• 한국유체기계학회 논문집
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• 제19권5호
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• pp.50-60
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• 2016

A design methodology of the modeled test facility to conserve an injection performance of a passive safety injection system is proposed. This safety injection system is composed of a core makeup tank and a safety injection tank. Individual tanks are connected with pressure balance line on the top side and injection line on the bottom side. It is important to conserve the scaled initial injection flow rate and total injection time since this system can be operated by small gravity head without any active pumps. Differential pressure distribution of the injection line induced by the gravity head is determined by the vertical length and elevation of each tank. However, the total injection time is adjustable by the flow resistance coefficient of the injection line. The scaling methodology for the tank and flow resistance coefficient is suggested. A key point of this test facility design is a scaling analysis for the flow resistance coefficient. The scaling analysis proposed on this paper is based on the volume scaling law with the same vertical length to the prototype and can be extended to a model with a reduced vertical length. A set of passive injection test were performed for the tanks with the same volume and the different length. The test results on the initial flow rate and total injection time showed the almost same injection characteristics and they were in good agreement with the design values.

• Nuclear Engineering and Technology
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• 제47권4호
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• pp.443-453
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• 2015

A hybrid safety injection tank (H-SIT) can enhance the capability of an advanced power reactor plus (APR+) during a station black out (SBO) that is accompanied by a severe accident. It may a useful alternative to an electric motor. The operations strategy of the H-SIT has to be investigated to achieve maximum utilization of its function. In this study, the master logic diagram (i.e., an analysis for identifying the differences between an H-SIT and a safety injection pump) and an accident case classification were used to determine the parameters of the H-SIT operation. The conditions that require the use of an H-SIT were determined using a decision-making process. The proper timing for using an H-SIT was also analyzed by using the Multi-dimensional Analysis of Reactor Safety (MARS) 1.3 code (Korea Atomic Energy Research Institute, Daejeon, South Korea). The operation strategy analysis indicates that a H-SIT can mitigate five types of failure: (1) failure of the safety injection pump, (2) failure of the passive auxiliary feedwater system, (3) failure of the depressurization system, (4) failure of the shutdown cooling pump (SCP), and (5) failure of the recirculation system. The results of the MARS code demonstrate that the time allowed for recovery can be extended when using an H-SIT, compared with the same situation in which an H-SIT is not used. Based on the results, the use of an H-SIT is recommended, especially after the pilot-operated safety relief valve (POSRV) is opened.

• 대한기계학회논문집B
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• 제40권3호
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• pp.165-172
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• 2016

노심보충탱크(Core Makeup Tank, CMT), 안전주입탱크(SafetyInjection Tank, SIT)와 자동감압계통(Auto Depressurization System, ADS)로 구성된 1 계열의 SMART 피동안전주입계통의 주입특성을 파악하기 위한 소형냉각재상실사고(SBLOCA) 모의에 대한 실험적 연구가 수행되었다. SBLOCA의시험은 0.4 인치 안전주입수 배관파단에 대해 수행되었으며, 정상상태 조건은 실험요건서에 제시된 시험 초기 조건을 만족시키도록 746초 동안 운전되었다. 노심 출력 및 안전주입 유량 등의 경계 조건도 적절히 모의되었으며, 안전주입계통 배관에서의 파단, 히터 트립 및 잔열곡선 인가, 원자로냉각재펌프 관성서행(Coastdown), 급수 중단, CMT 및 SIT의 주입, ADS #1 개방이 SBLOCA 시나리오에 따라 적절히 모의되었다. 노심지지원통 내부의 액체환산수위는 파단 초반에 감소하다가 CMT와 SIT가 주입되면서 서서히 회복되었으며, 피동안전주입계통의 주입유량이 노심 수위를 회복하기에 충분한 것으로 판단할 수 있다.

• 에너지공학
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• 제25권1호
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• pp.185-191
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• 2016

피동충수용 혼합형 안전주입탱크는 한국원자력연구원에서 제안한 원자력 피동안전계통의 한 종류로, 안전주입탱크의 상부와 가압기를 연결하여 모든 운전압력 조건에서 냉각수 주입이 가능하도록 개선한 시스템이다. 본 연구에서는 피동충수용 혼합형 안전주입탱크, 가압기와 원자력압력용기에 대한 압력 네트워크를 통해 피동충수용 혼합형 안전주입탱크와 가압기의 압력이 평형이 되는 조건을 이론적으로 도출하였으며, 개별효과시험장치를 이용하여 안전주입탱크에서 발생하는 다양한 열수력 현상(증기응축 및 열혼합 현상)들을 파악하였다.

