSE framework. Neutron and precursor equations are implemented using an action system that allows use of an arbitrary number of groups with no change in the input card. Results for many-channel configurations in 2D-axisymmetric and 3D coordinates are presented and compared against other coupled models as well as the Molten Salt Reactor Experiment.},
language = {en},
urldate = {2018-01-08},
journal = {Annals of Nuclear Energy},
author = {Lindsay, Alexander and Ridley, Gavin and Rykhlevskii, Andrei and Huff, Kathryn},
month = apr,
year = {2018},
keywords = {agent based modeling, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Nuclear fuel cycle, Object orientation, Parallel computing, Reactor physics, repository, Simulation, Systems analysis},
pages = {530--540},
annote = {2d prescribed},
file = {Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\RCWUNGTP\\Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\3GEC6NQ9\\Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;Moltres.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\4XDXRICB\\Moltres.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\Sun Myung\\Zotero\\storage\\E2T9U5IX\\Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\Sun Myung\\Zotero\\storage\\3DT9TEY3\\S0306454917304760.html:text/html},
}

@article{lindsay_moltres_2018,
title = {Moltres: finite element based simulation of molten salt reactors},
Expand Down Expand Up @@ -77,3 +41,39 @@ @article{lindsay_moltres_2018
pages = {1--2},
file = {Full Text PDF:C\:\\Users\\Sun Myung\\Zotero\\storage\\MJIZZW4P\\Lindsay and Huff - 2018 - Moltres finite element based simulation of molten.pdf:application/pdf;Snapshot:C\:\\Users\\Sun Myung\\Zotero\\storage\\E3ARQ46H\\joss.html:text/html},
}

@article{lindsay_introduction_2018,
title = {Introduction to {Moltres}: {An} application for simulation of {Molten} {Salt} {Reactors}},
volume = {114},
issn = {0306-4549},
shorttitle = {Introduction to {Moltres}},
url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454917304760},
doi = {10.1016/j.anucene.2017.12.025},
abstract = {Moltres is a new physics application for modeling coupled physics in fluid-fuelled, molten salt reactors. This paper describes its neutronics model, thermal hydraulics model, and their coupling in the MOOSE framework. Neutron and precursor equations are implemented using an action system that allows use of an arbitrary number of groups with no change in the input card. Results for many-channel configurations in 2D-axisymmetric and 3D coordinates are presented and compared against other coupled models as well as the Molten Salt Reactor Experiment.},
language = {en},
urldate = {2018-01-08},
journal = {Annals of Nuclear Energy},
author = {Lindsay, Alexander and Ridley, Gavin and Rykhlevskii, Andrei and Huff, Kathryn},
month = apr,
year = {2018},
keywords = {Reactor physics, Parallel computing, agent based modeling, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Nuclear fuel cycle, Object orientation, repository, Simulation, Systems analysis},
pages = {530--540},
file = {Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\RCWUNGTP\\Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\3GEC6NQ9\\Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;Moltres.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\4XDXRICB\\Moltres.pdf:application/pdf;ScienceDirect Full Text PDF:C\:\\Users\\Sun Myung\\Zotero\\storage\\E2T9U5IX\\Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;ScienceDirect Snapshot:C\:\\Users\\Sun Myung\\Zotero\\storage\\3DT9TEY3\\S0306454917304760.html:text/html},
}

