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MARS-KS 코드를 이용한 SMART-ITL 피동안전계통 시험장치의 잔열 제거 특성 분석
전병국(Byong Guk Jeon),김연식(Yeon-Sik Kim),류성욱(Sung-Uk Ryu),배황(Hwang Bae),이성재(Sung-Jae Yi),박현식(Hyun-Sik Park) 대한기계학회 2015 대한기계학회 춘추학술대회 Vol.2015 No.11
SMART, an integral type small modular reactor developed in KAERI, received its design certificate in 2012 for the first time in the world and now its safety features are enhanced by equipping more passive safety systems with core makeup tank (CMT) and safety injection tank (SIT) that can be operated without any electricity supply. An integral test facility for SMART, SMART-ITL, contains several passive systems: passive residual heat removal systems (PRHRS), passive safety injection system (PSIS), and automatic depressurization system (ADS). In this paper, we are to compare the heat removal capacities among those systems using a best-estimate system analysis code, MARS-KS.
MARS 코드를 활용한 냉각기능상실사고 시 사용후핵연료 저장조의 열수력적 거동 예비 해석
전병국(Byong Guk Jeon),김병재(Byung Jae Kim),김기환(Ki Hwan Kim),김종록(Jong Rok Kim),문상기(Sang Ki Moon) 대한기계학회 2015 대한기계학회 춘추학술대회 Vol.2015 No.11
In a loss of cooling accident caused by a loss of off-site power, similar to the Fukushima accident, water inside a spent fuel storage pool heats up and evaporates by decay heat. That leads to uncovery and failure of spent fuels and subsequent release of radioactive materials. To avoid such severe consequence, it is important to identify the thermalhydraulic behavior of spent fuels under the accident. We are planning to conduct experiments with the ATHER facility. Prior to the experiments, for a loss of cooling accident, peak temperature of fuel claddings as well as water level is calculated using the best estimate code, MARS, under different decay powers and discussions have been made.
냉각기능상실사고 시 사용후핵연료 저장조의 열수력적 거동 특성
전병국(Byong Guk Jeon),김기환(Ki Hwan Kim),김병재(Byung Jae Kim),김종록(Jong Rok Kim),박종국(Jong Kuk Park),문상기(Sang Ki Moon) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
After the Fukushima nuclear power plant accident, several efforts have been made to ensure integrity of spent fuel pools as well as nuclear reactors under prolonged station blackout. Regardless of low individual decay heat level, release of radioactive materials from spent fuel pools can be tragic because of a large number of fuel assemblies. In this research, thermal hydraulic behavior and safety of fuel rods inside a subchannel of nuclear fuel under loss of cooling accidents were evaluated through a 5 by 5 heater rods - experiment. We chose three cases representing decay heat at 1 day, 1 week, and 1 month after shutdown, corresponding to 0.38 kW/rod, 0.21 kW/rod, and 0.11 kW/rod, respectively. At higher decay heat level, mixture water level was much escalated because of large void generation while the maximum rod temperature was increased fast. The vessel module, COBRA-TF, in the MARS code was assessed by comparing with the experiment result. The water mixture level as well as the wall temperature profile was not well represented by the code. The models are needed to be further improved.
MARS-KS 코드를 이용한 파단크기별 SMART 종합시험장치의 안전계통 특성 검증
전병국(Byong Guk Jeon),조연식(Yeon-Sik Cho),류성욱(Sung-Uk Ryu),배황(Hwang Bae),이성재(Sung-Jae Yi),서재승(Jae-Seung Suh),박현식(Hyun-Sik Park) 대한기계학회 2016 대한기계학회 춘추학술대회 Vol.2016 No.12
SMART, an integral type small modular reactor, was developed in KAERI and received its design certificate in 2012. The reactor is characterized by enhanced safety by removal of large diameter pipes and adoption of passive safety systems. An integral test facility for SMART was built in KAERI and a series of experiments have been performed to explore the thermal hydraulic phenomena that accompany the operation of safety systems. In parallel to the experiments, intense efforts have been made to simulate using a system code, MARK-KS. The code is devoted to calculate transients of nuclear power plant systems under postulated accidents. In this paper, for two representative accident scenarios with different pipe break sizes, we compared the calculation results with the experimental results and obtained good predictions.
MARS-KS 코드를 이용한 SMART 종합시험장치의 안전주입현상 분석
전병국(Byong Guk Jeon),류성욱(Sung-Uk Ryu),양진화(Jin-Hwa Yang),배황(Hwang Bae),이성재(Sung-Jae Yi),박현식(Hyun-Sik Park) 대한기계학회 2019 대한기계학회 춘추학술대회 Vol.2019 No.11
SMART, an integral type small modular reactor, was developed in KAERI and received its design certificate in 2012. The reactor is characterized by enhanced safety by removal of large diameter pipes and adoption of passive safety systems. An integral test facility for SMART was built in KAERI and a series of experiments have been performed to explore the thermal hydraulic phenomena that accompany the operation of passive safety systems. In parallel to the experiments, intense efforts have been made to simulate using a system code, MARK-KS. The code is devoted to calculate transients of nuclear power plant systems under postulated accidents. In this paper, the phenomena of safety water injection are analyzed using MARS-KS. Importance and limit of condensation prediction using the code were identified.
Hyobong Ryu(유효봉),Byong-Guk Jeon(전병국),Hwang Bae(배황),Sung-Uk Ryu(류성욱),Sun-Joon Byun(변선준),Sung-Jae Yi(이성재),Hyun-Sik Park(박현식) 대한기계학회 2015 대한기계학회 춘추학술대회 Vol.2015 No.11
An integral type reactor, SMART (System-integrated Modular Advanced ReacTor) has been recently equipped with an additional passive safety system, which maintains the reactor in a safe condition during the design basis accident without any AC power to drive the safety injection pumps and operator action. For verification of the SMART passive safety system, a single train of a passive safety system consisting of a core makeup tank (CMT), a safety injection tank (SIT), and two stages of an automatic depressurization system (ADS) were additionally attached to the existing SMART-ITL (Integral Test Loop for SMART) facility. In this paper, we describe the test procedure and test result of a SBLOCA simulation to evaluate the performance of the CMT, which has a flow distributor in the upper part. The test was carried out according to the sequence of events (SOE) for an SBLOCA scenario. Most of the thermal-hydraulic properties of the CMT, such as the pressure, temperature, injection flow rate, and water level were obtained during the test with the operation of the passive safety system. We conducted experiments using two types of CMT, which have the same volume but different aspect ratio, called CMT #1-1 and CMT #1-2 for a better understanding of the shape effect. Characteristic properties such as the pressure, thermal stratification, and injection behavior were studied and compared.