CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR
The Monte Carlo (MC) neutron transport analysis for a complex nuclear system such as fusion facility may require accurate modeling of its complicated geometry. In order to take advantage of modeling capability of the computer aided design (CAD) system for the MC neutronics analysis, the Seoul Nation...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
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EDP Sciences
2017-01-01
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| Series: | EPJ Web of Conferences |
| Online Access: | https://doi.org/10.1051/epjconf/201715306019 |
| _version_ | 1818645536031375360 |
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| author | Seo Geon Ho Choi Sung Hoon Shim Hyung Jin |
| author_facet | Seo Geon Ho Choi Sung Hoon Shim Hyung Jin |
| author_sort | Seo Geon Ho |
| collection | DOAJ |
| description | The Monte Carlo (MC) neutron transport analysis for a complex nuclear system such as fusion facility may require accurate modeling of its complicated geometry. In order to take advantage of modeling capability of the computer aided design (CAD) system for the MC neutronics analysis, the Seoul National University MC code, McCARD, has been augmented with a CAD-based geometry processing module by imbedding the OpenCASCADE CAD kernel. In the developed module, the CAD geometry data are internally converted to the constructive solid geometry model with help of the CAD kernel. An efficient cell-searching algorithm is devised for the void space treatment. The performance of the CAD-based McCARD calculations are tested for the Korea Superconducting Tokamak Advanced Research device by comparing with results of the conventional MC calculations using a text-based geometry input. |
| first_indexed | 2024-12-17T00:32:18Z |
| format | Article |
| id | doaj.art-5182d742593d4bb9ad1d10b5392c812d |
| institution | Directory Open Access Journal |
| issn | 2100-014X |
| language | English |
| last_indexed | 2024-12-17T00:32:18Z |
| publishDate | 2017-01-01 |
| publisher | EDP Sciences |
| record_format | Article |
| series | EPJ Web of Conferences |
| spelling | doaj.art-5182d742593d4bb9ad1d10b5392c812d2022-12-21T22:10:14ZengEDP SciencesEPJ Web of Conferences2100-014X2017-01-011530601910.1051/epjconf/201715306019epjconf_icrs2017_06019CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTARSeo Geon HoChoi Sung HoonShim Hyung JinThe Monte Carlo (MC) neutron transport analysis for a complex nuclear system such as fusion facility may require accurate modeling of its complicated geometry. In order to take advantage of modeling capability of the computer aided design (CAD) system for the MC neutronics analysis, the Seoul National University MC code, McCARD, has been augmented with a CAD-based geometry processing module by imbedding the OpenCASCADE CAD kernel. In the developed module, the CAD geometry data are internally converted to the constructive solid geometry model with help of the CAD kernel. An efficient cell-searching algorithm is devised for the void space treatment. The performance of the CAD-based McCARD calculations are tested for the Korea Superconducting Tokamak Advanced Research device by comparing with results of the conventional MC calculations using a text-based geometry input.https://doi.org/10.1051/epjconf/201715306019 |
| spellingShingle | Seo Geon Ho Choi Sung Hoon Shim Hyung Jin CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR EPJ Web of Conferences |
| title | CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR |
| title_full | CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR |
| title_fullStr | CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR |
| title_full_unstemmed | CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR |
| title_short | CAD-Based Monte Carlo Neutron Transport KSTAR Analysis for KSTAR |
| title_sort | cad based monte carlo neutron transport kstar analysis for kstar |
| url | https://doi.org/10.1051/epjconf/201715306019 |
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