Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis
This study focused on developing and validating porous model parameters to accurately estimate the thermal behavior of spent nuclear fuel assemblies for computational fluid dynamics simulations. These assemblies are stored in Korean pressurized water reactors (PWRs) under dry storage conditions. Kor...
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| Format: | Article |
| Language: | English |
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Elsevier
2025-02-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573324004601 |
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| author | Do Yun Kim Han-Seop Song Jae-Ho Jeong Seung-Hwan Yu |
| author_facet | Do Yun Kim Han-Seop Song Jae-Ho Jeong Seung-Hwan Yu |
| author_sort | Do Yun Kim |
| collection | DOAJ |
| description | This study focused on developing and validating porous model parameters to accurately estimate the thermal behavior of spent nuclear fuel assemblies for computational fluid dynamics simulations. These assemblies are stored in Korean pressurized water reactors (PWRs) under dry storage conditions. Korean PWR fuel assemblies were categorized into four distinct types based on their configuration, facilitating the calculation of effective thermal conductivities and flow resistance coefficients. These parameters are crucial for simulating heat transfer and determining the peak cladding temperature (PCT), ensuring the thermal safety of stored nuclear fuel. The validation of the proposed porous model against explicit two-dimensional and three-dimensional simulations demonstrated its efficacy and reliability in enhancing the thermal analysis of spent fuel assemblies, highlighting the significance of accurately calculating the porous model parameters in the safety assessment of nuclear fuel storage. Furthermore, the study assessed the sensitivity of variables influencing temperature during spent nuclear fuel storage, focusing on flow resistance coefficients, control rod effect, and basket size. The findings revealed that variations in flow resistance and the presence of control rods minimally impacted PCT, whereas basket size significantly influenced temperature, underscoring its importance in the thermal analysis of nuclear fuel storage systems. |
| format | Article |
| id | doaj-art-1e22a76d15ae458791f4241a3d2a5920 |
| institution | Kabale University |
| issn | 1738-5733 |
| language | English |
| publishDate | 2025-02-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj-art-1e22a76d15ae458791f4241a3d2a59202025-01-31T05:11:08ZengElsevierNuclear Engineering and Technology1738-57332025-02-01572103211Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysisDo Yun Kim0Han-Seop Song1Jae-Ho Jeong2Seung-Hwan Yu3Korea Atomic Energy Research Institute, 111, Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon, 34057, Republic of Korea; Corresponding author.Department of Mechanical Engineering, Gachon University, 1342, Seongnam-daero, Sujeong-gu, Seongnam-si, Gyeonggi-do, Daejeon, Republic of KoreaDepartment of Mechanical Engineering, Gachon University, 1342, Seongnam-daero, Sujeong-gu, Seongnam-si, Gyeonggi-do, Daejeon, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaThis study focused on developing and validating porous model parameters to accurately estimate the thermal behavior of spent nuclear fuel assemblies for computational fluid dynamics simulations. These assemblies are stored in Korean pressurized water reactors (PWRs) under dry storage conditions. Korean PWR fuel assemblies were categorized into four distinct types based on their configuration, facilitating the calculation of effective thermal conductivities and flow resistance coefficients. These parameters are crucial for simulating heat transfer and determining the peak cladding temperature (PCT), ensuring the thermal safety of stored nuclear fuel. The validation of the proposed porous model against explicit two-dimensional and three-dimensional simulations demonstrated its efficacy and reliability in enhancing the thermal analysis of spent fuel assemblies, highlighting the significance of accurately calculating the porous model parameters in the safety assessment of nuclear fuel storage. Furthermore, the study assessed the sensitivity of variables influencing temperature during spent nuclear fuel storage, focusing on flow resistance coefficients, control rod effect, and basket size. The findings revealed that variations in flow resistance and the presence of control rods minimally impacted PCT, whereas basket size significantly influenced temperature, underscoring its importance in the thermal analysis of nuclear fuel storage systems.http://www.sciencedirect.com/science/article/pii/S1738573324004601Spent nuclear fueldry storage systemCFD analysisPorous modelEffective thermal conductivityFlow resistance coefficient |
| spellingShingle | Do Yun Kim Han-Seop Song Jae-Ho Jeong Seung-Hwan Yu Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis Nuclear Engineering and Technology Spent nuclear fuel dry storage system CFD analysis Porous model Effective thermal conductivity Flow resistance coefficient |
| title | Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis |
| title_full | Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis |
| title_fullStr | Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis |
| title_full_unstemmed | Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis |
| title_short | Development of CFD porous model parameters of Korean PWR spent nuclear fuel assemblies for thermal analysis |
| title_sort | development of cfd porous model parameters of korean pwr spent nuclear fuel assemblies for thermal analysis |
| topic | Spent nuclear fuel dry storage system CFD analysis Porous model Effective thermal conductivity Flow resistance coefficient |
| url | http://www.sciencedirect.com/science/article/pii/S1738573324004601 |
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