Development and verification of PWR core transient coupling calculation software
In PWR three-dimensional transient coupling calculation software CORCA-K, the nodal Green's function method and diagonal implicit Runge Kutta method are used to solve the spatiotemporal neutron dynamic diffusion equation, and the single-phase closed channel model and one-dimensional cylindrical...
| Main Authors: | , , , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2021-11-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321002898 |
| _version_ | 1819153595640053760 |
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| author | Zhigang Li Ping An Wenbo Zhao Wei Liu Tao He Wei Lu Qing Li |
| author_facet | Zhigang Li Ping An Wenbo Zhao Wei Liu Tao He Wei Lu Qing Li |
| author_sort | Zhigang Li |
| collection | DOAJ |
| description | In PWR three-dimensional transient coupling calculation software CORCA-K, the nodal Green's function method and diagonal implicit Runge Kutta method are used to solve the spatiotemporal neutron dynamic diffusion equation, and the single-phase closed channel model and one-dimensional cylindrical heat conduction transient model are used to calculate the coolant temperature and fuel temperature. The LMW, NEACRP and PWR MOX/UO2 benchmarks and FangJiaShan (FJS) nuclear power plant (NPP) transient control rod move cases are used to verify the CORCA-K. The effects of burnup, fuel effective temperature and ejection rate on the control rod ejection process of PWR are analyzed. The conclusions are as follows: (1) core relative power and fuel Doppler temperature are in good agreement with the results of benchmark and ADPRES, and the deviation between with the reference results is within 3.0% in LMW and NEACRP benchmarks; 2) the variation trend of FJS NPP core transient parameters is consistent with the results of SMART and ADPRES. And the core relative power is in better agreement with the SMART when weighting coefficient is 0.7. Compared with SMART, the maximum deviation is −5.08% in the rod ejection condition and while −5.09% in the control rod complex movement condition. |
| first_indexed | 2024-12-22T15:07:41Z |
| format | Article |
| id | doaj.art-1920f2a8d3cb4d7690c64cf1a42b1a2f |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-22T15:07:41Z |
| publishDate | 2021-11-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-1920f2a8d3cb4d7690c64cf1a42b1a2f2022-12-21T18:21:56ZengElsevierNuclear Engineering and Technology1738-57332021-11-01531136533664Development and verification of PWR core transient coupling calculation softwareZhigang Li0Ping An1Wenbo Zhao2Wei Liu3Tao He4Wei Lu5Qing Li6Nuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Science and Technology on Reactor System Design Technology Laboratory,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Corresponding author. Nuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China.Nuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Science and Technology on Reactor System Design Technology Laboratory,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, ChinaNuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Science and Technology on Reactor System Design Technology Laboratory,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, ChinaNuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Science and Technology on Reactor System Design Technology Laboratory,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, ChinaNuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Science and Technology on Reactor System Design Technology Laboratory,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, ChinaNuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Science and Technology on Reactor System Design Technology Laboratory,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, ChinaNuclear Power Institute of China,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, China; Science and Technology on Reactor System Design Technology Laboratory,328 Huayang Changshun Avenue Section 1, Shuangliu County, Chengdu City, Sichuan Province, ChinaIn PWR three-dimensional transient coupling calculation software CORCA-K, the nodal Green's function method and diagonal implicit Runge Kutta method are used to solve the spatiotemporal neutron dynamic diffusion equation, and the single-phase closed channel model and one-dimensional cylindrical heat conduction transient model are used to calculate the coolant temperature and fuel temperature. The LMW, NEACRP and PWR MOX/UO2 benchmarks and FangJiaShan (FJS) nuclear power plant (NPP) transient control rod move cases are used to verify the CORCA-K. The effects of burnup, fuel effective temperature and ejection rate on the control rod ejection process of PWR are analyzed. The conclusions are as follows: (1) core relative power and fuel Doppler temperature are in good agreement with the results of benchmark and ADPRES, and the deviation between with the reference results is within 3.0% in LMW and NEACRP benchmarks; 2) the variation trend of FJS NPP core transient parameters is consistent with the results of SMART and ADPRES. And the core relative power is in better agreement with the SMART when weighting coefficient is 0.7. Compared with SMART, the maximum deviation is −5.08% in the rod ejection condition and while −5.09% in the control rod complex movement condition.http://www.sciencedirect.com/science/article/pii/S1738573321002898PWRCore transient coupling calculationRod ejectionFuel effective temperature |
| spellingShingle | Zhigang Li Ping An Wenbo Zhao Wei Liu Tao He Wei Lu Qing Li Development and verification of PWR core transient coupling calculation software Nuclear Engineering and Technology PWR Core transient coupling calculation Rod ejection Fuel effective temperature |
| title | Development and verification of PWR core transient coupling calculation software |
| title_full | Development and verification of PWR core transient coupling calculation software |
| title_fullStr | Development and verification of PWR core transient coupling calculation software |
| title_full_unstemmed | Development and verification of PWR core transient coupling calculation software |
| title_short | Development and verification of PWR core transient coupling calculation software |
| title_sort | development and verification of pwr core transient coupling calculation software |
| topic | PWR Core transient coupling calculation Rod ejection Fuel effective temperature |
| url | http://www.sciencedirect.com/science/article/pii/S1738573321002898 |
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