• 공업화학
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• 제21권5호
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• pp.481-487
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• 2010

최근 에너지 효율이 높은 공정기술의 수요가 증가하면서 분리막을 이용한 기체분리가 많은 연구자들의 관심을 모으고 있다. 현재 분리막에 의한 기체 분리 시장은 고분자막이 독점하고 있으며 탄화수소와 같은 응축기체 분리시장이 휠씬 큼에도 불구하고 주로 비응축 기체분리에 제한되고 있다. 이는 고분자 재료의 물성에 한계가 있기 때문이다. 제올라이트막이나 제올라이트/고분자 복합막이 제올라이트의 우수한 분리력과 화학적/열적 특성으로 인해 고분자막의 한계를 극복할 수 있는 대안이 될 수 있다. 이번 총설에서는 이러한 기체분리를 위한 제올라이트막과 제올라이트/고분자 복합막에 대해 간략히 소개하고자 한다.

• 한국시뮬레이션학회논문지
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• 제13권2호
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• pp.13-21
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• 2004

The thermal-hydraulic model ARTS which was based on the RETRAN-3D code adopted in the domestic full-scope power plant simulator which was provided in 1998 by KEPRI. Since ARTS is a generalized code to model the components with control volumes, the smaller time-step size should be used even if converged solution could not get in a single volume. Therefore, dedicated models which do not force to reduce the time-step size are sometimes more suitable in terms of a real-time calculation and robustness. In the case of PRT(Pressurizer Relief Tank) model, it is consist of subcooled water in bottom and non-condensable gas in top. The sparger merged under subcooled water enhances condensation. The complicated thermal-hydraulic phenomena such as condensation, phase separation with existence of non-condensable gas makes difficult to simulate. Therefore, the PRT volume can limit the time-step size if we model it with a general control volume. To prevent the time-step size reduction due to convergence failure for simulating this component, we developed a dedicated model for PRT. The dedicated model was expected to provide substantially more accurate predictions in the analysis of the system transients. The results were resonable in terms of accuracy, real-time simulation, robustness and education of operators, complying with the ANSI/ANS-3.5-1998 simulator software performance criteria and RETRAN-3D results.

• 한국기계가공학회지
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• 제15권2호
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• pp.31-37
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• 2016

In the steam system, a stream trap valve discharges a condensate and a non-condensable gas. It also prevents stream from being leaked. The free float stream trap valve is a mechanical type of stream trap. The valve is opened when a hallow ball is floated due to the density of the condensate through the condensate flows into the valve. On the other hand, when the flow of the condensate is completed, the valve is closed as the float subsides due to the weight of the structure and the stream is blocked. In addition, the bimetal lifts the hallow ball, which discharges the non-condensable gas. In this study, the performance of the properties of the free float stream trap valve, the method of support for three points, and the orifice design are researched. Moreover, the condensate discharge capacity of the free float stream trap valve is calculated from the experiment.

• 설비공학논문집
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• 제8권4호
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• pp.510-518
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• 1996

The study presents experimental and theoretical analysis focusing on the infulence of a noncondensable gas upon the absorption enhancement that is obtained by Marangoni convection generated by the addition of the surfactant. The shadowgraph method is adopted in this visualization. As a result of absorption phenomena with shadowgraph photos, the different patterns of Marangoni convection cells are observed in accordance with the various amounts of noncondensable gas. Furthermore, non dimensional number K(Ma/Ra) is introduced to calculate the value of surface tension difference theoretically for the comparison with the various amount of non condensable gas in absorber.

• 한국산학기술학회논문지
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• 제19권4호
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• pp.517-524
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• 2018

본 연구의 목표는 수평 관외 초소수성 튜브에서 비응축가스(NCG)의 영향을 관찰하고, 이를 일반 알루미늄 튜브의 응축 현상과 비교하는 것이다. 초소수성 튜브 제작을 위해 Self-Assembled Monolayer(SAM) 코팅으로 알루미늄 튜브의 외부를 표면개질 했다. 응축 성능을 나타내기 위해 총합 열전달계수를 사용하였고, 이 값으로 응축 성능을 비교 검토하였다. 본 연구의 주요 변수는 비응축가스 질량 분율로, 0.08에서 0.45의 범위에서 실험을 진행하였다. 응축 실험을 통해 비응축가스 질량 분율이 낮아질수록 응축 성능이 SAM 튜브와 일반 튜브에서 모두 향상되는 것을 확인했다. SAM 튜브에서 적응축 열전달 성능은 일반 튜브 대비하여 평균 약 1.9배에서 2.5배 정도 큰 것을 관찰하였다. SAM 튜브에서 비응축가스 질량 분율이 낮아지면서 응축 성능 상승폭이 감소하게 되는데, 이는 Flooded 응축 현상이 발현되었기 때문이다. 응축이 더 활발하게 진행되면 SAM 튜브에서 막응축이 일어나는 것을 관찰하였고, 이 때 성능은 일반 알루미늄 튜브보다도 저하된 성능을 보였다. SAM 알루미늄 튜브에서 Flooded 응축과 막응축이 일어나는 원인으로 표면에서의 Pinning 효과를 이용하여 설명하였다. 결론적으로, SAM 튜브를 실제 응축기에 적용해 표면개질로 인한 응축 성능 개선 효과를 얻기 위해서는 적응축 또는 Flooded 응축이 일어나는 조건으로 응축기 내 환경 조성을 해야 한다.

