ERSN-OpenMC-Py: A python-based open-source software for OpenMC Monte Carlo code
The graphical user interface is a key element in facilitating the use of complex simulation software. This project describes the development of a graphical user interface called “ERSN-OpenMC-Py” for an existing neutron simulation code, OpenMC. The main goal is to make simulation more accessible to a...
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| Vydáno v: | Computer physics communications Ročník 299; s. 109121 |
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| Hlavní autoři: | , , , , , , , , |
| Médium: | Journal Article |
| Jazyk: | angličtina |
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Elsevier B.V
01.06.2024
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| ISSN: | 0010-4655, 1879-2944 |
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| Abstract | The graphical user interface is a key element in facilitating the use of complex simulation software. This project describes the development of a graphical user interface called “ERSN-OpenMC-Py” for an existing neutron simulation code, OpenMC. The main goal is to make simulation more accessible to a wider audience by providing a user-friendly and intuitive user interface. The process of developing the graphical user interface is described in detail, including the different stages of development such as user interface design, user interface implementation, and user interface integration with the OpenMC simulation code. The development tools used, such as Python3 and PyQt5, are also explained. The user interface allows the user to control the simulation parameters and interact with the simulation results. Key features of the user interface include visualization of simulation results, modification of simulation parameters, saving and loading simulation configurations, as well as managing output files. The end result is a functional user interface that allows users to easily visualize simulation results and control simulation parameters in an intuitive manner. This user interface also provides a better user experience for non-programming experts who wish to use the simulation code for their own projects.
Program Title: ERSN-OpenMC-Py, version 1.0
CPC Library link to program files:https://doi.org/10.17632/83xrdht7mz.1
Developer's repository link:https://github.com/mohamedlahdour/ERSN-OpenMC-Py
Licensing provisions: GPLv2
Programming language: Python 3
External routines/libraries: NumPy, Matplotlib, PyQt5
Nature of problem: The program is designed to be utilized in the everyday workflow for tasks such as preparing input files for the OpenMC code and analyzing the resulting calculations.
Solution method: The graphical user interface of the OpenMC is created using PyQt5. Figures are plotted by means of matplotlib library. |
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| AbstractList | The graphical user interface is a key element in facilitating the use of complex simulation software. This project describes the development of a graphical user interface called “ERSN-OpenMC-Py” for an existing neutron simulation code, OpenMC. The main goal is to make simulation more accessible to a wider audience by providing a user-friendly and intuitive user interface. The process of developing the graphical user interface is described in detail, including the different stages of development such as user interface design, user interface implementation, and user interface integration with the OpenMC simulation code. The development tools used, such as Python3 and PyQt5, are also explained. The user interface allows the user to control the simulation parameters and interact with the simulation results. Key features of the user interface include visualization of simulation results, modification of simulation parameters, saving and loading simulation configurations, as well as managing output files. The end result is a functional user interface that allows users to easily visualize simulation results and control simulation parameters in an intuitive manner. This user interface also provides a better user experience for non-programming experts who wish to use the simulation code for their own projects.
Program Title: ERSN-OpenMC-Py, version 1.0
CPC Library link to program files:https://doi.org/10.17632/83xrdht7mz.1
Developer's repository link:https://github.com/mohamedlahdour/ERSN-OpenMC-Py
Licensing provisions: GPLv2
Programming language: Python 3
External routines/libraries: NumPy, Matplotlib, PyQt5
Nature of problem: The program is designed to be utilized in the everyday workflow for tasks such as preparing input files for the OpenMC code and analyzing the resulting calculations.