• Nuclear Engineering and Technology
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• 제41권8호
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• pp.995-1004
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• 2009

The Advanced Power Reactor 1400 (APR1400) is an evolutionary advanced light water reactor (ALWR) based on the Optimized Power Reactor 1000 (OPR1000), which is in operation in Korea. The APR1400 incorporates a variety of engineering improvements and operational experience to enhance safety, economics, and reliability. The advanced design features and improvements of the APR1400 design include a pilot operated safety relief valve (POSRV), a four-train safety injection system with direct vessel injection (DVI), a fluidic device (FD) in the safety injection tank, an in-containment refueling water storage tank (IRWST), an external reactor vessel cooling system, and an integrated head assembly (IHA). Development of the APR1400 started in 1992 and continued for ten years. The APR1400 design received design certification from the Korean nuclear regulatory body in May of2002. Currently, two construction projects for the APR1400 are in progress in Korea.

• 한국유체기계학회 논문집
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• 제4권3호
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• pp.53-61
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• 2001

Vortex type Fluidic Device(FD) which is installed at the bottom of Safety Injection Tank(SIT) controls the discharge flow rate from the tank. In case of loss of coolant accident the injection water flows into primary system in two steps; initial high flow rate for certain period of time and subsequent low flow rate. By two-step control of the discharge flow rate, FD can ensure the effective use of water in the tank. A small-scale FD has been tested to obtain a required flow characteristics maintaining full pressure and height of prototype, which are the major contributing parameters. Through the testing of many different arrangements of internal geometry of FD, most appropriate one was selected and its performance data was obtained. As characteristics of FD, time dependent Euler number, flow rate and pressure are presented and discussed. Also a method to predict the full size FD is presented.

• 대한기계학회논문집B
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• 제41권10호
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• pp.675-683
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• 2017

본 연구에서 원자력 발전용 비상노심냉각 장치인 안전주입탱크의 재충수 단계에 대한 유량에 대한 이론해석을 수행했다. 이론해석을 통해 재충수 단계 유동에 대한 이론 모형을 정립하고 재충수 단계에 대한 비선형 유량방정식을 구하고, 테일러 급수 전개법을 통해 근사유량방정식과 냉각수의 자유표면 높이변화와 유량변화를 예측할 수 있는 이론해들을 구했다. 기존연구에 나와 있는 실험과 비교하여 이론해의 유용성을 검증했다.

• 한국전산유체공학회지
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• 제19권1호
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• pp.64-72
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• 2014

This study aimed at assessing the analysis capability of thermal-hydraulic computer code, MARS for the behaviors of the core make-up tank (CMT). The sensitivity study on the nodalization to simulate the CMT was conducted, and the MARS calculations were compared with KAIST experimental data and RELAP5/MOD3.3 calculations. The 12-node model was fixed through a nodalization study to investigate the effect of the number of nodes in the CMT (2-, 4-, 8-, 12-, 16-node). The sensitivity studies on various parameters, such as water subcooling of the CMT, steam pressure, and natural circulation flow were done. MARS calculations were reasonable in the injection time and the effects of several parameters on the CMT behaviors even though the mesh-dependency should be properly treated for reactor applications.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2001년도 유체기계 연구개발 발표회 논문집
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• pp.425-432
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• 2001

Fluidic valve is adopted in APR1400 to control passively the flow rate of cooling water from the safety injection tank. It is necessary to establish independent evaluation guideline for the flow characteristics of fluidic valve in order to secure safety. Three dimensional numerical model for fluidic valve is developed and numerical results are compared with experimental data obtained at KAERI in order to verify numerical simulation. Also influence of the grid number and the turbulence model were investigated. In addition, variation of flow rate is investigated at various elapsed times after valve operating, and flow characteristics are analyzed at low and high flow rate conditions, respectively.

• Nuclear Engineering and Technology
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• 제54권5호
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• pp.1890-1901
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• 2022

We have assessed the applicability of the thermal-hydraulic system analysis code, SPACE, to a small modular reactor called SMART. For the assessment, the experimental data from a scale-down integral-test facility, SMART-ITL, were used. It was conformed that the SPACE code unrealistically calculates the safety injection flow rate through the CMT and SIT during a small-break loss-of-coolant experiment. This unrealistic behavior was due to the overprediction of interfacial heat transfer at the steam-water interface in a vertically stratified flow in the tanks. In this study, a special thermal-hydraulic component model has been developed to realistically calculate the interfacial heat transfer when a strong non-equilibrium two-phase flow is formed in the CMT or SIT. Additionally, we developed a special heat structure model, which analytically calculates the heat transfer from the hot steam to the cold tank wall. The combination of two models for the tank are called the special component model. We assessed it using the SMART-ITL passive safety injection system (PSIS) test data. The results showed that the special component model well predicts the transient behaviors of the CMT and SIT.