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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.8
- 수록면
- 2,547 - 2,555 (9page)
- DOI
- https://doi.org/10.1016/j.net.2021.01.040
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초록· 키워드
오류제보하기
The frequency of reactor coolant leakage is expected to increase over the lifetime of a nuclear powerplant owing to degradation mechanisms, such as flow-acceleration corrosion and stress corrosioncracking. When loss of coolant accidents (LOCAs) occur, several parameters change rapidly depending onthe size and location of the cracks. In this study, leak flow during LOCAs is predicted using a deep fuzzyneural network (DFNN) model. The DFNN model is based on fuzzy neural network (FNN) modules andhas a structure where the FNN modules are sequentially connected. Because the DFNN model is based onthe FNN modules, the performance factors are the number of FNN modules and the parameters of theFNN module. These parameters are determined by a least-squares method combined with a geneticalgorithm; the number of FNN modules is determined automatically by cross checking a fitness functionusing the verification dataset output to prevent an overfitting problem. To acquire the data of LOCAs, anoptimized power reactor-1000 was simulated using a modular accident analysis program code. Thepredicted results of the DFNN model are found to be superior to those predicted in previous works. Theleak flow prediction results obtained in this study will be useful to check the core integrity in nuclearpower plant during LOCAs. This information is also expected to reduce the workload of the operators
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참고문헌 (3)
참고문헌 신청
최건필 / 2017 / Estimation of LOCA Break Size Using Cascaded Fuzzy Neural Networks / Nuclear Engineering and Technology 49(3):495~503
Dong Yeong Kim / 2016 / Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks / Nuclear Engineering and Technology 48(3):702~710
K. H. Yoo / 2017 / Identification of LOCA and estimation of its break size by multi-connected support vector machines / IEEE Trans. Nucl. Sci 64(10):2610~2617
Dong Yeong Kim / 2016 / Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks / Nuclear Engineering and Technology 48(3):702~710
K. H. Yoo / 2017 / Identification of LOCA and estimation of its break size by multi-connected support vector machines / IEEE Trans. Nucl. Sci 64(10):2610~2617
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