• 대한기계학회논문집B
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• 제22권8호
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• pp.1083-1090
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• 1998

A kind of three-way check valve, so called hydraulic calve was proposed for the substitute of the density lock of passive reactor such as SPWR (System-Integrated Pressurized Water Reactor). The function of the valve are the separation of the borated water from main coolant loop for normal operation and the insurge of the water into the loop for shutdown and the removal of the decay power when the main coolant flow rate is not enough. To verify the operability and the characteristics of the valve, experimental works were executed with 1/3 scale model calve. Also a diffuser model was proposed for the theoretical analysis of the valve.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2004년도 추계학술발표회 발표논문집
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• pp.313-314
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• 2004

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.711-712
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• 2005

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.669-670
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• 2005

• Nuclear Engineering and Technology
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• 제31권1호
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• pp.17-28
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• 1999

A thermal-hydraulic analysis is conducted on the loss-of-coolant-accident (LOCA) during shutdown operation of YGN Units 3/4. Based on the review of plant-specific characteristics of YGN Units 3/4 in design and operation, a set of analysis cases is determined, and predicted by the RELAP5/MOD3.2 code during LOCA in the hot-standby mode. The evaluated thermal-hydraulic phenomena are blowdown, break flow, inventory distribution, natural circulation, and core thermal response. The difference in thermal-hydraulic behavior of LOCA at shutolown condition from that of LOCA at full power is identified as depressurization rate, the delay in peak natural circulation timing and the loop seal clearing (LSC) timing. In addition, the effect of high pressure safety injection (HPSI) on plant response is also evaluated. The break spectrum analysis shows that the critical break size can be between 1% to 2% of cold leg area, and that the available operator action time for the Sl actuation and the margin in the peak clad temperature (PCT) could be reduced when considering uncertainties of the present RELAP5 calculation.

• Nuclear Engineering and Technology
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• 제26권1호
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• pp.19-31
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• 1994

기사용 핵연료 저장조에 대한 열수력 해석과 관련된 인자들이 열수력 해석에 미치는 영향에 대한 분석을 수행하였다. 기사용 핵연료에서 발생하는 붕괴열(decay heat)을 제거하기 위해 일어나는 자연 순환(natural circulation)현상을 모사하기 위해 단순화된 유동망(simplified flow network)해석 모델을 사용하였다. 기사용 핵연료 저장조의 각 셀에 저장되는 연료 집합체에서 발생하는 붕괴열을 제거하기 위해 흐르는 유량의 압력 손실량이 자연순환을 일으키는 밀도차이에 의해 생성되는 구동력(driving force)과 평형을 이루는 관계를 이용하여 지배 방정식을 유도하였다. 그러나 유량, 저항 계수, 붕괴열, 밀도 등의 변수들이 서로 종속 관계를 갖기 때문에 반복 계산을 통해 해를 얻게 된다. 본 해석을 적용한 영광 3, 4호기의 경우, 12채널을 고려하였고 사용되는 입력 (저항 계수, 붕괴열)을 보수적으로 결정하였다. 본 연구를 통해 영광 3, 4호기 기사용 핵연료 저장조의 열수력 특성을 구하였다. 또한 유동로를 따라 형성되는 유동 저항중에 기하학적 요인에 의한 압력 손실은, 기사용 핵연료 저장조의 경우 압력 용기내의 유동과 달리 천이 영역(transition region)이 존재하게 되므로 Reynolds수에 민감한 것을 알 수 있다. 간극 유동은 조밀화된 연료 집합체 (consolidated fuel assembly)가 아닌 경우 무시할 수 있었다.

