Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR
Lead-cooled fast reactor (LFR) has been an important option for floating nuclear power plant. The design of 50 MW natural circulation LFR had been proposed by Lanzhou University for floating nuclear power plant. However, floating nuclear power plant was affected by the marine environment, which led...
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Frontiers Media S.A.
2025-05-01
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| Series: | Frontiers in Energy Research |
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| Online Access: | https://www.frontiersin.org/articles/10.3389/fenrg.2025.1566271/full |
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| author | Jinting Liu Jinting Liu Tingyu Li Tingyu Li Tingyu Li Yang Li Yang Li Yang Li Danna Zhou Danna Zhou Danna Zhou Dajian Yu Dajian Yu Dajian Yu |
| author_facet | Jinting Liu Jinting Liu Tingyu Li Tingyu Li Tingyu Li Yang Li Yang Li Yang Li Danna Zhou Danna Zhou Danna Zhou Dajian Yu Dajian Yu Dajian Yu |
| author_sort | Jinting Liu |
| collection | DOAJ |
| description | Lead-cooled fast reactor (LFR) has been an important option for floating nuclear power plant. The design of 50 MW natural circulation LFR had been proposed by Lanzhou University for floating nuclear power plant. However, floating nuclear power plant was affected by the marine environment, which led to safety problems in reactor under inclined condition. To analyze the impact of different heat exchangers configuration and inclination angle on the thermal-hydraulic safety performance of the reactor, this study utilized RELAP5 software and established a thermal-hydraulic model of the 50 MW natural circulation LFR. The results indicated that the core flow rate reduced to 95.12% of the flow rate at 100%FP power, when the inclination angle was 30°. When the angle between the heat exchanger and the central axis of floating nuclear power plant is 45°, the maximum outlet temperature difference in the heat exchanger is 1.86K. During the process of power increasing and decreasing, the reactor power was increased with rates of 0.5% FP/min, and the core cladding temperature was increased to the maximum 938.42K. This study provided technical reference for the design of natural circulation lead-cooled fast reactors in floating nuclear power plant. |
| format | Article |
| id | doaj-art-aba041748aad42e9b2cca863c2043926 |
| institution | Kabale University |
| issn | 2296-598X |
| language | English |
| publishDate | 2025-05-01 |
| publisher | Frontiers Media S.A. |
| record_format | Article |
| series | Frontiers in Energy Research |
| spelling | doaj-art-aba041748aad42e9b2cca863c20439262025-08-20T03:51:58ZengFrontiers Media S.A.Frontiers in Energy Research2296-598X2025-05-011310.3389/fenrg.2025.15662711566271Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFRJinting Liu0Jinting Liu1Tingyu Li2Tingyu Li3Tingyu Li4Yang Li5Yang Li6Yang Li7Danna Zhou8Danna Zhou9Danna Zhou10Dajian Yu11Dajian Yu12Dajian Yu13University of Science and Technology of China, Hefei, ChinaHefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei, ChinaShandong Key Laboratory of Neutron Science and Technology, Qingdao, ChinaInstitute of Neutron Energy Co. Ltd., Qingdao, ChinaQingdao Key Laboratory of Neutron Energy Technology, Qingdao, ChinaInstitute of Neutron Energy Co. Ltd., Qingdao, ChinaQingdao Key Laboratory of Neutron Energy Technology, Qingdao, ChinaInternational Academy of Neutron Science, Qingdao, ChinaInstitute of Neutron Energy Co. Ltd., Qingdao, ChinaQingdao Key Laboratory of Neutron Energy Technology, Qingdao, ChinaInternational Academy of Neutron Science, Qingdao, ChinaShandong Key Laboratory of Neutron Science and Technology, Qingdao, ChinaInstitute of Neutron Energy Co. Ltd., Qingdao, ChinaQingdao Key Laboratory of Neutron Energy Technology, Qingdao, ChinaLead-cooled fast reactor (LFR) has been an important option for floating nuclear power plant. The design of 50 MW natural circulation LFR had been proposed by Lanzhou University for floating nuclear power plant. However, floating nuclear power plant was affected by the marine environment, which led to safety problems in reactor under inclined condition. To analyze the impact of different heat exchangers configuration and inclination angle on the thermal-hydraulic safety performance of the reactor, this study utilized RELAP5 software and established a thermal-hydraulic model of the 50 MW natural circulation LFR. The results indicated that the core flow rate reduced to 95.12% of the flow rate at 100%FP power, when the inclination angle was 30°. When the angle between the heat exchanger and the central axis of floating nuclear power plant is 45°, the maximum outlet temperature difference in the heat exchanger is 1.86K. During the process of power increasing and decreasing, the reactor power was increased with rates of 0.5% FP/min, and the core cladding temperature was increased to the maximum 938.42K. This study provided technical reference for the design of natural circulation lead-cooled fast reactors in floating nuclear power plant.https://www.frontiersin.org/articles/10.3389/fenrg.2025.1566271/fulllead-cooled fast reactornatural circulationinclined conditionRELAP5thermal-hydraulic safety characteristics |
| spellingShingle | Jinting Liu Jinting Liu Tingyu Li Tingyu Li Tingyu Li Yang Li Yang Li Yang Li Danna Zhou Danna Zhou Danna Zhou Dajian Yu Dajian Yu Dajian Yu Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR Frontiers in Energy Research lead-cooled fast reactor natural circulation inclined condition RELAP5 thermal-hydraulic safety characteristics |
| title | Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR |
| title_full | Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR |
| title_fullStr | Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR |
| title_full_unstemmed | Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR |
| title_short | Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR |
| title_sort | thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on lfr |
| topic | lead-cooled fast reactor natural circulation inclined condition RELAP5 thermal-hydraulic safety characteristics |
| url | https://www.frontiersin.org/articles/10.3389/fenrg.2025.1566271/full |
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