@article{park_verification_2022,
title = {Verification of moltres for multiphysics simulations of fast-spectrum molten salt reactors},
volume = {173},
issn = {03064549},
url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454922001463},
doi = {10.1016/j.anucene.2022.109111},
abstract = {Modeling strongly coupled neutronics and thermal–hydraulics in liquid-fueled MSRs requires robust and flexible multiphysics software for accurate simulations at reasonable computational costs. In this paper, we present Moltres and its neutronics and thermal–hydraulics modeling capabilities relevant to multiphysics reactor analysis. As a MOOSE-based application, Moltres provides various multiphysics coupling schemes and time-stepping methods, including fully coupled solves with implicit time-stepping. We verified Moltres’ MSR modeling capabilities against a multiphysics numerical benchmark developed for software dedicated to modeling fast-spectrum MSRs. The results show that Moltres performed comparably to participating software packages in the benchmark; the majority of the relevant quantities fell within one standard deviation of the benchmark average. Among the participating multiphysics tools in the benchmark, Moltres agrees closest to the multiphysics tool from the Delft University of Technology due to similarities in the numerical solution techniques and meshing schemes.},
language = {en},
urldate = {2022-04-26},
journal = {Annals of Nuclear Energy},
author = {Park, Sun Myung and Munk, Madicken},
month = aug,
year = {2022},
pages = {109111},
file = {Park and Munk - 2022 - Verification of moltres for multiphysics simulatio.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\PHNTVU4R\\Park and Munk - 2022 - Verification of moltres for multiphysics simulatio.pdf:application/pdf},
}
40 changes: 27 additions & 13 deletions doc/content/bib/theses.bib
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@mastersthesis{park_advancement_2020,
address = {Urbana, IL},
title = {Advancement and {Verification} of {Moltres} for {Molten} {Salt} {Reactor} {Safety} {Analysis}},
copyright = {Copyright 2020 Sun Myung Park},
url = {https://www.ideals.illinois.edu/handle/2142/108542},
language = {English},
school = {University of Illinois at Urbana-Champaign},
author = {Park, Sun Myung},
month = aug,
year = {2020},
file = {Park - 2020 - Advancement and Verification of Moltres for Molten.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\JYYYTBJ7\\Park - 2020 - Advancement and Verification of Moltres for Molten.pdf:application/pdf},
}

@mastersthesis{fairhurst-agosta_multi-physics_2020,
address = {Urbana, IL},
title = {Multi-{Physics} and {Technical} {Analysis} of {High}-{Temperature} {Gas}-{Cooled} {Reactors} for {Hydrogen} {Production}},
Expand Down Expand Up @@ -33,19 +46,6 @@ @mastersthesis{lee_neutronics_2020
file = {Lee - 2020 - Neutronics and Thermal-Hydraulics Analysis of Tran.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\73JPRPQ3\\Lee - 2020 - Neutronics and Thermal-Hydraulics Analysis of Tran.pdf:application/pdf},
}

@mastersthesis{park_advancement_2020,
address = {Urbana, IL},
title = {Advancement and {Verification} of {Moltres} for {Molten} {Salt} {Reactor} {Safety} {Analysis}},
copyright = {Copyright 2020 Sun Myung Park},
url = {https://www.ideals.illinois.edu/handle/2142/108542},
language = {English},
school = {University of Illinois at Urbana-Champaign},
author = {Park, Sun Myung},
month = aug,
year = {2020},
file = {Park - 2020 - Advancement and Verification of Moltres for Molten.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\JYYYTBJ7\\Park - 2020 - Advancement and Verification of Moltres for Molten.pdf:application/pdf},
}

@mastersthesis{pater_multiphysics_2019,
title = {Multiphysics simulations of {Molten} {Salt} {Reactors} using the {Moltres} code},
copyright = {http://creativecommons.org/licenses/by-nc-sa/3.0/es/},
Expand All @@ -61,3 +61,17 @@ @mastersthesis{pater_multiphysics_2019
keywords = {Àrees temàtiques de la UPC::Física, Nuclear engineering--Safety measures, Reactors nuclears -- Mesures de seguretat -- Simulació per ordinador},
file = {Full Text PDF:C\:\\Users\\Sun Myung\\Zotero\\storage\\NWWJN9XA\\Pater - 2019 - Multiphysics simulations of Molten Salt Reactors u.pdf:application/pdf;Snapshot:C\:\\Users\\Sun Myung\\Zotero\\storage\\QZJV3C6Z\\173747.html:text/html},
}

