• 한국전산유체공학회:학술대회논문집
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• 한국전산유체공학회 2010년 춘계학술대회논문집
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• pp.380-388
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• 2010

A thermal-hydraulic code, named CUPID, has been developed for the analysis of transient two-phase flows in nuclear reactor components. A two-fluid three-field model was used for steam-water two-phase flows. To obtain numerical solutions, the finite volume method was applied over unstructured cell-centered meshes. In steam-water two-phase flows, a phase change, i.e., evaporation of condensation, results in a great change in the flow field because of substantial density difference between liquid and vapor phases. Thus, two-phase flows are very sensitive to the local pressure that determines the phase change. This in turn puts emphasis on the accurate evaluation of local pressure gradient. This paper presents a new numerical scheme to evaluate the pressure gradient at cell centers on unstructured meshes. The results of the new scheme for a simple test function a gravity-driven cavity, and a wall boiling two-phase flow are compared with those of the previous schemes in the cupid code.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2628-2641
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• 2023

Nuclear safety is the lifeline for the development and application of nuclear energy. In severe accidents of pressurized water reactor (PWR), aerosols, as the main carrier of fission products, are suspended in the containment vessel, posing a potential threat of radioactive contamination caused by leakage into the environment. The gas-phase aerosols suspended in the containment will settle onto the wall or sump water through the natural deposition mechanism, thereby reducing atmospheric radioactivity. Aiming at the low accuracy of the aerosol model in the ISAA code, this paper improves the natural deposition model of aerosol in the containment. The aerosol dynamic shape factor was introduced to correct the natural deposition rate of non-spherical aerosols. Moreover, the gravity, Brownian diffusion, thermophoresis and diffusiophoresis deposition models were improved. In addition, ABCOVE, AHMED and LACE experiments were selected to validate and evaluate the improved ISAA code. According to the calculation results, the improved model can more accurately simulate the peak aerosol mass and respond to the influence of the containment pressure and temperature on the natural deposition rate of aerosols. At the same time, it can significantly improve the calculation accuracy of the residual mass of aerosols in the containment. The performance of improved ISAA can meet the requirements for analyzing the natural deposition behavior of aerosol in containment of advanced PWRs in severe accident. In the future, further optimization will be made to address the problems found in the current aerosol model.

• 한국안전학회지
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• 제35권4호
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• pp.84-91
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• 2020

The Korean nuclear industry developed the SPACE (Safety and Performance Analysis Code for nuclear power plants) code and this code adpots two-phase flows, two-fluid, three-field models which are comprised of gas, continuous liquid and droplet fields and has a capability to simulate three-dimensional model. According to the revised law by the Nuclear Safety and Security Commission (NSSC) in Korea, the multiple failure accidents that must be considered for accident management plan of nuclear power plant was determined based on the lessons learned from the Fukushima accident. Generally, to improve the reliability of the calculation results of a safety analysis code, verification work for separate and integral effect experiments is required. In this reason, the goal of this work is to verify calculation capability of SPACE code for multiple failure accident. For this purpose, it was selected the experiment which was conducted to simulate a Multiple Steam Generator Tube Rupture(MSGTR) accident with Passive Auxiliary Feedwater System(PAFS) operation by Korea Atomic Energy Research Institute (KAERI) and focused that the comparison between the experiment results and code calculation results to verify the performance of the SPACE code. The MSGR accident has a unique feature of the penetration of the barrier between the Reactor Coolant System (RCS) and the secondary system resulting from multiple failure of steam generator U-tubes. The PAFS is one of the advanced safety features with passive cooling system to replace a conventional active auxiliary feedwater system. This system is passively capable of condensing steam generated in steam generator and feeding the condensed water to the steam generator by gravity. As the results of overall system transient response using SPACE code showed similar trends with the experimental results such as the system pressure, mass flow rate, and collapsed water level in component. In conclusion, it could be concluded that the SPACE code has sufficient capability to simulate a MSGTR accident.

