CEFR control rod drop transient simulation using RAST-F code system
This study aimed to verify and validate the transient simulation capability of the hybrid code system RAST-F for fast reactor analysis. For this purpose, control rod (CR) drop experiments involving eight separate CRs and six CR groups in the China Experimental Fast Reactor (CEFR) start-up tests were...
| Main Authors: | , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2023-12-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573323003790 |
| _version_ | 1797448130011070464 |
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| author | Tuan Quoc Tran Xingkai Huo Emil Fridman Deokjung Lee |
| author_facet | Tuan Quoc Tran Xingkai Huo Emil Fridman Deokjung Lee |
| author_sort | Tuan Quoc Tran |
| collection | DOAJ |
| description | This study aimed to verify and validate the transient simulation capability of the hybrid code system RAST-F for fast reactor analysis. For this purpose, control rod (CR) drop experiments involving eight separate CRs and six CR groups in the China Experimental Fast Reactor (CEFR) start-up tests were utilized to simulate the CR drop transient. The RAST-F numerical solution, including the neutron population, time-dependent reactivity, and CR worth, was compared against the measurement values obtained from two out-of-core detectors. Moreover, the time-dependent reactivity and CR worth from RAST-F were verified against the results obtained by the Monte Carlo code Serpent using continuous energy nuclear data. A code-to-code comparison between Serpent and RAST-F showed good agreement in terms of time-dependent reactivity and CR worth. The discrepancy was less than 160 pcm for reactivity and less than 110 pcm for CR worth. RAST-F solution was almost identical to the measurement data in terms of neutron population and reactivity. All the calculated CR worth results agreed with experimental results within two standard deviations of experimental uncertainty for all CRs and CR groups. This work demonstrates that the RAST-F code system can be a potential tool for analyzing time-dependent phenomena in fast reactors. |
| first_indexed | 2024-03-09T14:06:01Z |
| format | Article |
| id | doaj.art-8dbec5d7853444bca4c05103a7ec0e03 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-03-09T14:06:01Z |
| publishDate | 2023-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-8dbec5d7853444bca4c05103a7ec0e032023-11-30T05:06:20ZengElsevierNuclear Engineering and Technology1738-57332023-12-01551244914503CEFR control rod drop transient simulation using RAST-F code systemTuan Quoc Tran0Xingkai Huo1Emil Fridman2Deokjung Lee3Department of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, Republic of KoreaChina Institute of Atomic Energy, POB 275(95), Beijing, 102413, ChinaHelmholtz-Zentrum Dresden-Rossendorf, Bautzner Landstraße 400, 01328, Dresden, GermanyDepartment of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, Republic of Korea; Advanced Nuclear Technology and Services, 406-21 Jonga-ro, Jung-gu, Ulsan, 44429, Republic of Korea; Corresponding author. Department of Nuclear Engineering, Ulsan National Institute of Science and Technology, 50 UNIST-gil, Ulsan, 44919, Republic of Korea.This study aimed to verify and validate the transient simulation capability of the hybrid code system RAST-F for fast reactor analysis. For this purpose, control rod (CR) drop experiments involving eight separate CRs and six CR groups in the China Experimental Fast Reactor (CEFR) start-up tests were utilized to simulate the CR drop transient. The RAST-F numerical solution, including the neutron population, time-dependent reactivity, and CR worth, was compared against the measurement values obtained from two out-of-core detectors. Moreover, the time-dependent reactivity and CR worth from RAST-F were verified against the results obtained by the Monte Carlo code Serpent using continuous energy nuclear data. A code-to-code comparison between Serpent and RAST-F showed good agreement in terms of time-dependent reactivity and CR worth. The discrepancy was less than 160 pcm for reactivity and less than 110 pcm for CR worth. RAST-F solution was almost identical to the measurement data in terms of neutron population and reactivity. All the calculated CR worth results agreed with experimental results within two standard deviations of experimental uncertainty for all CRs and CR groups. This work demonstrates that the RAST-F code system can be a potential tool for analyzing time-dependent phenomena in fast reactors.http://www.sciencedirect.com/science/article/pii/S1738573323003790CEFRRAST-FTransientNodal diffusion codeSerpent |
| spellingShingle | Tuan Quoc Tran Xingkai Huo Emil Fridman Deokjung Lee CEFR control rod drop transient simulation using RAST-F code system Nuclear Engineering and Technology CEFR RAST-F Transient Nodal diffusion code Serpent |
| title | CEFR control rod drop transient simulation using RAST-F code system |
| title_full | CEFR control rod drop transient simulation using RAST-F code system |
| title_fullStr | CEFR control rod drop transient simulation using RAST-F code system |
| title_full_unstemmed | CEFR control rod drop transient simulation using RAST-F code system |
| title_short | CEFR control rod drop transient simulation using RAST-F code system |
| title_sort | cefr control rod drop transient simulation using rast f code system |
| topic | CEFR RAST-F Transient Nodal diffusion code Serpent |
| url | http://www.sciencedirect.com/science/article/pii/S1738573323003790 |
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