• 한국안전학회지
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• 제12권1호
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• pp.77-93
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• 1997

The natural convection and combined heat transfer induced by fire in a rectangular enclosure is numerically studied. The model for this numerical analysis is partially opened, it is divided by a vertical baffle projecting from ceiling. The solution procedure Includes the standard k- $\varepsilon$ model for turbulent flow and the discrete ordinates method (DOM ) is used for the calculation of radiative heat transfer equation. In this study, numerical simulation on the combined naturnal convection and radiation is carried out in a partial enclosure filled with absorbed-emitted gray media, but is not considered scattering problem. The velocity vectors, streamlines, and isothermal lines are compared the results of pure convection with those of the combined convection-radiation, the combined heat transfer. Comparing the results of pure convection with those of the combined convection-radiation, the combined heat transfer analysis shows the stronger circulation than those of the pure convection. Three different locations of heat source are considered to observe the effect of heat source location on the heat transfer phenomena. As the results, the circulation and the heat transfer In the left region from heating block are much more influenced than those in the right region. It is also founded that the radiation effect cannot be neglected in analyzing the building in fire.

• Nuclear Engineering and Technology
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• 제54권8호
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• pp.3166-3175
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• 2022

The most numerical investigations of the thermal-hydraulic phenomena following the loss of the residual heat removal capability during the mid-loop operation of the pressurized water reactor were performed according to simplifications and are not sufficiently accurate. To perform more accurate and more reliable predictions of thermal-hydraulic accidents in a nuclear power plant using computational fluid dynamics codes, a more detailed methodology is needed. Modelling results identified that thermal stratification and natural convection are observed. Temperatures of lower monitoring points remain low, while temperatures of upper monitoring points increase over time. The water in the heated region, in the upper unheated region and the pipe region was well mixed due to natural convection, meanwhile, there is no natural convection in the lower unheated region. Water temperature in the pipe region increased after a certain time delay due to circulation of flow induced by natural convection in the heated and upper unheated regions. The modelling results correspond to the experimental data. The developed computational fluid dynamics methodology could be applied for modelling of two-component single/two-phase natural convection and thermal stratification phenomena during the mid-loop operation of the pressurized water reactor or other nuclear and non-nuclear installations at similar conditions.

• Ecology and Resilient Infrastructure
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• 제6권2호
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• pp.109-119
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• 2019

국내의 많은 저수심 저수지들은 다양한 수질오염물질의 유입으로 인해 부영양화가 진행되고 있으며, 해마다 반복적으로 표층의 녹조 발생과 저층의 빈산소화를 겪고 있다. 이를 방지하기 위한 대책으로 저수지의 성층현상을 완화하는 기존 기술들이 있으나 대부분 동력이 필요하며 비경제적인 측면으로 인해 도입이 어려운 실정이다. 본 연구에서는 바람과 수류의 자연에너지를 활용하는 무동력 수류순환시스템을 개발하고 상이한 조건을 갖는 두 저수지를 대상으로 테스트베드를 구축, 운영하여 현장적용성을 검토하였다. 수류순환시스템을 모사한 전산유체역학 (CFD) 모의 결과, 하향류가 유도되어 표층과 심층 사이의 성층현상을 완화시키고, 영향반경은 약 30 m에 달하는 것으로 해석되었다. 테스트베드에 대한 장기 모니터링 결과, 수류순환 작용에 의해 DO의 변동을 완만하게 하고, DO 과포화 현상을 저감하며, pH의 과도한 상승을 방지하는 등 다양한 수질개선 효과가 관찰되었다. 본 수류순환시스템의 현장적용성을 제고하기 위해서는 홍수시 및 저수심 조건에 대한 대응방안 마련이 필요한 것으로 판단된다.

• 한국분무공학회지
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• 제1권1호
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• pp.35-43
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• 1996

A vaporization model for single component fuel droplet has been developed for applying to sub- and supercritical conditions. This model can account for transient liquid heat ins and circulation effect inside the droplet, forced and natural convection, Stefan flow effect, real gas effect and ambient gas solubility into the liquid droplet in high-pressure conditions. Thermodynamic and transport properties are calculated as functions of temperature and pressure in both phases. Numerical calculations are carried out for several validation cases with the detailed experimental data. Numerical results confirm that this supercritical vaporization model is applicable to the high-pressure conditions encountered in the combustion processes of diesel engine.