@phdthesis{chee_fluoride-salt-cooled_2022,
address = {Urbana, IL},
type = {Dissertation},
title = {Fluoride-{Salt}-{Cooled} {High} {Temperature} {Reactor} {Design} {Optimization} with {Evolutionary} {Algorithms}},
copyright = {Copyright 2021 Gwendolyn Jin Yi Chee},
url = {https://github.com/arfc/2022-chee-dissertation},
abstract = {Additive manufacturing of reactor core components removes the geometric constraints required by conventional manufacturing, such as slabs as fuel planks and cylinders as fuel rods. Due to the expansion of the potential design space facilitated through additive manufacturing, reactor designers need to find methods, such as generative design, to explore the design space efficiently. In this defense, I will show that I successfully applied evolutionary algorithms to conduct generative reactor design optimization for a fluoride-salt-cooled high-temperature reactor (FHR). I achieved this through three distinct research efforts: 1) furthering our understanding of the FHR design’s complexities through neutronics and temperature modeling, 2) creating an open-source tool that enables generative design reactor optimization with evolutionary algorithms, and 3) applying the tool to the FHR to optimize for non-conventional geometries and fuel distributions},
school = {University of Illinois at Urbana-Champaign},
author = {Chee, Gwendolyn Jin Yi},
month = aug,
year = {2022},
file = {2022-chee-dissertation-pres.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\Y93FYTHR\\2022-chee-dissertation-pres.pdf:application/pdf;Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:C\:\\Users\\Sun Myung\\Zotero\\storage\\EXF7M46A\\Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:application/pdf},
}
7 changes: 7 additions & 0 deletions doc/content/css/moltres.css
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color: var(--uiuc-blue);
font-weight:400;
}

@media (prefers-color-scheme: dark), (prefers-dark-interface) {
.dropdown-content li > a, .dropdown-content li > span {
background-color: var(--darkmode-navigator);
color: var(--darkmode-fore);
}
}
29 changes: 29 additions & 0 deletions doc/content/getting_started/eigenvalue.md
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# Eigenvalue Calculation with NtAction

The input files associated with this tutorial are
[moltres/tutorial/eigenvalue/nts.i](https://github.com/arfc/moltres/blob/devel/tutorial/eigenvalue/nts.i) and
[moltres/tutorial/eigenvalue/nts-action.i](https://github.com/arfc/moltres/blob/devel/tutorial/eigenvalue/nts-action.i).
Refer to [Tutorial 2a](getting_started/input_syntax.md) for an introduction on the input file
syntax and in-depth descriptions of every input parameter.

As mentioned in Tutorial 2a, this example involves a simple 2-D axisymmetric core model of the
Molten Salt Reactor Experiment (MSRE) that was developed at Oak Ridge National Laboratory. The
figure below shows the 2-D MSRE model for this tutorial. It is a 70.8 cm by 169 cm rectangle that
is axisymmetric about the left boundary. The domain consists of 14 fuel channels, alternating with
14 solid graphite moderator regions, represented in the figure by gray and red rectangles,
respectively.

!media media/msre_2d.png
id=msre-2d
caption=2-D axisymmetric model of the MSRE
style=width:35%;text-align:center;margin-left:auto;margin-right:auto;

For multiplication factor ($k$) eigenvalue calculations, Moltres relies on the
`InversePowerMethod` or `NonlinearEigen` executioners from MOOSE. These executioners solve the
neutron diffusion equations set up as an eigenvalue problem to find $k$ and the neutron flux
distribution, which occur as the absolute minimum eigenvalue $1/k$ and the corresponding
eigenvector of the system. The mathematical background and documentation for these executioners can
be found [here](https://mooseframework.inl.gov/source/executioners/InversePowerMethod.html). This
tutorial uses the `InversePowerMethod` executioner which applies the inverse power method.


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