CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100
Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast reactor (LFR) is one of the most promising advanced reactors which are able to meet the safety economic goals of Gen-IV nuclear energy systems. A small modular natural circulation lead cooled fast reactor-...
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| Format: | Article |
| Language: | English |
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Wiley
2016-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2016/9612120 |
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| author | Pengcheng Zhao Kangli Shi Shuzhou Li Jingchao Feng Hongli Chen |
| author_facet | Pengcheng Zhao Kangli Shi Shuzhou Li Jingchao Feng Hongli Chen |
| author_sort | Pengcheng Zhao |
| collection | DOAJ |
| description | Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast reactor (LFR) is one of the most promising advanced reactors which are able to meet the safety economic goals of Gen-IV nuclear energy systems. A small modular natural circulation lead cooled fast reactor-100 MWth (SNRLFR-100) is being developed by University of Science and Technology of China (USTC). In the present work, a 3D CFD model, primary heat exchanger model, fuel pin model, and point kinetic model were established based on some reasonable simplifications and assumptions, the steady-state natural circulation characteristics of SNCLFR-100 primary cooling system were discussed and illustrated, and some reasonable suggestions were proposed for the reactor’s thermal-hydraulic and structural design. Moreover, in order to have a first evaluation of the system behavior in accident conditions, an unprotected loss of heat sink (ULOHS) transient simulation at beginning of the reactor cycle (BOC) has been analyzed and discussed based on the steady-state simulation results. The key temperatures of the reactor core are all under the safety limits at transient state; the reactor has excellent thermal-hydraulic performance. |
| format | Article |
| id | doaj-art-732f045c2cb341129aa0281c05e3edb3 |
| institution | OA Journals |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2016-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-732f045c2cb341129aa0281c05e3edb32025-08-20T02:06:16ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832016-01-01201610.1155/2016/96121209612120CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100Pengcheng Zhao0Kangli Shi1Shuzhou Li2Jingchao Feng3Hongli Chen4School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui 230027, ChinaSchool of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui 230027, ChinaSchool of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui 230027, ChinaSchool of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui 230027, ChinaSchool of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui 230027, ChinaSmall modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast reactor (LFR) is one of the most promising advanced reactors which are able to meet the safety economic goals of Gen-IV nuclear energy systems. A small modular natural circulation lead cooled fast reactor-100 MWth (SNRLFR-100) is being developed by University of Science and Technology of China (USTC). In the present work, a 3D CFD model, primary heat exchanger model, fuel pin model, and point kinetic model were established based on some reasonable simplifications and assumptions, the steady-state natural circulation characteristics of SNCLFR-100 primary cooling system were discussed and illustrated, and some reasonable suggestions were proposed for the reactor’s thermal-hydraulic and structural design. Moreover, in order to have a first evaluation of the system behavior in accident conditions, an unprotected loss of heat sink (ULOHS) transient simulation at beginning of the reactor cycle (BOC) has been analyzed and discussed based on the steady-state simulation results. The key temperatures of the reactor core are all under the safety limits at transient state; the reactor has excellent thermal-hydraulic performance.http://dx.doi.org/10.1155/2016/9612120 |
| spellingShingle | Pengcheng Zhao Kangli Shi Shuzhou Li Jingchao Feng Hongli Chen CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100 Science and Technology of Nuclear Installations |
| title | CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100 |
| title_full | CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100 |
| title_fullStr | CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100 |
| title_full_unstemmed | CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100 |
| title_short | CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100 |
| title_sort | cfd analysis of the primary cooling system for the small modular natural circulation lead cooled fast reactor snrlfr 100 |
| url | http://dx.doi.org/10.1155/2016/9612120 |
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