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연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 495 - 503 (9page)
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초록· 키워드
오류제보하기
Operators of nuclear power plants may not be equipped with sufficient information during aloss-of-coolant accident (LOCA), which can be fatal, or they may not have sufficient time toanalyze the information they do have, even if this information is adequate. It is not easy topredict the progression of LOCAs in nuclear power plants. Therefore, accurate information ontheLOCAbreak positionandsize should be provided to efficientlymanage the accident. In thispaper, the LOCA break size is predicted using a cascaded fuzzy neural network (CFNN) model.
The input data of theCFNNmodel are the time-integrated values of each measurement signalfor an initial short-time interval after a reactor scram. The training of the CFNN model isaccomplished by a hybrid method combined with a genetic algorithm and a least squaresmethod. As a result, LOCA break size is estimated exactly by the proposed CFNN model.
목차
등록된 정보가 없습니다.
참고문헌 (19)
참고문헌 신청
A. Gofuku / 1988 / Diagnostic techniques of a small-break lossof-coolant accident at a pressurized water reactor plant / Nucl. Technol 81 : 313 ~ 332
C. Allison / 1998 / Comparison between MAAP, MELCOR and SCDAP/RELAP5 / Proceedings of the Workshop on Severe Accident Research : 396 ~ 401
D. Y. Kim / 2015 / Estimation of minimum DNBR using cascaded fuzzy neural networks / IEEE Trans. Nucl. Sci 62 : 1849 ~ 1856
Dong Yeong Kim / 2016 / Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks / Nuclear Engineering and Technology 48 (3) : 702
E. B. Bartlett / 1992 / Nuclear power plant diagnostics using an artificial neural network / Nucl. Technol 97 : 272 ~ 281
C. Allison / 1998 / Comparison between MAAP, MELCOR and SCDAP/RELAP5 / Proceedings of the Workshop on Severe Accident Research : 396 ~ 401
D. Y. Kim / 2015 / Estimation of minimum DNBR using cascaded fuzzy neural networks / IEEE Trans. Nucl. Sci 62 : 1849 ~ 1856
Dong Yeong Kim / 2016 / Reactor Vessel Water Level Estimation During Severe Accidents Using Cascaded Fuzzy Neural Networks / Nuclear Engineering and Technology 48 (3) : 702
E. B. Bartlett / 1992 / Nuclear power plant diagnostics using an artificial neural network / Nucl. Technol 97 : 272 ~ 281
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