Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer
Abstracts: The research on the flow and heat transfer characteristics of lead bismuth(LBE) is significant for the thermal-hydraulic calculation, safety analysis and practical application of lead-based fast reactors(LFR). In this paper, a new CFD model is proposed to solve the thermal-hydraulic analy...
| Main Authors: | , , , , , , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2022-07-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573322000614 |
| _version_ | 1818535987693748224 |
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| author | Jie Liu Ping Song Dalin Zhang Shibao Wang Chao Lin Yapeng Liu Lei Zhou Chenglong Wang Wenxi Tian Suizheng Qiu G.H. Su |
| author_facet | Jie Liu Ping Song Dalin Zhang Shibao Wang Chao Lin Yapeng Liu Lei Zhou Chenglong Wang Wenxi Tian Suizheng Qiu G.H. Su |
| author_sort | Jie Liu |
| collection | DOAJ |
| description | Abstracts: The research on the flow and heat transfer characteristics of lead bismuth(LBE) is significant for the thermal-hydraulic calculation, safety analysis and practical application of lead-based fast reactors(LFR). In this paper, a new CFD model is proposed to solve the thermal-hydraulic analysis of LBE. The model includes two parts: turbulent model and turbulent Prandtl, which are the important factors for LBE. In order to find the best model, the experiment data and design of 19-pin hexagonal rod bundle with spacer grid, undertaken at the Karlsruhe Liquid Metal Laboratory (KALLA) are used for CFD calculation. Furthermore, the turbulent model includes SST k−ω and k−ε; the turbulent Prandtl includes Cheng-Tak and constant (Prt =1.5,2.0,2.5,3.0). Among them, the combination between SST k−ω and Cheng-Tak is more suitable for the experiment. But in the low Pe region, the deviation between the experiment data and CFD result is too much. The reason may be the inlet-effect and when Pe is in a low level, the number of molecular thermal diffusion occupies an absolute advantage, and the buoyancy will enhance. In order to test and verify versatility of the model, the NCCL performed by the Nuclear Thermal-hydraulic Laboratory (Nuthel) of Xi'an Jiao tong University is used for CFD to calculate. This paper provides two verification examples for the new universal model. |
| first_indexed | 2024-12-11T18:32:11Z |
| format | Article |
| id | doaj.art-028c66e0755a404785dd56a042a5a528 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-11T18:32:11Z |
| publishDate | 2022-07-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-028c66e0755a404785dd56a042a5a5282022-12-22T00:54:52ZengElsevierNuclear Engineering and Technology1738-57332022-07-0154727282735Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacerJie Liu0Ping Song1Dalin Zhang2Shibao Wang3Chao Lin4Yapeng Liu5Lei Zhou6Chenglong Wang7Wenxi Tian8Suizheng Qiu9G.H. Su10State Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaScience and Technology on Thermal Energy and Power Laboratory, Wuhan Second Ship Design and Research Institute, Wuhan 430205, Hubei, PR ChinaState Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR China; Corresponding author.State Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaChina Institute of Atomic Energy, Beijing 102413, PR ChinaState Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaState Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaState Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaState Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaState Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaState Key Laboratory of Multiphase Flow in Power Engineering, Shaanxi Key Lab. of Advanced Nuclear Energy and Technology, Department of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an, Shaanxi, 710049, PR ChinaAbstracts: The research on the flow and heat transfer characteristics of lead bismuth(LBE) is significant for the thermal-hydraulic calculation, safety analysis and practical application of lead-based fast reactors(LFR). In this paper, a new CFD model is proposed to solve the thermal-hydraulic analysis of LBE. The model includes two parts: turbulent model and turbulent Prandtl, which are the important factors for LBE. In order to find the best model, the experiment data and design of 19-pin hexagonal rod bundle with spacer grid, undertaken at the Karlsruhe Liquid Metal Laboratory (KALLA) are used for CFD calculation. Furthermore, the turbulent model includes SST k−ω and k−ε; the turbulent Prandtl includes Cheng-Tak and constant (Prt =1.5,2.0,2.5,3.0). Among them, the combination between SST k−ω and Cheng-Tak is more suitable for the experiment. But in the low Pe region, the deviation between the experiment data and CFD result is too much. The reason may be the inlet-effect and when Pe is in a low level, the number of molecular thermal diffusion occupies an absolute advantage, and the buoyancy will enhance. In order to test and verify versatility of the model, the NCCL performed by the Nuclear Thermal-hydraulic Laboratory (Nuthel) of Xi'an Jiao tong University is used for CFD to calculate. This paper provides two verification examples for the new universal model.http://www.sciencedirect.com/science/article/pii/S1738573322000614LBETurbulent modelTurbulent Prandtl number19-pin hexagonal rod bundle with spacer gridCircular tubes |
| spellingShingle | Jie Liu Ping Song Dalin Zhang Shibao Wang Chao Lin Yapeng Liu Lei Zhou Chenglong Wang Wenxi Tian Suizheng Qiu G.H. Su Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer Nuclear Engineering and Technology LBE Turbulent model Turbulent Prandtl number 19-pin hexagonal rod bundle with spacer grid Circular tubes |
| title | Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer |
| title_full | Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer |
| title_fullStr | Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer |
| title_full_unstemmed | Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer |
| title_short | Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer |
| title_sort | thermal hydraulic research on rod bundle in the lbe fast reactor with grid spacer |
| topic | LBE Turbulent model Turbulent Prandtl number 19-pin hexagonal rod bundle with spacer grid Circular tubes |
| url | http://www.sciencedirect.com/science/article/pii/S1738573322000614 |
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