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이선기 한국압력기기공학회 2020 한국압력기기공학회 논문집 Vol.16 No.1
In nuclear power plants, there is a risk of thermal fatigue in equipment and piping affecting system soundness because the temperature change of the system accompanies in every operation and shutdown. Therefore, in order to prevent the excess of the fatigue limit during the lifetime of plants, the fatigue limit of each piping material is determined in the designing stage. However, there are many cases where equipment or piping is locally subjected to thermal fatigue that is not considered in the design, resulting in damage to the equipment and piping, and failure during operation. Currently, local thermal fatigue generation mechanisms that are not taken into account in the design stage are gradually being identified. In this paper, the effects of the fluid temperature fluctuations on the piping soundness due to the mixing of hot and cold water, one of the local thermal fatigue generating mechanisms, were evaluated.
Development of an Improved FARE Tool with Application to Wolsong Nuclear Power Plant
이선기,홍승열 한국원자력학회 2013 Nuclear Engineering and Technology Vol.45 No.2
In Canada Deuterium Uranium (CANDU)-type nuclear power plants, the reactor is composed of 380 fuel channels and refueling is performed on one or two channels per day. At the time of refueling, the fluid force of the cooling water inside the channel is exploited. New fuel added upstream of the fuel channel is moved downstream by the fluid force of the cooling water,and the used fuel is pushed out. Through this process, refueling is completed. Among the 380 fuel channels, outer rows 1 and 2(called the FARE channel) make the process of using only the internal fluid force impossible because of the low flow rate of the channel cooling water. Therefore, a Flow Assist Ram Extension (FARE) tool, a refueling aid, is used to refuel these channels in order to compensate for the insufficient fluid force. The FARE tool causes flow resistance, thus allowing the fuel to be moved down with the flow of cooling water. Although the existing FARE tool can perform refueling in Korean plants, the coolant flow rate is reduced to below 80% of the normal flow for some time during refueling. A Flow rate below 80% of the normal flow cause low flow rate alarm signal in the plant operation. A flow rate below 80% of the normal flow may cause difficulties in the plant operation because of the increase in the coolant temperature of the channel. A new and improved FARE tool is needed to address the limitations of the existing FARE tool. In this study, we identified the cause of the low flow phenomena of the existing FARE tool. A new and improved FARE tool has been designed and manufactured. The improved FARE tool has been tested many times using laboratory test apparatus and was redesigned until satisfactory results were obtained. In order to confirm the performance of the improved FARE tool in a real plant, the final design FARE tool was tested at Wolsong Nuclear Power Plant Unit 2. The test was carried out successfully and the low flow rate alarm signal was eliminated during refueling. Several additional improved FARE tools have been manufactured. These improved FARE tools are currently being used for Korean CANDU plant refueling.
이선기 대한산업경영학회 2020 산업융합연구 Vol.18 No.4
원자력발전소의 순환수 계통 해수배관에 차단밸브가 설치되어 있지 않을 경우 복수기 내부 세관(튜브) 에서 해수 누설 등의 이상 발생시, 정비 및 보수를 위해 최소한 순환수 펌프 1대를 정지하여야 하며, 최악의 경우에는 발전정지를 하여야 한다. 그러나 순환수 계통 해수배관에 차단밸브를 설치할 경우, 복수기 이상 발생 시 병열로 연결된 복수기의 해당 수실만 차단 가능함으로 발전소 출력 손실을 최소화 할 수 있다. 본 논문에서 는 원자력발전소 순환수 계통의 복수기 수실에 차단밸브를 설치할 경우, 순환수 계통의 유량변화, 계통의 구조 적 건전성, 복수기 진공도에의 영향을 평가하였다. 평가결과, 복수기 수실 차단밸브 설치에 따른 유량은 밸브 완전 개방시 0.3% 감소하며, 완전 잠금시에는 4.5% 감소하였다. 또한 유량감소에 따라 복수기 진공도는 떨어 지나 계통의 건전성은 유지됨을 알았다. Because there are no isolation valves in condensate system of nuclear power plants, circulating water pump was shutdown for the condenser repair. When circulating water pump was shutdown, power plant output decreased about 45%. These output decreasing can minimize by establishing isolation valves. In this paper, evaluated effect to flow conditions change of condensate system, structural integrity of system, condenser pressure of in case of establish isolation valves to condensate system. Results of the evaluation, the flow rate due to the installation of the isolation valve decreased 0.3% when the valve was fully opened and 4.5% when fully closed. In addition, it was found that the vacuum degree of the condenser decreased with decreasing flow rate, but the integrity of the system was maintained.