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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2009.1
- 수록면
- 1,181 - 1,190 (10page)
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초록· 키워드
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Knowing more about the Local Power Density (LPD) at the hottest part of a nuclear reactor core can provide more important
information than knowledge of the LPD at any other position. The LPD at the hottest part needs to be estimated accurately in order
to prevent the fuel rod from melting in a nuclear reactor. Support Vector Machines (SVMs) have successfully been applied in
classification and regression problems. Therefore, in this paper, the power peaking factor, which is defined as the highest LPD to
the average power density in a reactor core, was estimated by SVMs which use numerous measured signals of the reactor coolant
system. The SVM models were developed by using a training data set and validated by an independent test data set. The SVM
models’ uncertainty was analyzed by using 100 sampled training data sets and verification data sets. The prediction intervals were
very small, which means that the predicted values were very accurate. The predicted values were then applied to the first fuel cycle
of the Yonggwang Nuclear Power Plant Unit 3. The root mean squared error was approximately 0.15%, which is accurate enough
for use in LPD monitoring and for core protection that uses LPD estimation.
목차
등록된 정보가 없습니다.
참고문헌 (21)
참고문헌 신청
ABB Combustion Engineering Inc. / 1986 / Overview Description of the Core Operation Limit Supervisory System (COLSS)
B.O. Cho / 2002 / MASTER: reactor core design and analysis code / Proceedings of 2002 Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics (PHYSOR 2002)
G.C. Lee / 2002 / Improved methodology for generation of axial flux shapes in digital core protection systems / Annals of Nuclear Energy 29 (7) : 805 ~ 819
GYUN YOUNG HEO / 2008 / CONDITION MONITORING USING EMPIRICAL MODELS: TECHNICAL REVIEW AND PROSPECTS FOR NUCLEAR APPLICATIONS / Nuclear Engineering and Technology 40 (1) : 49
H.C. Kim / 1997 / Development of a back propagation network for one-step transient DNBR calculations / Annals of Nuclear Energy 24 (17) : 1437 ~ 1446
B.O. Cho / 2002 / MASTER: reactor core design and analysis code / Proceedings of 2002 Int. Conf. New Frontiers of Nuclear Technology: Reactor Physics (PHYSOR 2002)
G.C. Lee / 2002 / Improved methodology for generation of axial flux shapes in digital core protection systems / Annals of Nuclear Energy 29 (7) : 805 ~ 819
GYUN YOUNG HEO / 2008 / CONDITION MONITORING USING EMPIRICAL MODELS: TECHNICAL REVIEW AND PROSPECTS FOR NUCLEAR APPLICATIONS / Nuclear Engineering and Technology 40 (1) : 49
H.C. Kim / 1997 / Development of a back propagation network for one-step transient DNBR calculations / Annals of Nuclear Energy 24 (17) : 1437 ~ 1446
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