Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor
The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PWR) may suffer serious thermal shock caused by cold water from reactor Safety Injection System (SIS) in some unexpected accident scenarios. It implies the formation of great temperature gradient on the...
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| Format: | Article |
| Language: | English |
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Wiley
2017-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2017/2960412 |
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| author | Mingjun Wang Qiaolin Zuo Hao Yu Wenxi Tian G. H. Su Suizheng Qiu |
| author_facet | Mingjun Wang Qiaolin Zuo Hao Yu Wenxi Tian G. H. Su Suizheng Qiu |
| author_sort | Mingjun Wang |
| collection | DOAJ |
| description | The Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PWR) may suffer serious thermal shock caused by cold water from reactor Safety Injection System (SIS) in some unexpected accident scenarios. It implies the formation of great temperature gradient on the inlet nozzles and RPV wall, leading to the localized stresses and propagation of possible flaws that appeared in the material. In this paper, the multiscale thermal hydraulic analysis was performed for Chashma Nuclear Power Plant (NPP) under the inadvertent SIS operation scenario. The primary loop and SIS were modeled using one-dimensional method, while the three-dimensional models of reactor cold leg, RPV inlet nozzles, and downcomer were established. Then, the inadvertent Safety Injection System operation scenario was simulated using RELAP5 code, providing the boundary conditions for three-dimensional Computational Fluid Dynamics (CFD) analysis. The fluid and solid coupling heat transfer simulation method was employed. Results show that the maximum temperature difference was about 80 K in the most conservative condition and the RPV inlet nozzle region was the most critical region during the accident. This work could provide in-depth understanding on the effect of cold coolant injection along the main pipes and RPV wall during the accident scenario. |
| format | Article |
| id | doaj-art-b5e459d0f3f74113b63c3a269ea3d81e |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2017-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-b5e459d0f3f74113b63c3a269ea3d81e2025-02-03T01:26:33ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/29604122960412Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water ReactorMingjun Wang0Qiaolin Zuo1Hao Yu2Wenxi Tian3G. H. Su4Suizheng Qiu5Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, ChinaDepartment of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, ChinaDepartment of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, ChinaDepartment of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, ChinaDepartment of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, ChinaDepartment of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, ChinaThe Reactor Pressure Vessel (RPV) inlet nozzles and downcomer wall in Pressurized Water Reactors (PWR) may suffer serious thermal shock caused by cold water from reactor Safety Injection System (SIS) in some unexpected accident scenarios. It implies the formation of great temperature gradient on the inlet nozzles and RPV wall, leading to the localized stresses and propagation of possible flaws that appeared in the material. In this paper, the multiscale thermal hydraulic analysis was performed for Chashma Nuclear Power Plant (NPP) under the inadvertent SIS operation scenario. The primary loop and SIS were modeled using one-dimensional method, while the three-dimensional models of reactor cold leg, RPV inlet nozzles, and downcomer were established. Then, the inadvertent Safety Injection System operation scenario was simulated using RELAP5 code, providing the boundary conditions for three-dimensional Computational Fluid Dynamics (CFD) analysis. The fluid and solid coupling heat transfer simulation method was employed. Results show that the maximum temperature difference was about 80 K in the most conservative condition and the RPV inlet nozzle region was the most critical region during the accident. This work could provide in-depth understanding on the effect of cold coolant injection along the main pipes and RPV wall during the accident scenario.http://dx.doi.org/10.1155/2017/2960412 |
| spellingShingle | Mingjun Wang Qiaolin Zuo Hao Yu Wenxi Tian G. H. Su Suizheng Qiu Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor Science and Technology of Nuclear Installations |
| title | Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor |
| title_full | Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor |
| title_fullStr | Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor |
| title_full_unstemmed | Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor |
| title_short | Multiscale Thermal Hydraulic Study under the Inadvertent Safety Injection System Operation Scenario of Typical Pressurized Water Reactor |
| title_sort | multiscale thermal hydraulic study under the inadvertent safety injection system operation scenario of typical pressurized water reactor |
| url | http://dx.doi.org/10.1155/2017/2960412 |
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