Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR
When the large pressurized water reactor in-vessel retention (IVR) system is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at the same time. In order to ensure the structural in...
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| Format: | Article |
| Language: | English |
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Frontiers Media S.A.
2022-05-01
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| Series: | Frontiers in Energy Research |
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| Online Access: | https://www.frontiersin.org/articles/10.3389/fenrg.2022.899405/full |
| _version_ | 1817990861802176512 |
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| author | Dahuan Zhu Hongping Sun Bin Zheng Tao Huang Jian Deng Youyou Xu Yuejian Luo |
| author_facet | Dahuan Zhu Hongping Sun Bin Zheng Tao Huang Jian Deng Youyou Xu Yuejian Luo |
| author_sort | Dahuan Zhu |
| collection | DOAJ |
| description | When the large pressurized water reactor in-vessel retention (IVR) system is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at the same time. In order to ensure the structural integrity of the RPV under such conditions, first, through the severe accident system program, the case that has the greatest impact on the pressure-bearing thermal shock of the outer wall of the reactor pressure vessel was selected under the station blackout (SBO) accident. Then, based on this case, the fracture mechanics finite element method was used to calculate and evaluate the pressure thermal shock (PTS) of the RPV, and the final crack size at the end of the life of the core barrel and the lower head was obtained by fatigue crack expansion calculation. The maximum ratio of the stress intensity factor correction value and corresponding limit value under the PTS transient load is about 0.874, which meets the requirements of RCC-M specification. The results of the study indicate that the RPV will not experience fracture failure when the IVR system is put into service during the station blackout accident for the HPR1000 nuclear power plant. |
| first_indexed | 2024-04-14T01:05:37Z |
| format | Article |
| id | doaj.art-a0256da3b3e5409383c0023d154c3f39 |
| institution | Directory Open Access Journal |
| issn | 2296-598X |
| language | English |
| last_indexed | 2024-04-14T01:05:37Z |
| publishDate | 2022-05-01 |
| publisher | Frontiers Media S.A. |
| record_format | Article |
| series | Frontiers in Energy Research |
| spelling | doaj.art-a0256da3b3e5409383c0023d154c3f392022-12-22T02:21:16ZengFrontiers Media S.A.Frontiers in Energy Research2296-598X2022-05-011010.3389/fenrg.2022.899405899405Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWRDahuan ZhuHongping SunBin ZhengTao HuangJian DengYouyou XuYuejian LuoWhen the large pressurized water reactor in-vessel retention (IVR) system is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at the same time. In order to ensure the structural integrity of the RPV under such conditions, first, through the severe accident system program, the case that has the greatest impact on the pressure-bearing thermal shock of the outer wall of the reactor pressure vessel was selected under the station blackout (SBO) accident. Then, based on this case, the fracture mechanics finite element method was used to calculate and evaluate the pressure thermal shock (PTS) of the RPV, and the final crack size at the end of the life of the core barrel and the lower head was obtained by fatigue crack expansion calculation. The maximum ratio of the stress intensity factor correction value and corresponding limit value under the PTS transient load is about 0.874, which meets the requirements of RCC-M specification. The results of the study indicate that the RPV will not experience fracture failure when the IVR system is put into service during the station blackout accident for the HPR1000 nuclear power plant.https://www.frontiersin.org/articles/10.3389/fenrg.2022.899405/fullin-vessel retention systempressure vesselpressurized thermal shockfracture mechanicsadvanced PWR |
| spellingShingle | Dahuan Zhu Hongping Sun Bin Zheng Tao Huang Jian Deng Youyou Xu Yuejian Luo Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR Frontiers in Energy Research in-vessel retention system pressure vessel pressurized thermal shock fracture mechanics advanced PWR |
| title | Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR |
| title_full | Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR |
| title_fullStr | Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR |
| title_full_unstemmed | Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR |
| title_short | Study on Thermal Shock Failure Characteristics of RPV During IVR System Start-Up for Typical Advanced PWR |
| title_sort | study on thermal shock failure characteristics of rpv during ivr system start up for typical advanced pwr |
| topic | in-vessel retention system pressure vessel pressurized thermal shock fracture mechanics advanced PWR |
| url | https://www.frontiersin.org/articles/10.3389/fenrg.2022.899405/full |
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