[국내논문]고리1호기 계통제염을 위한 원자로냉각재내 유동 특성 평가 Flow Characteristics Evaluation in Reactor Coolant System for Full System Decontamination of Kori-1 Nuclear Power Plant원문보기
국내 가동원전 중 2-루프 가압경수로인 고리1호기는 약 40년 운전한 후, 2017년 6월 18일 영구정지되었다. 영구정지된 고리 1호기는 주요 해체작업을 수행하기전에 계통내 선량률을 저감시켜 작업자피폭을 최소화하기 위한 계통제염을 수행할 예정이다. 일반적으로, 계통제염 범위는 원자로압력용기, 가압기, 증기발생기, 화학 및 체적제어계통, 잔열제거계통 및 원자로 냉각재계통 주요배관을 포함한다. 이러한 계통 및 기기 등을 효율적으로 제염하기 위해서는 제염과정에서 원자로냉각재계통내 유동특성을 평가할 필요가 있다. 계통제염을 위해 순환유량을 제공하는 방법은 다양하나, 본 논문에서는 잔열제거펌프 운전에 따른 고리1호기 원자로냉각재계통내 유동특성을 평가하였다. 잔열제거펌프를 이용한 계통제염은 원자로냉각재 내 유량의 불균형을 초래하여 계통내 기기 및 배관 등에 불순물을 침적시켜 제염이 효율적이지 않다는 것으로 평가되었다.
국내 가동원전 중 2-루프 가압경수로인 고리1호기는 약 40년 운전한 후, 2017년 6월 18일 영구정지되었다. 영구정지된 고리 1호기는 주요 해체작업을 수행하기전에 계통내 선량률을 저감시켜 작업자피폭을 최소화하기 위한 계통제염을 수행할 예정이다. 일반적으로, 계통제염 범위는 원자로압력용기, 가압기, 증기발생기, 화학 및 체적제어계통, 잔열제거계통 및 원자로 냉각재계통 주요배관을 포함한다. 이러한 계통 및 기기 등을 효율적으로 제염하기 위해서는 제염과정에서 원자로냉각재계통내 유동특성을 평가할 필요가 있다. 계통제염을 위해 순환유량을 제공하는 방법은 다양하나, 본 논문에서는 잔열제거펌프 운전에 따른 고리1호기 원자로냉각재계통내 유동특성을 평가하였다. 잔열제거펌프를 이용한 계통제염은 원자로냉각재 내 유량의 불균형을 초래하여 계통내 기기 및 배관 등에 불순물을 침적시켜 제염이 효율적이지 않다는 것으로 평가되었다.
The Kori-1 Nuclear Power Plant (NPP), WH 2-Loop Pressurized Water Reactor (PWR) operated for approximately 40 years in Korea, was permanently ceased on June 18, 2017. To reduce worker exposure to radiation by reducing the dose rate in the system before starting main decommissioning activities, the p...
The Kori-1 Nuclear Power Plant (NPP), WH 2-Loop Pressurized Water Reactor (PWR) operated for approximately 40 years in Korea, was permanently ceased on June 18, 2017. To reduce worker exposure to radiation by reducing the dose rate in the system before starting main decommissioning activities, the permanently ceased Kori-1 NPP will be subjected to full system decontamination. Generally, the range of system decontamination includes Reactor Pressure Vessels (RPV), Pressurizer (PZR), Steam Generators (SG), Chemical & Volume Control System (CVCS), Residual Heat Removal System (RHRS), and Reactor Coolant System (RCS) piping. In order to decontaminate these systems and equipment in an effective manner, it is necessary to evaluate the influence of the flow characteristics in the RCS during the decontamination period. There are various methods of providing circulating flow rate to the system decontamination. In this paper, the flow characteristics in Kori-1 NPP reactor coolant according to RHR pump operation were evaluated. The evaluation results showed that system decontamination using an RHR pump was not effective at decontamination due first to impurities deposited in piping and equipment, and second to the extreme flow unbalance in the RCS caused deposition of impurities.
The Kori-1 Nuclear Power Plant (NPP), WH 2-Loop Pressurized Water Reactor (PWR) operated for approximately 40 years in Korea, was permanently ceased on June 18, 2017. To reduce worker exposure to radiation by reducing the dose rate in the system before starting main decommissioning activities, the permanently ceased Kori-1 NPP will be subjected to full system decontamination. Generally, the range of system decontamination includes Reactor Pressure Vessels (RPV), Pressurizer (PZR), Steam Generators (SG), Chemical & Volume Control System (CVCS), Residual Heat Removal System (RHRS), and Reactor Coolant System (RCS) piping. In order to decontaminate these systems and equipment in an effective manner, it is necessary to evaluate the influence of the flow characteristics in the RCS during the decontamination period. There are various methods of providing circulating flow rate to the system decontamination. In this paper, the flow characteristics in Kori-1 NPP reactor coolant according to RHR pump operation were evaluated. The evaluation results showed that system decontamination using an RHR pump was not effective at decontamination due first to impurities deposited in piping and equipment, and second to the extreme flow unbalance in the RCS caused deposition of impurities.
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제안 방법
Jose Cabrera NPP used to the RCPs to supply the chemical agents and circulation flow rate in the decontamination scope. In this plant, nitrogen was pressurized in the PZR to provide the minimum pressure (~430 psig) required for RCP operation and the design was changed so that the demineralized water could be supplied separately to protect the RCP seals.
성능/효과
According to Eq. (3), it was evaluated that the residual concentration of impurities in the PZR with the charging pump operation for supplying the auxiliary spray flow rate was 61.6% of the initial concentration after 60 minute, 37.9% for two charging pumps operation and 23.3% for three charging pumps operation, respectively. Fig.
This paper dealt with the flow characteristics in Kori1 NPP reactor coolant according to RHR pump operation. It was demonstrated that sufficient circulation flow rate was required in the RCS to efficiently decontaminate systems and equipment, and the decontamination effect was improved as the circulation flow rate was increased. This paper showed that system decontamination using RHR pump could not be effective due to impurities deposited in piping and equipment, and the extreme flow unbalance in RCS caused the deposition of impurities as well.
It was demonstrated that sufficient circulation flow rate was required in the RCS to efficiently decontaminate systems and equipment, and the decontamination effect was improved as the circulation flow rate was increased. This paper showed that system decontamination using RHR pump could not be effective due to impurities deposited in piping and equipment, and the extreme flow unbalance in RCS caused the deposition of impurities as well. A separate facility can be considered to distribute the flow rate equally to solve the unbalance of the flow rate.
참고문헌 (5)
Electric Power Research Institute, "Decontamination Handbook", Electric Power Research Institute Report, EPRI TR-112352 (1999).
Electric Power Research Institute, "Evaluation of the Decontamination of the Reactor Coolant Systems at Maine Yankee and Connecticut Yankee", Electric Power Research Institute Report, EPRI TR-112092 (1999).
Electric Power Research Institute, "Jose Cabrera Nuclear Power Plant Full System Chemical Decontamination Experience Report", Electric Power Research Institute Report, EPRI TR-109230 (2009).
Korea Hydro & Nuclear Power Co. LTD., "Final Safety Analysis Report of Kori unit 1", Kori Unit 1 Nuclear Power Plant (2014).
Korea Hydro & Nuclear Power Co. LTD., "Final Safety Analysis Report of Kori Unit 3&4", Kori Units 3&4 Nuclear Power Plants (2015).
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