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발전소전원상실사고시 고압비상충수계통의 종합효과시험에 대한 MARS-KS 코드 검증 해석
이선일(Sunil Lee),류성욱(Sung Uk Ryu),이성재(Sung-Jae Yi) 대한기계학회 2019 대한기계학회 춘추학술대회 Vol.2019 No.11
This paper reports the validation of the injection performance of Hybrid Safety Injection Tank (HSIT) using a integral effect test facility (ATLAS-HSIT) in Korea Atomic Energy Research Institute (KAERI). The concept of Hybrid Safety Injection Tank (Hybrid SIT) has been introduced for the purpose of application to the Advanced Power Reactor Plus (APR+). The Hybrid SIT is a passive safety injection system that enables the safety injection water to be injected into the reactor pressure vessel under the condition of high pressure by connecting the top of the SIT and the pressurizer (PZR). In this study, the SBO situation of the APR+ was analyzed by using the ATLAS Facility in order to evaluate whether the operation of the Hybrid SIT has an effect on the cooling performance of the Reactor Coolant System (RCS). After injection of the HSIT, it was found that the height of core and downcomer were maintained constant and peak cladding temperature was maintained under 350℃. It means that HEMS can contribute to effectively cool down the reactor coolant system during an SBO transient in both the experimental data and the MARS-KS calculation. In addition, the MARS-KS code analysis results proved to have the sufficient capability to quantitatively predict the SBO transient with the operation of the HSIT.
이선일(Sunil Lee),서경우(Kyoung Woo Seo) 대한기계학회 2018 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.6 No.2
고온 고압조건을 가진 발전용 상업로와는 달리 저온 저압조건에서 작동되는 연구용 원자로는 일반적으로 핵반응이 발생하는 노심이 개방된 수조수에 담겨 있는 개방수조형 방식으로 설계된다. 이 수조수의 냉각 및 정화를 위해 일차냉각계통을 포함한 다양한 유체계통이 필요하다. 특히 일차냉각계통은 정상출력운전 중 노심에서 발생되는 열을 일차냉각계통 펌프와 열교환기를 이용하여 제거하는 역할을 한다. 일차냉각계통 펌프가 정지되면 일차냉각계통 펌프의 관성바퀴에 의한 관성서행 유량을 통해 노심냉각을 유지하고, 안전잔열제거계통 펌프를 정지하면 플랩밸브를 통한 수조수의 자연순환에 의해 노심붕괴열이 제거된다. 본 논문에서는 개방수조형 연구용 원자로의 노심 냉각을 위한 일차냉각계통에 대해서 설계요건, 계통설명, 계통 운전(기동, 출력운전, 원자로 정지), 설계평가, 검사 및 시험의 항목으로 나누어 자세히 기술하였다. Unlike the nuclear power reactor, the research reactor for the multi-purpose neutron application has been designed with the open-pool type reactor the core is submerged in. The research reactor has several fluid systems such as primary cooling system (PCS), secondary cooling system, pool water management system, and hot water layer system. The primary cooling system removes the fission heat from the core in the normal operation. When the PCS pumps are not in operation after the reactor shutdown or trip, PCS removes the core decay heat by natural circulation through the flap valve. In this paper, the design bases, system description, system operation, design evaluation, inspection and testing for the primary cooling system are specified in detail.
가압 경수로용 종합 효과 시험 장치를 위한 이차 계통의 개념 설계
이선일(Sunil Lee),류성욱(Sung Uk Ryu),박현식(Hyun Sik Park) 대한기계학회 2019 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.7 No.2
국내에서 연구 중인 표준 원전은 안전성 및 성능을 검증해야 하며, 이를 위해 기기 및 계통 기반의 시험인 개발 효과 시험(SET: Separate Effect Test)을 포함하여 모든 계통을 포함하는 종합 효과 시험(IET: Integral Effect Test)이 수행되고 있다. IET 장치의 경우, 시험의 용이성을 고려해 원자로를 포함하는 일차 계통, 터빈을 포함하는 이차 계통, 안전을 위한 다양한 안전 계통, 그리고 여러 보조 계통들을 모두 축소 모형하여 구성된다. 실제 전기 생산을 위한 이차 계통은 발전 사이클(랭킨 사이클, Rankine Cycle)을 열역학적 기초로 두고 있으며, IET에서는 발전 사이클을 구성하지 않고 일차 계통의 경계 조건만을 만족시키는 역할을 수행하게 설계되고 있다. 이런 IET의 이차 계통은 크게 열린계 방식(open system type)과 닫힌계 방식(closed system type)으로 나누어진다. 두 가지 방식 중 본 논문에서는 일반적으로 사용되는 가압 경수로용 IET 장치의 이차 계통인 열린계 방식의 설계 과정에 대해서 설계 요건, 설계 개요, 주요 기능, 기술 사양으로 나누어 자세히 소개하고자 한다. Standard nuclear power plants under studying in Korea should verify the safety and performance of the systems and components. For this purpose, integral effect tests including all systems in power plant are being conducted, including the separate effect tests, which are a component or a system-based tests. In the case of the IET, the primary system including the reactor, the secondary system including the turbine, the various safety systems, and various auxiliary systems are scaled down for ease of testing. The secondary system for the actual electricity production is based on the thermodynamic basis of the power generation cycle (Rankin cycle), and IET is designed to fulfill the boundary conditions of the primary system without consisting the power generation cycle. This secondary system for IET is largely divided into open-system type and closed-system type. In this paper, the design process for the open-system type, which is the secondary system of commonly used in IET for the pressurized water reactor, is described in detail by dividing into design overview, design requirements, main functions, and technical specifications.
이선일(Sunil Lee),류성욱(Sung Uk Ryu),이성재(Sung-Jae Yi) 대한기계학회 2017 대한기계학회 춘추학술대회 Vol.2017 No.11
Research reactors should incorporate the measurement system for the core power to control and regulate the reactor power. The open-pool type research reactor modeled in this paper has three separate and independent channels of the neutron detectors to measure the core power. To calibrate these detectors, the thermal power of Primary Cooling System (PCS) which cools down the heat generated in reactor core is used as calibration reference. The core thermal power can be estimated by the measured values of the mass flow rates, core inlet/outlet temperatures of coolant in the PCS. In general, the uncertainty of the core thermal power is required to be controlled below a certain value. To meet this requirement, the uncertainty of core thermal power should be evaluated based on the uncertainty of the measured parameters. In this paper, the calculation equation for the core thermal power is derived and the uncertainty evaluation is conducted with variation of the uncertainty of the measured parameters such as mass flow rates and temperatures. In this parametric study, the allowable uncertainty for temperature sensors has been obtained to guarantee 5% of the core thermal power uncertainty.
이선일(Sunil Lee),김용찬(Yongchan Kim) 대한기계학회 2019 대한기계학회 춘추학술대회 Vol.2019 No.11
In this paper, the simulation model of a hybrid cooler combining vapor compression and natural circulation cycles was developed to investigate the effects of operating parameters on the system performance. The model for the vapor compression cycle was developed based on the ORNL (Oak Ridge National Laboratory, 1983) heat pump model. The sectorial thermal resistance model was used to predict the performance of the natural circulation cycle. The predicted data using the model were compared with the measured data to decide appropriate heat transfer correlations and then to validate the model. The predicted data in the vapor circulation and natural circulation mode were consistent with the measured data within relative deviations of 2.3% and 5.5%, respectively. The predicted results of the vapor compression cycle showed a good agreement with the measured data.