Solution method: The graphical user interface of the OpenMC is created using PyQt5. Figures are plotted by means of matplotlib library. |
| ArticleNumber | 109121 |
| Author | Lahdour, M. El Maliki El Hlaibi, S. El Hajjaji, O. EL Bakkali, J. Idrissi, Abdelghani Oulad-Belayachi, S. Al-Zain, J. El Bardouni, T. Ziani, H. |
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| Cites_doi | 10.13182/NT11-135 10.1016/j.cpc.2020.107812 |
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| References | Chadwick (br0090) 2011 Goorley (br0120) Dec 2012; 180 Van Rossum (br0060) 2007 EL Bakkali, El Bardouni (br0050) 2016 Lahdour, El Bardouni (br0030) 2019 Archier, Noguère, De Saint Jean, Plompen, Rouki (br0140) 2014 Chadwick (br0130) 2006 Brown (br0100) 2018 Lahdour, El Bardouni (br0010) 2020 Lahdour, El Bardouni (br0020) 2021; 261 Fitzpatrick (br0070) 2020 Forrest, Capote, Otsuka, Kawano, Koning, Kunieda, Sublet, Watanabe (br0150) 2012 Romano (br0040) 2015 br0080 Plompen (br0110) 2020 Forrest (10.1016/j.cpc.2024.109121_br0150) 2012 Fitzpatrick (10.1016/j.cpc.2024.109121_br0070) 2020 Plompen (10.1016/j.cpc.2024.109121_br0110) 2020 EL Bakkali (10.1016/j.cpc.2024.109121_br0050) 2016 Lahdour (10.1016/j.cpc.2024.109121_br0030) 2019 Goorley (10.1016/j.cpc.2024.109121_br0120) 2012; 180 Chadwick (10.1016/j.cpc.2024.109121_br0090) 2011 Brown (10.1016/j.cpc.2024.109121_br0100) 2018 Van Rossum (10.1016/j.cpc.2024.109121_br0060) 2007 Archier (10.1016/j.cpc.2024.109121_br0140) 2014 Romano (10.1016/j.cpc.2024.109121_br0040) 2015 Chadwick (10.1016/j.cpc.2024.109121_br0130) 2006 Lahdour (10.1016/j.cpc.2024.109121_br0020) 2021; 261 Lahdour (10.1016/j.cpc.2024.109121_br0010) 2020 |
| References_xml | – year: 2011 ident: br0090 article-title: ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, vol. 112 publication-title: Special Issue on ENDF/B-VII.1 Library – year: 2019 ident: br0030 article-title: NTP-ERSN: A New Package for Solving the Multigroup Neutron Transport Equation in a Slab Geometry, vol. 145 – start-page: 1 year: 2007 end-page: 36 ident: br0060 article-title: Python programming language publication-title: USENIX Annual Technical Conference, vol. 41 – volume: 180 start-page: 298 year: Dec 2012 end-page: 315 ident: br0120 article-title: Initial MCNP6 release overview publication-title: Nucl. Technol. – volume: 261 year: 2021 ident: br0020 article-title: OpenNTP: implementation of the SN method in Cartesian 2D geometry and the CP method in cylindrical and spherical 1D geometry publication-title: Comput. Phys. Commun. – year: 2012 ident: br0150 article-title: FENDL-3 Library-Summary Documentation – year: 2016 ident: br0050 article-title: ERSN-OpenMC, a Java-Based GUI for OpenMC Monte Carlo Code, vol. 9 – year: 2020 ident: br0110 article-title: The Joint Evaluated Fission and Fusion Nuclear Data Library, JEFF-3.3, vol. 56 – year: 2015 ident: br0040 article-title: OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development, vol. 82 – year: 2014 ident: br0140 article-title: New JEFF-3.2 Sodium Neutron Induced Cross-Sections Evaluation for Neutron Fast Reactors Applications: from 0 to 20 MeV, vol. 118 – year: 2006 ident: br0130 article-title: ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, vol. 107 publication-title: Evaluated Nuclear Data File ENDF/B-VII.0 – year: 2020 ident: br0010 article-title: NTP-ERSN Verification with C5G7 1D Extension Benchmark and GUI Development – ident: br0080 – year: 2018 ident: br0100 article-title: ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data, vol. 148 publication-title: Special Issue on Nuclear Reaction Data – year: 2020 ident: br0070 article-title: Create GUI Applications with Python & Qt5 (PyQt5 Edition): The Hands-on Guide to Making Apps with Python – year: 2018 ident: 10.1016/j.cpc.2024.109121_br0100 article-title: ENDF/B-VIII.0: the 8th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data, vol. 148 – year: 2020 ident: 10.1016/j.cpc.2024.109121_br0070 – year: 2006 ident: 10.1016/j.cpc.2024.109121_br0130 article-title: ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology, vol. 107 – year: 2016 ident: 10.1016/j.cpc.2024.109121_br0050 – year: 2020 ident: 10.1016/j.cpc.2024.109121_br0110 – year: 2015 ident: 10.1016/j.cpc.2024.109121_br0040 – volume: 180 start-page: 298 year: 2012 ident: 10.1016/j.cpc.2024.109121_br0120 article-title: Initial MCNP6 release overview publication-title: Nucl. Technol. doi: 10.13182/NT11-135 – year: 2014 ident: 10.1016/j.cpc.2024.109121_br0140 – year: 2011 ident: 10.1016/j.cpc.2024.109121_br0090 article-title: ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, vol. 112 – year: 2020 ident: 10.1016/j.cpc.2024.109121_br0010 – volume: 261 year: 2021 ident: 10.1016/j.cpc.2024.109121_br0020 article-title: OpenNTP: implementation of the SN method in Cartesian 2D geometry and the CP method in cylindrical and spherical 1D geometry publication-title: Comput. Phys. Commun. doi: 10.1016/j.cpc.2020.107812 – year: 2019 ident: 10.1016/j.cpc.2024.109121_br0030 – start-page: 1 year: 2007 ident: 10.1016/j.cpc.2024.109121_br0060 article-title: Python programming language – year: 2012 ident: 10.1016/j.cpc.2024.109121_br0150 |
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