Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON
This research focuses on the comparative analysis of the PWR fuel assembly based on VERA depletion benchmark problems using community-developed open source Monte Carlo code OpenMC, python based burnup code system ONIX (a coupling interface for Monte Carlo code OpenMC), and deterministic DRAGON code....
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
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Center for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN)
2022-12-01
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| Series: | Atom Indonesia |
| Subjects: | |
| Online Access: | https://aij.batan.go.id/index.php/aij/article/view/1191 |
| _version_ | 1797978428180267008 |
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| author | A. Islam T. A. Rahim A. S. Mollah |
| author_facet | A. Islam T. A. Rahim A. S. Mollah |
| author_sort | A. Islam |
| collection | DOAJ |
| description | This research focuses on the comparative analysis of the PWR fuel assembly based on VERA depletion benchmark problems using community-developed open source Monte Carlo code OpenMC, python based burnup code system ONIX (a coupling interface for Monte Carlo code OpenMC), and deterministic DRAGON code. The depletion analysis was performed using OpenMC and ONIX with ENDF/B-VII.1 nuclear data library, and DRAGON with SHEM-361 based DRAGLIB format library (ENDF/B-VII.1). The code-to-code analysis on the evolution of , atom number density, and power distribution as a function of burnup has been performed and the result shows a good agreement with the maximum difference within 200 pcm at EOC. However small discrepancy around 90 pcm has been observed in calculated by DRAGON compared to OpenMC in the presence of integral fuel burnable absorbers (IFBA). The above-mentioned codes have been validated successfully for the first time against PWR fuel assembly based on VERA depletion benchmark problems. It can be concluded that initial implementation of these codes at the Department of Nuclear Science and Engineering under Military Institute of Science and Technology, Dhaka, was successful and that further research works are to be performed to utilize these codes for depletion/neutronics calculation of existing 3MW TRIGA Mark-II research reactor and VVER-type power reactor that is to be commissioned in Bangladesh. |
| first_indexed | 2024-04-11T05:23:54Z |
| format | Article |
| id | doaj.art-7d3764e9bb444104a82ebbf318f38f17 |
| institution | Directory Open Access Journal |
| issn | 0126-1568 |
| language | English |
| last_indexed | 2024-04-11T05:23:54Z |
| publishDate | 2022-12-01 |
| publisher | Center for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN) |
| record_format | Article |
| series | Atom Indonesia |
| spelling | doaj.art-7d3764e9bb444104a82ebbf318f38f172022-12-23T13:34:59ZengCenter for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN)Atom Indonesia0126-15682022-12-0148319320310.17146/aij.2022.1191496Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGONA. Islam0T. A. Rahim1A. S. Mollah2Department of Nuclear Science and Engineering, Military Institute of Science and Technology (MIST), Dhaka-1216, BangladeshDepartment of Nuclear Science and Engineering, Military Institute of Science and Technology (MIST), Dhaka-1216, BangladeshDepartment of Nuclear Science and Engineering, Military Institute of Science and Technology (MIST), Dhaka-1216, BangladeshThis research focuses on the comparative analysis of the PWR fuel assembly based on VERA depletion benchmark problems using community-developed open source Monte Carlo code OpenMC, python based burnup code system ONIX (a coupling interface for Monte Carlo code OpenMC), and deterministic DRAGON code. The depletion analysis was performed using OpenMC and ONIX with ENDF/B-VII.1 nuclear data library, and DRAGON with SHEM-361 based DRAGLIB format library (ENDF/B-VII.1). The code-to-code analysis on the evolution of , atom number density, and power distribution as a function of burnup has been performed and the result shows a good agreement with the maximum difference within 200 pcm at EOC. However small discrepancy around 90 pcm has been observed in calculated by DRAGON compared to OpenMC in the presence of integral fuel burnable absorbers (IFBA). The above-mentioned codes have been validated successfully for the first time against PWR fuel assembly based on VERA depletion benchmark problems. It can be concluded that initial implementation of these codes at the Department of Nuclear Science and Engineering under Military Institute of Science and Technology, Dhaka, was successful and that further research works are to be performed to utilize these codes for depletion/neutronics calculation of existing 3MW TRIGA Mark-II research reactor and VVER-type power reactor that is to be commissioned in Bangladesh.https://aij.batan.go.id/index.php/aij/article/view/1191vera, depletion, openmc, onix, dragon |
| spellingShingle | A. Islam T. A. Rahim A. S. Mollah Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON Atom Indonesia vera, depletion, openmc, onix, dragon |
| title | Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON |
| title_full | Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON |
| title_fullStr | Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON |
| title_full_unstemmed | Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON |
| title_short | Inter-Code Comparison of Computational VERA Depletion Benchmark Using OpenMC, OpenMC-ONIX and DRAGON |
| title_sort | inter code comparison of computational vera depletion benchmark using openmc openmc onix and dragon |
| topic | vera, depletion, openmc, onix, dragon |
| url | https://aij.batan.go.id/index.php/aij/article/view/1191 |
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