개인구독
소속 기관이 없으신 경우, 개인 정기구독을 하시면 저렴하게
논문을 무제한 열람 이용할 수 있어요.
지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.6
- 수록면
- 702 - 710 (9page)
이용수
초록· 키워드
오류제보하기
Global concern and interest in the safety of nuclear power plants have increased considerablysince the Fukushima accident. In the event of a severe accident, the reactor vesselwater level cannot be measured. The reactor vessel water level has a direct impact onconfirming the safety of reactor core cooling. However, in the event of a severe accident, itmay be possible to estimate the reactor vessel water level by employing other information. The cascaded fuzzy neural network (CFNN) model can be used to estimate the reactor vesselwater level through the process of repeatedly adding fuzzy neural networks. The developedCFNN model was found to be sufficiently accurate for estimating the reactor vessel waterlevel when the sensor performance had deteriorated. Therefore, the developed CFNN modelcan help provide effective information to operators in the event of a severe accident.
목차
등록된 정보가 없습니다.
참고문헌 (24)
참고문헌 신청
A. Murata / 2015 / Classification method of severe accident condition for the development of severe accident instrumentation and monitoring system in nuclear power plant / J. Nucl. Sci. Technol 53:870~877
J.W. Hines / 1997 / Signal validation using an adaptive neural fuzzy inference system / Nucl. Technol 119:181~193
M.G. Na / 2001 / A neuro-fuzzy inference system for sensor failure detection using wavelet denoising / PCA and SPRT, J. Korean Nucl. Soc 33:483~497
JAMIE GARVEY / 2007 / VALIDATION OF ON-LINE MONITORING TECHNIQUES TO NUCLEAR PLANT DATA / Nuclear Engineering and Technology 39(2):149~158
E.B. Bartlett / 1992 / Nuclear power plant diagnostics using an artificial neural network / Nucl. Technol 97:272~281
J.W. Hines / 1997 / Signal validation using an adaptive neural fuzzy inference system / Nucl. Technol 119:181~193
M.G. Na / 2001 / A neuro-fuzzy inference system for sensor failure detection using wavelet denoising / PCA and SPRT, J. Korean Nucl. Soc 33:483~497
JAMIE GARVEY / 2007 / VALIDATION OF ON-LINE MONITORING TECHNIQUES TO NUCLEAR PLANT DATA / Nuclear Engineering and Technology 39(2):149~158
E.B. Bartlett / 1992 / Nuclear power plant diagnostics using an artificial neural network / Nucl. Technol 97:272~281
함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Event/accident Simulation Model of the Reactor Pressure Vessel Internal Segmentation Activity
한국방사성폐기물학회 학술대회
2019 .01
-
EVALUATION OF HEAT-FLUX DISTRIBUTION AT THE INNER AND OUTER REACTOR VESSEL WALLS UNDER THE IN-VESSEL RETENTION THROUGH EXTERNAL REACTOR VESSEL COOLING CONDITION
Nuclear Engineering and Technology
2015 .01
-
TOP-MOUNTED IN-CORE INSTRUMENTATION : CURRENT STATUS AND TECHNICAL ISSUES
에너지공학
2015 .06
-
Nuclear Reactor Vessel Water Level Prediction During Severe Accidents Using Deep Neural Networks
Nuclear Engineering and Technology
2019 .01
-
Weighting Factors of the Performance Shaping Factors for the Segmentation of Reactor Pressure Vessel Internals Using Fuzzy AHP
한국방사성폐기물학회 학술대회
2018 .01
-
Assessment of N-16 activity concentration in Bangladesh Atomic Energy Commission TRIGA Research Reactor
Nuclear Engineering and Technology
2018 .01
-
PREDICTION OF HYDROGEN CONCENTRATION IN CONTAINMENT DURING SEVERE ACCIDENTS USING FUZZY NEURAL NETWORK
Nuclear Engineering and Technology
2015 .01
-
Evaluating direct vessel injection accident-event progression of AP1000 and key figures of merit to support the design and development of water-cooled small modular reactors
Nuclear Engineering and Technology
2024 .06
-
설계방식에 따른 초고압 반응용기의 구조적 특성에 관한 연구
한국정밀공학회 학술발표대회 논문집
2018 .05
-
Vessel failure sensitivities of an advanced reactor for SBLOCA
Nuclear Engineering and Technology
2020 .01
-
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
-
Study on Radiological Inventory Assessment of K 1 Reactor Vessel
한국방사성폐기물학회 학술대회
2019 .01
-
Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor
Nuclear Engineering and Technology
2020 .01
-
INSTRUMENTATION AND CONTROL STRATEGIES FOR AN INTEGRAL PRESSURIZED WATER REACTOR
Nuclear Engineering and Technology
2015 .01
-
Segmentation and Packaging Plan for the Reactor Pressure Vessel
한국방사성폐기물학회 학술대회
2017 .01
-
An interactive multiple model method to identify the in-vessel phenomenon of a nuclear plant during a severe accident from the outer wall temperature of the reactor vessel
Nuclear Engineering and Technology
2021 .02
-
원자로용기 결함 조건에 따른 원자로 내부구조물 이상진동에 대한 유한요소 해석
한국소음진동공학회논문집
2023 .12
-
A Takagi – Sugeno fuzzy power-distribution method for a prototypical advanced reactor considering pump degradation
Nuclear Engineering and Technology
2017 .01
-
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
-
Enhancing Utilization and Ensuring Security: Insights to Compromise Contradicting Conditions in New Research Reactors
Nuclear Engineering and Technology
2021 .05
이 논문의 저자 정보
최근 본 자료
댓글(0)
0