Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method
To study the influence of parameter uncertainty in small pressurized water reactor (SPWR) once-through steam generator (OTSG), the nonlinear mathematical model of the SPWR is firstly established. Including the reactor core model, the OTSG model and the pressurizer model. Secondly, a control strategy...
| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2023-07-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573323001420 |
| _version_ | 1827918592913440768 |
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| author | Lekang Chen Chuqi Chen Linna Wang Wenjie Zeng Zhifeng Li |
| author_facet | Lekang Chen Chuqi Chen Linna Wang Wenjie Zeng Zhifeng Li |
| author_sort | Lekang Chen |
| collection | DOAJ |
| description | To study the influence of parameter uncertainty in small pressurized water reactor (SPWR) once-through steam generator (OTSG), the nonlinear mathematical model of the SPWR is firstly established. Including the reactor core model, the OTSG model and the pressurizer model. Secondly, a control strategy that both the reactor core coolant average temperature and the secondary-side outlet pressure of the OTSG are constant is adopted. Then, the uncertainty quantification method is established based on Latin hypercube sampling and statistical method. On this basis, the quantitative platform for parameter uncertainty of the OTSG is developed. Finally, taking the uncertainty in primary-side flowrate of the OTSG as an example, the platform application work is carried out under the variable load in SPWR and step disturbance of secondary-side flowrate of the OTSG. The results show that the maximum uncertainty in the critical output parameters is acceptable for SPWR. |
| first_indexed | 2024-03-13T03:44:48Z |
| format | Article |
| id | doaj.art-9f154beb7ebb418e904793a98587ac99 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-03-13T03:44:48Z |
| publishDate | 2023-07-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-9f154beb7ebb418e904793a98587ac992023-06-23T04:42:44ZengElsevierNuclear Engineering and Technology1738-57332023-07-0155723952406Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling methodLekang Chen0Chuqi Chen1Linna Wang2Wenjie Zeng3Zhifeng Li4School of Nuclear Science and Technology, University of South China, Hengyang City, 421001, ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang City, 421001, ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang City, 421001, ChinaSchool of Nuclear Science and Technology, University of South China, Hengyang City, 421001, China; Corresponding author.Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology, And Shaanxi Engineering Research Center of Advanced Nuclear Energy, Xi'an Jiaotong University, Xi'an, 710049, China; Corresponding author.To study the influence of parameter uncertainty in small pressurized water reactor (SPWR) once-through steam generator (OTSG), the nonlinear mathematical model of the SPWR is firstly established. Including the reactor core model, the OTSG model and the pressurizer model. Secondly, a control strategy that both the reactor core coolant average temperature and the secondary-side outlet pressure of the OTSG are constant is adopted. Then, the uncertainty quantification method is established based on Latin hypercube sampling and statistical method. On this basis, the quantitative platform for parameter uncertainty of the OTSG is developed. Finally, taking the uncertainty in primary-side flowrate of the OTSG as an example, the platform application work is carried out under the variable load in SPWR and step disturbance of secondary-side flowrate of the OTSG. The results show that the maximum uncertainty in the critical output parameters is acceptable for SPWR.http://www.sciencedirect.com/science/article/pii/S1738573323001420Parameter uncertaintyUncertainty quantification platformSmall pressurized water reactorDual-constant control strategy |
| spellingShingle | Lekang Chen Chuqi Chen Linna Wang Wenjie Zeng Zhifeng Li Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method Nuclear Engineering and Technology Parameter uncertainty Uncertainty quantification platform Small pressurized water reactor Dual-constant control strategy |
| title | Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method |
| title_full | Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method |
| title_fullStr | Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method |
| title_full_unstemmed | Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method |
| title_short | Uncertainty quantification of once-through steam generator for nuclear steam supply system using latin hypercube sampling method |
| title_sort | uncertainty quantification of once through steam generator for nuclear steam supply system using latin hypercube sampling method |
| topic | Parameter uncertainty Uncertainty quantification platform Small pressurized water reactor Dual-constant control strategy |
| url | http://www.sciencedirect.com/science/article/pii/S1738573323001420 |
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