• Transactions of the Korean Society of Mechanical Engineers
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• v.17 no.5
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• pp.1313-1320
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• 1993

Flow patterns inside the riser section and the effects of the heater inlet-and exit-restrictions, liquid charging level and the heater inlet subcooling on the flow characteristics inside an open two-phase natural circulation loop were studied experimentally. Three basic circulation modes were observed ; periodic circulation (A)(flow oscillations with incubation(no boiling) period), continuous circulations(stable operation mode with no flow oscillations), and periodic circulation (B) (flow oscillations with continuous boiling). The circulation rate increases and then decreases with the increase of the heating rate and the maximum circulation rate appears with the continuous circulation mode. The decrease of the inlet-restriction or the increase of the exitrestriction destabilizes the system. When the liquid charging level or the inlet subcooling decreases, the continuous circulation mode starts at the lower heating rate and the system is stabilized.

• Transactions of the Korean Society of Mechanical Engineers
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• v.14 no.4
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• pp.920-926
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• 1990

본 연구에서는 Fig.1과 같은 2상 자연순환 회로의 1차원 해석을 수행하고, 액 상의 과냉정도와 각 상 영역에서의 밸브 마찰저항이 순환유속에 미치는 영향을 살펴보 므로써 정적 불안정의 조건을 알아보는데 있다. 본 모델에서는 유한 길이를 갖는 증 발기와 응축기를 고려하였으며, 정적 불안정의 가능성을 해석적으로 보여주기 위해 간 단한 모델(point-heat-source/sink)도 함께 다루었다.

• Proceedings of the KSME Conference
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• 2003.04a
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• pp.1897-1902
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• 2003

An 1/21.6 scaled experimental facility was prepared utilizing the results of a scaling analysis to simulate the APRI400 reactor and insulation system. The behaviors of the boiling-induced two-phase natural circulation flow in the insulation gap were observed, and the liquid mass flow rates driven by natural circulation loop were measured by varying the wall heat flux, upper exit slot area and configuration. And non-heating experiments have also been performed and discussed to certify the hydraulic similarity of the heating experiments by injecting air equivalent to the steam generated in the heating experimental condition.

• Proceedings of the KSME Conference
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• 2004.04a
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• pp.1927-1932
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• 2004

A 1/21.6 scaled non-heating experimental facility was prepared utilizing the results of a scaling analysis to simulate the APR1400 reactor and insulation system. The behaviors of the air bubble-induced two-phase natural circulation flow in the insulation gap were observed, and the liquid mass flow rates driven by natural circulation loop were measured by varying the injected air flow rate and distribution. As the injected air flow rates increased, the natural circulation flow rates also increased. Both the longitudinal and the latitudinal distributions of the injected air affected the natural circulation flow rates, especially, the longitudinal effect is more larger.

• Nuclear Engineering and Technology
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• v.15 no.3
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• pp.188-196
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• 1983

A simplified fast-running system code is developed to simulate loop transients such as pump coastdown, loop failures and natural circulation. Special emphasis is put on the numerical investigation of the natural circulation system with multiloop. For this purpose, 5 governing equations are derived, and they are discretized by the space-time integration technique. The developed computer program is applied to three sample problems; transition from 2-loop to 1-loop operation, transition from 1-loop to 2-loop operation, and the transient behavior with decay power in the case of 2-loop operation.

• Proceedings of the KSME Conference
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• 2003.11a
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• pp.781-785
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• 2003

This work presents a numerical analysis of two-phase natural circulation flow in reactor cavity under external vessel cooling. Steady, incompressible, three-dimensional Reynolds-averaged Navier-Stokes equations for multiphase flows with zero equation turbulence model are solved to predict the shear key effect on the circulation rate of cooling water and the distribution of void fraction according to the different mass flow of inlet air. Results show that shear key has a positive effect on the circulation rate of cooling water and induce a local increase of void fraction below the shear key, but not remarkably.

• Journal of Energy Engineering
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• v.28 no.4
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• pp.103-110
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• 2019

The domestic innovative power reactor named iPOWER will employ the passive molten corium cooling system(PMCCS) to cool down and stabilize the core melt in the severe accident. The final design concept of the PMCCS is yet to be determined, but the in-vessel retention through external reactor vessel cooling has been also considered as a viable strategy to cope with the severe accident. In this study, the two-phase natural circulation flow established between the reactor vessel and the insulation was simulated using a thermal-hydraulic system code, MARS-KS. The flow path of cooling water was modeled with one-dimensional nodes, and the boundary condition of the heat load from the molten core was defined to estimate the naturally-driven flow rate. The evolution of major thermal-hydraulic parameters were also evaluated, including the temperature and the level of cooling water, the void fraction around the lower head of the reactor vessel, and the heat transfer mode on its external surface.