• Journal of Advanced Marine Engineering and Technology
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• 제39권5호
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• pp.563-569
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• 2015

A chemical reaction occurring in CSTR (Continuous Stirred Tank Reactor) is significantly affected by the concentration, temperature, pressure, and reacting time of materials, and thus it has strong nonlinear and time-varying characteristics. Also, when an existing linear PID controller with fixed gain is used, the performance could deteriorate or could be unstable if the system parameters change due to the change in the operating point of CSTR. In this study, a technique for the design of a fuzzy PD plus I controller was proposed for the temperature control of a CSTR process. In the fuzzy PD plus I controller, a linear integral controller was added to a fuzzy PD controller in parallel, and the steady-state performance could be improved based on this. For the fuzzy membership function, a Gaussian type was used; for the fuzzy inference, the Max-Min method of Mamdani was used; and for the defuzzification, the center of gravity method was used. In addition, the saturation state of the actuator was also considered during controller design. The validity of the proposed method was examined by comparing the set-point tracking performance and the robustness to the parameter change with those of an adaptive controller and a nonlinear proportional-integral-differential controller.

• Nuclear Engineering and Technology
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• 제48권1호
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• pp.246-258
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• 2016

The shield building of AP1000 was designed to protect the steel containment vessel of the nuclear reactor. Therefore, the safety and integrity must be ensured during the plant life in any conditions such as an earthquake. The aim of this paper is to study the effect of water in the water tank on the response of the AP1000 shield building when subjected to three-dimensional seismic ground acceleration. The smoothed particle hydrodynamics method (SPH) and finite element method (FEM) coupling method is used to numerically simulate the fluid and structure interaction (FSI) between water in the water tank and the AP1000 shield building. Then the grid convergence of FEM and SPH for the AP1000 shield building is analyzed. Next the modal analysis of the AP1000 shield building with various water levels (WLs) in the water tank is taken. Meanwhile, the pressure due to sloshing and oscillation of the water in the gravity drain water tank is studied. The influences of the height of water in the water tank on the time history of acceleration of the AP1000 shield building are discussed, as well as the distributions of amplification, acceleration, displacement, and stresses of the AP1000 shield building. Research on the relationship between the WLs in the water tank and the response spectrums of the structure are also taken. The results show that the high WL in the water tank can limit the vibration of the AP1000 shield building and can more efficiently dissipate the kinetic energy of the AP1000 shield building by fluid-structure interaction.

• 한국축산시설환경학회지
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• 제6권3호
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• pp.175-184
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• 2000