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2008년도 춘계학술대회 논문집
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• pp.456-459
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• 2008

The 10t/d pyrolysis demonstration plant for waste tire recycling have been constructed and operated for commissioning of the plant. The plant have the tube reactor with chain conveyer attached disk. The reactor temperature is 500$\sim$600deg.C and pressure is -80$\sim$-100mmHg. Non-condensable gas is used as fuel for pyrolysis heat source.

• 한국에너지공학회:학술대회논문집
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• 한국에너지공학회 2003년도 춘계 학술발표회 논문집
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• pp.371-376
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• 2003

원자력 발전소에서 격납건물 계통의 건전성 유지는 냉각재상실사고(Loss of Coolant Accident: LOCA) 및 주증기관 파단(Main Steam Line Break : MSLB) 사고와 같은 설계기준사고 시 격납건물의 최대 온도/압력을 평가하는 격납건물 성능 평가는 격납용기 내에 방사능 물질을 효율적으로 가두어 방사능 피해로부터 공공의 안전을 확보할 수 있느냐 하는 관건이다.(중략)

• Nuclear Engineering and Technology
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• 제41권5호
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• pp.575-602
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• 2009

In the wake of the Three Mile Island accident, vigorous research efforts were initiated to acquire a basic knowledge of the progression and consequences of accidents that involve a substantial degree of core degradation and melting. The primary emphasis of this research was placed on containment integrity, with: i) hydrogen combustion-detonation, ii) steam explosion, iii) direct containment heating (DCH), and iv) melt attack on the BWR Mark-I containment shell identified as energetic processes that could lead to early containment failure (i.e., within the first 24 hours of the accident). Should the core melt fail the reactor vessel, then non-condensable gas production from Molten Core-Concrete Interaction (MCCI) was identified as a mechanism that could fail the containment by pressurization over the long term. One signification question that arose as part of this investigation was the effectiveness of water in terminating an MCCI by flooding the interacting masses from above, thereby quenching the molten core debris and rendering it permanently coolable. Successful quenching of the core melt would prevent basemat melt through, as well as continued containment pressurization by non-condensable gas production, and so the accident progression would be successfully terminated without release of radioactivity to the environment. Based on these potential merits, ex-vessel corium coolability has been the focus of extensive research over the last 20 years as a potential accident management strategy for current plants. In addition, outcomes from this research have impacted the accident management strategies for the Gen III+LWR plant designs that are currently being deployed around the world. This paper provides: i) an historical overview of corium coolability research, ii) summarizes the current status of research in this area, and iii) highlights trends in severe accident management strategies that have evolved based on the findings from this work.

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.439-458
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• 2013

REX-10 is a fully-passive small modular reactor in which the coolant flow is driven by natural circulation, the RCS is pressurized by a steam-gas pressurizer, and the decay heat is removed by the PRHRS. To confirm design decisions and analyze the transient responses of an integral PWR such as REX-10, a thermal-hydraulic system code named TAPINS (Thermal-hydraulic Analysis Program for INtegral reactor System) is developed in this study. Based on a one-dimensional four-equation drift-flux model, TAPINS incorporates mathematical models for the core, the helical-coil steam generator, and the steam-gas pressurizer. The system of difference equations derived from the semi-implicit finite-difference scheme is numerically solved by the Newton Block Gauss Seidel (NBGS) method. TAPINS is characterized by applicability to transients with non-equilibrium effects, better prediction of the transient behavior of a pressurizer containing non-condensable gas, and code assessment by using the experimental data from the autonomous integral effect tests in the RTF (REX-10 Test Facility). Details on the hydrodynamic models as well as a part of validation results that reveal the features of TAPINS are presented in this paper.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.611-623
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• 2024

The ISP-47 TOSQAN experiment was analyzed with containmentFOAM which is an open-source CFD code based on OpenFOAM. The containment phenomena taking place during the experiment are gas mixing, stratification and wall condensation in a mixture composed of steam and non-condensable gas. The k-ω SST turbulence model was adopted with buoyancy turbulence models. The wall condensation model used is based on the diffusion layer approach. We have simulated the full TOSQAN experiment which had a duration 20000 s. Sensitivity studies were conducted for the buoyancy turbulence models with SGDH and GGDH and there were not significant differences. All the main features of the experiments namely pressure history, temperature, velocity and gas species evolution were well predicted by containemntFOAM. The simulation results confirmed the formation of two large flow stream circulations and a mixing zone resulting by the combined effects of the condensation flow and natural convection flow. It was found that the natural convection in lower region of the vessel devotes to maintain two large circulations and to be varied the height of the mixing zone as result of sensitivity analysis of non-condensing wall temperature. The computational results obtained with the 2D mesh grid approach were comparable to the experimental results.