Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code
Constitutive equations in a nuclear reactor safety analysis code are mostly empirical correlations developed from experiments, which always accompany uncertainties. The accuracy of the code can be improved by modifying the constitutive equations fitting wider range of data with less uncertainty. Thu...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2023-01-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573322004119 |
| _version_ | 1797955397595693056 |
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| author | ChoHwan Oh Doh Hyeon Kim Jeong Ik Lee |
| author_facet | ChoHwan Oh Doh Hyeon Kim Jeong Ik Lee |
| author_sort | ChoHwan Oh |
| collection | DOAJ |
| description | Constitutive equations in a nuclear reactor safety analysis code are mostly empirical correlations developed from experiments, which always accompany uncertainties. The accuracy of the code can be improved by modifying the constitutive equations fitting wider range of data with less uncertainty. Thus, the sensitivity of the code with respect to the constitutive equations is evaluated quantitatively in the paper to understand the room for improvement of the code. A new methodology is proposed which first starts by dividing the thermal hydraulic conditions into multiple sub-regimes using self-organizing map (SOM) clustering method. The sensitivity analysis is then conducted by multiplying an arbitrary set of coefficients to the constitutive equations for each sub-divided thermal-hydraulic regime with SOM to observe how the code accuracy varies. The randomly chosen multiplier coefficient represents the uncertainty of the constitutive equations. Furthermore, the set with the smallest error with the selected experimental data can be obtained and can provide insight which direction should the constitutive equations be modified to improve the code accuracy. The newly proposed method is applied to a steady-state experiment and a transient experiment to illustrate how the method can provide insight to the code developer. |
| first_indexed | 2024-04-10T23:33:36Z |
| format | Article |
| id | doaj.art-1be7b298eb584931985a30ea5390c493 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-04-10T23:33:36Z |
| publishDate | 2023-01-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-1be7b298eb584931985a30ea5390c4932023-01-12T04:18:36ZengElsevierNuclear Engineering and Technology1738-57332023-01-01551131143Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis codeChoHwan Oh0Doh Hyeon Kim1Jeong Ik Lee2Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, Republic of KoreaDepartment of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, Republic of KoreaCorresponding author.; Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, 34141, Republic of KoreaConstitutive equations in a nuclear reactor safety analysis code are mostly empirical correlations developed from experiments, which always accompany uncertainties. The accuracy of the code can be improved by modifying the constitutive equations fitting wider range of data with less uncertainty. Thus, the sensitivity of the code with respect to the constitutive equations is evaluated quantitatively in the paper to understand the room for improvement of the code. A new methodology is proposed which first starts by dividing the thermal hydraulic conditions into multiple sub-regimes using self-organizing map (SOM) clustering method. The sensitivity analysis is then conducted by multiplying an arbitrary set of coefficients to the constitutive equations for each sub-divided thermal-hydraulic regime with SOM to observe how the code accuracy varies. The randomly chosen multiplier coefficient represents the uncertainty of the constitutive equations. Furthermore, the set with the smallest error with the selected experimental data can be obtained and can provide insight which direction should the constitutive equations be modified to improve the code accuracy. The newly proposed method is applied to a steady-state experiment and a transient experiment to illustrate how the method can provide insight to the code developer.http://www.sciencedirect.com/science/article/pii/S1738573322004119Constitutive equation sensitivity analysisReactor safety analysis codeSelf-organizing mapNon-parametric statisticsSUBO experimentMIT pressurizer experiment |
| spellingShingle | ChoHwan Oh Doh Hyeon Kim Jeong Ik Lee Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code Nuclear Engineering and Technology Constitutive equation sensitivity analysis Reactor safety analysis code Self-organizing map Non-parametric statistics SUBO experiment MIT pressurizer experiment |
| title | Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code |
| title_full | Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code |
| title_fullStr | Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code |
| title_full_unstemmed | Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code |
| title_short | Application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code |
| title_sort | application of data driven modeling and sensitivity analysis of constitutive equations for improving nuclear power plant safety analysis code |
| topic | Constitutive equation sensitivity analysis Reactor safety analysis code Self-organizing map Non-parametric statistics SUBO experiment MIT pressurizer experiment |
| url | http://www.sciencedirect.com/science/article/pii/S1738573322004119 |
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