Lab-scale의 실험을 통하여 축산폐수의 액비화에 있어서 막 분리 기술의 도입에 따른 막 오염 특성과 투과특성에 대해 살펴본 결과 다음과 같은 결론을 얻을 수 있었다. 1. System의 안정적 운전을 위해서는 낮은 투과유속에서의 운전이 효과적이라 사료되며, Tmax가 지수 함수적으로 투과유속에 대해 감소하였다. 이를 통해서 예측식을 수립하여 운전에 있어서의 막 세정 시기를 결정할 수 있을 것으로 사료된다. 2. 전반적인 막 자체에 대한 순수투과저항을 관찰해본 결과 막 오염은 비가역적 영역보다는 가역적 영역에 의해 이루어진다고 사료된다. 3. 투과유속이 낮을 경우 막면 부착물에 의한 여과저항의 상승이 막 오염의 주된 원인이 되는 반면, 투과유속이 증가할수록 농도분극현상이 막 오염의 주된 원인이 된다고 사료된다. 따라서 높은 투과유속에서의 운전을 위해서는 이러한 농도 분극현상을 최소화 하기 위해서는 이러한 농도 분극현상을 최소화 하기 위하여 높은 전단응력을 제공하거나 막표면에 물리적 충격을 주어 농도 분극현상을 제어하는 방법이 추가되어야 할 것이라 사료된다. 4. 중력여과 및 간헐여과를 통한 막 분리 특성을 살펴본 결과 중력여과의 경우 별도의 흡입압력을 부여하지 않고 단지 수위차에 의해 생성되는 위치에너지에 의한 여과에서도 1.7LMH에서 약 3.5일간 안정되게 유지된 것을 확인할 수 있었으며, 간헐여과를 통해 농도 분극현상을 감소시킴으로 해서 연속여과보다 안정된 운전이 이루어졌다. 종합적으로 고찰해 봤을 때, 축산폐수의 액비화에 있어서 막 분리 기술의 도입은 그 유출수의 성상에 있어서 원수의 성상에 상관없이 일정한 질을 보이고 있음을 확인할 수 있었고, 공정의 안정적 유지를 위해서는 낮은 투과유속의 흡입과 정지의 간격이 비교적 긴 간헐여과 방식이 적합하다고 사료되며, 높이차를 이용한 중력여과 또한 추가적인 연구가 진행된다면 동력의 소모면에서 이점이 있을 것이라 사료된다.기는 축사의 난방 보조열원으로서 양호한 열효율을 나타내어 우리나라 축사시설에 적용가능성을 제시하였다. 본 지열교환기 시스템은 지열을 이용하는 환경보전형 에너지 시스템으로서 시설하기 간편하고 경제적이며 반영구적인 냉난방 및 환기시스템이다. 따라서, 우리나라 축산시설에 실용화될 경우에 우수한 대체에너지원으로 에너지 절감효과에도 크게 기여하리라고 전망된다.ble amount of acid mucin, Most of the medium sized and small mucous cells contained neutral mucin and sialomucin, but a few mucous cells contained neutral mucin and strongly sulfomucin or neutral combined with strongly sulfomucin and sialomucin. Most of the esophageal mucous cells pf Bryzoichthys lysimus contained small amount of neutral mucin, while on the other hand a feww mucous cells contained small amount of neutral mucin and minimal amount of sialomucin. But the esophageal mucous cells of Takifugu pardalis contained considerable amount of neutral mucin only.분해가 더욱 촉진되었으며, 30℃에서 교반 처리를 행한 경우가 10℃에서 교반 처리를 행한 경우 보다 지방분해가 더욱 촉진되었다. 산양유 원유는 30℃에서 교반 처리 시간이 연장되어도 지방분해는 뚜렷한 증가를 나타내지 않았다.와 표준체중군 여자에게서 가장 높게 나타났다. 5. 남자의 53.9%, 여자의 83.2%가 체중 조절에 관심이 있다

• 에너지공학
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• 제25권4호
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• pp.124-132
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• 2016

노심보충탱크 상부에 설치되는 유동분사기 형상에 따른 냉각수 주입특성 및 탱크 내에서의 열수력 현상 변화를 파악하기 위한 안전주입배관 2인치 파단 소형냉각재상실사고(SBLOCA) 모의시험이 잔열 및 피동잔열제거계통(PRHRS) 모의 없이 수행되었다. 두 가지 형상의 유동분사기를 설치하고 수행한 각각의 시험은 거의 유사한 초기 및 경계조건에서 수행되었으며, 이로 인해 반복시험에 대한 재현성이 충족되었다고 판단된다. 시험결과는 유동분사기의 종류(본 시험에서는 구멍의 개수에 해당)에 관계없이 유사한 열수력학적 거동을 보였으며, 초기 주입유량 관점에서는 구멍의 개수가 2배인 B형이 A형에 비해 좀 더 우수한 주입 성능을 보였다. 노심보충탱크 격리 밸브가 개방된 후 압력평형배관을 통해 유입되는 고온의 원자로냉각재는 상부 헤더에서 상대적으로 저온인 $50^{\circ}C$ 물과 혼합되면서 증기 응축과 같은 상변화에 의한 압력 변동을 동반하는 다차원 열유동 현상을 일으키게 된다. 이로 인해 초반부 노심보충탱크 주입 유량은 상온운전 조건에서 보다는 작게 되고, 일정시간 경과 후에는 유사한 주입유량 특성을 보였다.