• Proceedings of the KSME Conference
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• 2007.05b
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• pp.3086-3091
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• 2007

When a molten corium is relocated in a lower head of a reactor vessel, the ERVC (External Reactor Vessel Cooling) system is actuated as coolant is supplied into a reactor cavity to remove a decay heat from the molten corium during a severe accident. To achieve this severe accident mitigation strategy, the two-phase natural circulation flow in the annular gap between the external reactor vessel and the insulation should be formed sufficiently by designing the coolant inlet/outlet area and gap size adequately on the insulation device. For this reason, one-dimensional natural circulation flow tests were conducted to estimate the natural circulation flow under the ERVC condition of APR1400. The experimental facility is one-dimensional and scaled-down as the half height and 1/238 rectangular channel area of the APR1400 reactor vessel. As the water inlet area increased, the natural circulation mass flow rate asymptotically increased, that is, it converged at a specific value. And the circulation mass flow rate also increased as the outlet area, injected air flow rate, and outlet height increased. But the circulation mass flow rate was not changed along with the external water level variation if the water level was higher than the outlet height.

• 한국전산유체공학회:학술대회논문집
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• 2008.03b
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• pp.308-311
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• 2008

As a severe accident mitigation strategy in a nuclear power plant, ERVC(External Reactor Vessel Cooling) has been proposed. Under ERVC conditions, where a molten corium is relocated in a reactor vessel lower head, a natural circulation two-phase flow is driven in the annular gap between the reactor vessel wall and its insulation. This flow should be sufficient to remove the decay heat of the molten corium and maintain the integrity of the reactor vessel. Preliminary experimental study was performed to estimate the natural circulation two-phase flow. The experimental facility which is one dimensional, the half height, and the 1/238 channel area of APR1400, was prepared and the experiments were carried out to estimate the natural circulation two-phase flow with varying the parameters of the coolant inlet area, the heat rate, and the coolant inlet subcooling. In results, the periodic circulation flow was observed and the characteristics were varied from the experimental parameters. The frequency of the natural circulation flow rate increased as the wall heat flux increased.

• Proceedings of the Korea Water Resources Association Conference
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• 2010.05a
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• pp.952-956
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• 2010

저수지에 설치된 물순환장치는 저수지 수문상황과 자연조건의 변화에 따라 유동특성이 상이하므로 연구자가 고려하는 다양한 조건에서 현장 측정하기는 불가능하다. 이런 문제를 대체하는 방안으로 전산유체유동(CFD) 모형을 적용한 모사를 실시함으로서 다양한 조건에 따른 효과를 평가할수 있게 된다. 본 연구에서는 전산유체유동을 통한 대류식 물순환장치의 유동영향범위와 수질변화 등을 평가하고, 다양한 조건에서 모사를 실시하여 최적운영방안을 도출하고 실제운영에 활용토록 하고자 한다. 수체거동을 모사하기 위해 실제 저수지를 형상화한 Domain을 3가지로 구성하였다. 첫번째는 반경 20m, 깊이 40m Domain에 물순환장치를 중앙에 설치한 것이며(D20), 두 번째는 반경 40m, 깊이 40m에 두 개의 물순환장치를 양쪽에 설치하였고(D40), 세 번째는 반경 100m, 깊이 40m로 설정(D100)하였고 양쪽에 두 개의 물순환장치를 설치한 것으로 구성하였다. CFD에 의한 개별 대류식 순환장치의 유동모사결과 D20은 시간의 경과에 따라 수온성층이 하강하는 현상이 나타났으며 이러한 결과로 판단할때 40m 간격으로 대류식 순환장치를 설치하여 운영하면 탈성층이 나타날 수 있을것으로 판단되었다. D40에 대하여 CFD에 의한 유동모사를 실시하였으며 시간의 경과에 따라 수온성층의 변화는 나타나지 않았다. 이러한 결과로 판단할때 40m 간격으로 한줄로 대류식 순환장치를 설치하여 운영하면 성층을 깨는 현상은 나타나지 않을 것으로 평가되었다. 반면 Dye테스트시 심층에서 상승한 수체는 수온성층 표면에서 수평방향으로 계속 퍼져 나가면서 옆장치에서 상승된 수체와 혼합이 활발히 이루어 지는 현상을 나타내었다. 장치간 거리가 100m인 대류식 물순환장치에 의한 유동모사시 수온성층의 변화는 전혀 나타나지 않았으며, Dye테스트시 심층에서 상승한 수체는 수온성층 위에서 수평방향으로 퍼져 나가면서 옆에서 가동되는 장치에서 상승된 수체와 혼합 현상을 나타내기는 하나 D40보다 혼합시간이 더 걸리는 것으로 나타났다.