현행 주급수유량 기반의 열출력 계산 방법을 주급수 벤츄리의 파울링 현상과 무관한 주증기 유량 기반의 열출력 계산 방법에 대한 연구 논문임
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https://www.riss.kr/link?id=T14055619
대전: 忠南大學校 大學院, 2016
학위논문(석사) -- 忠南大學校 大學院 , 기계공학과 열유체시스템 전공 , 2016. 2
2016
한국어
621 판사항(22)
대전
Study of Reactor Thermal Power Based on Main Steam Flow of Nuclear Power Plant
vi, 67 p.: 삽화; 26 cm.
충남대학교 논문은 저작권에 의해 보호받습니다.
지도교수: 박종호
참고문헌 : p. 63-64
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상세조회0
다운로드국문 초록 (Abstract)
현행 주급수유량 기반의 열출력 계산 방법을 주급수 벤츄리의 파울링 현상과 무관한 주증기 유량 기반의 열출력 계산 방법에 대한 연구 논문임
현행 주급수유량 기반의 열출력 계산 방법을 주급수 벤츄리의 파울링 현상과 무관한 주증기 유량 기반의 열출력 계산 방법에 대한 연구 논문임
다국어 초록 (Multilingual Abstract)
The current feedwater mass flow measurement has experienced the venturi fouling which causes erroneous high flow indications. The high flow indication leads to high reactor thermal power indication and, as a result, causes plant operators to reduce re...
The current feedwater mass flow measurement has experienced the venturi fouling which causes erroneous high flow indications. The high flow indication leads to high reactor thermal power indication and, as a result, causes plant operators to reduce real power output in order to maintain plant power below licensed power(100%).
One of the effective remedies to this venturi fouling is considered to be an independent steam flow measurement because it is not susceptible to fouling problem.
A mathematical mass flow equation was developed based on the steam flow rate in a similar way to the feedwater-flow-based power calculation method.
Parallel indications of both powers give a continuous indication of potential fouling problem. The main steam-flow-based power monitoring is expected to enhance the core power monitoring capability.
The development project includes the review of the thermal power operation and design features, the development of main steam flow calibration methodology and operator procedure, and preliminary uncertainty evaluation to determine the feasibility of the method.
Results of the Study are summarized as below;
A mathematical steam mass flow rate equation has been developed to be implemented in the reactor thermal power calculation for OPR1000 plants.
The basic inputs to mass flow equation have been determined and main steam flow calibration procedure has been developed for use in the plant by the operators.
Uncertainty evaluation of main steam-flow-based power showed less than 1.5% at 95 % confidence level which is well within the acceptance criteria.
The COLSS power calculation algorithm was modified to implement the main steam-flow-based power calculation. The modified COLSS program was installed in the nuclear plant plant to verify the operating performance for a certain period of testing.
목차 (Table of Contents)