Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model
The best estimation process of AP1000 Nuclear Power Plant (NPP) requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters. Therefore, it is necessary to identify and evaluate the influences of these parameters and modelin...
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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/10.1155/2017/9304520 |
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| author | Hao Shi Qi Cai Yuqing Chen |
| author_facet | Hao Shi Qi Cai Yuqing Chen |
| author_sort | Hao Shi |
| collection | DOAJ |
| description | The best estimation process of AP1000 Nuclear Power Plant (NPP) requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters. Therefore, it is necessary to identify and evaluate the influences of these parameters and modeling approaches quantitatively and qualitatively. Based on the best estimate thermal-hydraulic system code RELAP5/MOD3.2, sensitivity analysis has been performed on core partition methods, parameters, and model selections in AP1000 Nuclear Power Plant, like the core channel number, pressurizer node number, feedwater temperature, and so forth. The results show that core channel number, core channel node number, and the pressurizer node number have apparent influences on the coolant temperature variation and pressure drop through the reactor. The feedwater temperature is a sensitive factor to the Steam Generator (SG) outlet temperature and the Steam Generator outlet pressure. In addition, the cross-flow model nearly has no effects on the coolant temperature variation and pressure drop in the reactor, in both the steady state and the loss of power transient. Furthermore, some fittest parameters with which the most accurate results could be obtained have been put forward for the nuclear system simulation. |
| format | Article |
| id | doaj-art-a4a64e4526ef4fa19c0386b8bb60b3cd |
| 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-a4a64e4526ef4fa19c0386b8bb60b3cd2025-02-03T05:52:18ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/93045209304520Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation ModelHao Shi0Qi Cai1Yuqing Chen2Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033, ChinaDepartment of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033, ChinaDepartment of Nuclear Science and Engineering, Naval University of Engineering, Wuhan 430033, ChinaThe best estimation process of AP1000 Nuclear Power Plant (NPP) requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters. Therefore, it is necessary to identify and evaluate the influences of these parameters and modeling approaches quantitatively and qualitatively. Based on the best estimate thermal-hydraulic system code RELAP5/MOD3.2, sensitivity analysis has been performed on core partition methods, parameters, and model selections in AP1000 Nuclear Power Plant, like the core channel number, pressurizer node number, feedwater temperature, and so forth. The results show that core channel number, core channel node number, and the pressurizer node number have apparent influences on the coolant temperature variation and pressure drop through the reactor. The feedwater temperature is a sensitive factor to the Steam Generator (SG) outlet temperature and the Steam Generator outlet pressure. In addition, the cross-flow model nearly has no effects on the coolant temperature variation and pressure drop in the reactor, in both the steady state and the loss of power transient. Furthermore, some fittest parameters with which the most accurate results could be obtained have been put forward for the nuclear system simulation.http://dx.doi.org/10.1155/2017/9304520 |
| spellingShingle | Hao Shi Qi Cai Yuqing Chen Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model Science and Technology of Nuclear Installations |
| title | Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model |
| title_full | Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model |
| title_fullStr | Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model |
| title_full_unstemmed | Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model |
| title_short | Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model |
| title_sort | sensitivity evaluation of ap1000 nuclear power plant best estimation model |
| url | http://dx.doi.org/10.1155/2017/9304520 |
| work_keys_str_mv | AT haoshi sensitivityevaluationofap1000nuclearpowerplantbestestimationmodel AT qicai sensitivityevaluationofap1000nuclearpowerplantbestestimationmodel AT yuqingchen sensitivityevaluationofap1000nuclearpowerplantbestestimationmodel |