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.
초록· 키워드
오류제보하기
A Study of Improvement in Reactor Thermal Power Measurement Method using Kalman Filter. The objectives of the safety analysis of nuclear power plants are to maintain the surface temperature of fuel and fuel cladding within limit value in case of Loss of Coolant accident (LOCA) so that it ensures the safety and reliability of nuclear power plants. The new technique evaluating the reactor power and improvement of existing plant system increase the safety margin of nuclear power plant operation, and accordingly, economic effect will be anticipated. Hereby, 1 would like to introduce reactor power measurement method using Kalman filter that enables to calculate the reactor power more precisely combining the parameters, for example, turbine output as the 1 st stage pressure of high pressure turbine, and reactor power using energy equilibrium relation. It is expected that the new technique will enhance the accuracy of measurement of reactor power and maintain the reliability of nuclear power operation by increasing operational safety margin, and gain the economic benefit
목차
등록된 정보가 없습니다.
참고문헌 (0)
참고문헌 신청함께 읽어보면 좋을 논문
논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!
-
Simulation of Reactor and Turbine Power Transients in CANDU 6 Nuclear Power Plants
한국에너지학회 학술발표회
1994 .05
-
계통 안전성을 고려한 원자력발전의 부하추종 요건연구
전기학회논문지
2012 .11
-
Seismic Design Loads of the Reactor Internals for Korean Standard Nuclear Power Plant
대한기계학회 춘추학술대회
1992 .01
-
POWER UPRATES IN NUCLEAR POWER PLANTS : INTERNATIONAL EXPERIENCES AND APPROACHES FOR IMPLEMENTATION
Nuclear Engineering and Technology
2008 .01
-
Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
Nuclear Engineering and Technology
2020 .01
-
A Study on the Application of the Reactor Power Cutback System to WH 1000 Type Nuclear Power Plant
한국방사성폐기물학회 학술대회
2018 .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
-
Modeling of Nuclear Reactor and Its Power Control by Model Predictive Control
ICEIC : International Conference on Electronics, Informations and Communications
2006 .06
-
Robust feedback-linearization control for axial power distribution in pressurized water reactors during load-following operation
Nuclear Engineering and Technology
2018 .01
-
Technology Selection for Offshore Underwater Small Modular Reactors
Nuclear Engineering and Technology
2016 .01
-
원전 조직 및 인적 특성요인 분석을 위한 동태적 시뮬레이션 연구
대한인간공학회 학술대회논문집
2013 .10
-
Neuro-Fuzzy Algorithm for Nuclear Reactor Power Control : Part 1
한국지능시스템학회 논문지
1995 .09
-
CORE DESIGN CONCEPTS FOR HIGH PERFORMANCE LIGHT WATER REACTORS
Nuclear Engineering and Technology
2007 .01
-
연구용 원자로의 출력제어기법 설계 및 적용사례
대한전자공학회 학술대회
2014 .06
-
AM600: A New Look at the Nuclear Steam Cycle
Nuclear Engineering and Technology
2017 .01
-
Study on Nuclear Test Scheme and Test Results for Safety Neutron Measurement System in Research Reactor
한국방사성폐기물학회 학술대회
2017 .01
-
동력용 원자로에 있어서의 열공학연구현황 ( Review of the Heat Transfer Research on the Nuclear Power Reactors )
대한기계학회지
1968 .08
-
Organizational Contributions to Nuclear Power Plant Safety
Nuclear Engineering and Technology
2005 .01
-
A Safety Assessment Methodology for a Digital Reactor Protection System
International Journal of Control Automation and Systems
2006 .02
-
일체형원자로에서 냉각재펌프의 전력측정을 이용한 실시간 유량산정 방법에 관한 연구
한국유체기계학회 학술대회 논문집
2003 .12
이 논문의 저자 정보
최근 본 자료
댓글(0)
0