• Nuclear Engineering and Technology
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• 제56권3호
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• pp.1052-1065
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• 2024

Advanced Pressurized Water Reactors (APWRs) and Boiling Water Reactors (BWRs) employ a suppression pool as a heat sink to prevent containment overpressure. Steam can be discharged into the pool through multi-hole spargers or blowdown pipes in both normal and accident conditions. Direct Contact Condensation (DCC) creates sources of momentum and heat. The competition between these two sources determines the development of thermal stratification or mixing of the pool. Thermal stratification is of safety concern as it reduces the cooling capability compared to a completely mixed pool condition. In this work we develop a scaling approach to prediction of the thermal stratification in a water pool induced by steam injection through spargers. Experimental data obtained from large-scale pool tests conducted in the PPOOLEX and PANDA facilities, as well as simulation results obtained using validated codes are used to develop the scaling. Two injection orientations, namely radial injection through multi-hole Sparger Head (SH) and vertical injection through Load Reduction Ring (LRR), are considered. We show that the erosion rate of the cold layer can be estimated using the Richardson number. In this work, scaling laws are proposed to estimate both the (i) transient erosion velocity and (ii) the stable position of the thermocline. These scaling laws are then implemented into a 1D model to simulate the thermal behavior of the pool during steam injection through the sparger.

• Nuclear Engineering and Technology
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• 제38권1호
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• pp.61-68
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• 2006

CHF characteristics of nano- fluids were investigated with different volumetric concentrations of $TiO_2$ nanoparticles. Pool boiling experiments indicated that the application of nano-fluids, instead of pure water, as a cooling liquid significantly increased the CHF. SEM (scanning electron microscope) observations subsequent to the pool boiling experiments revealed that nanoparticles were coated on the heating surface during pool boiling of nano-fluids. In order to investigate the roles of nanoparticles in CHF enhancement ofb nano-fluids, pool boiling experiments were performed using (a) a nanoparticle-coated heater, prepared by pool boiling of nano-fluids, immersed in pure water and (b) a nanoparticle-coated heater immersed in nano-fluids. The results demonstrated two different roles of nanoparticles in CHF enhancement using nano-fluids: the effect of nanoparticles coated on the heater surface and the effect of nanoparticles suspended in nano- fluids.

• 대한기계학회논문집B
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• 제25권8호
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• pp.1037-1045
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• 2001

The effect of hysteresis in saturated pool boiling of water from stainless-steel surfaces has been investigated experimentally. Several sets of test sections of different surface conditions, geometries, orientations, diameters, lengths, and water types were tested at atmospheric pressure. The experimental results show that hysteresis effects in pool boiling heat transfer are not significant, but some appreciable trends are observed in accordance with parameters change. At higher heat flux regions, the curve for heat flux decrease is shifted to the left side of the curve for heat flux increase. To clarify hysteresis in pool boiling and to give some improvement on published correlations, four empirical correlations are obtained in terms of tube diameter, surface roughness, and tube wall superheat.

• 대한기계학회논문집 C: 기술과 교육
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• 제5권2호
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• pp.135-143
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• 2017

국내 유일의 연구용원자로인 하나로(Hi-flux Advanced Neutron Application ReactOr)는 다목적으로 중성자를 이용하기 위해 개방형 수조 내 노심이 존재하는 구조이며, 노심에서 발생되는 핵분열 열을 제거하기 위한 일차 냉각계통, 그리고 연결된 유체계통이 구비되어 있다. 원자로 수조 상부 근방에서 진행되는 방사성 작업 시 작업자의 방사능 피폭을 최소화하기 위해 수조고온층계통에 의해 상부에 고온층이 형성되어 있으며, 다소 저온 영역에 있는 방사능 가스 및 이물질이 상부로 올라오는 것을 방지하기 위해 수조수 온도를 $50^{\circ}C$이하로 제한하고 있으며 이를 위해 수조수관리계통이 연결되어 있다. 수조수관리계통의 구비된 판형열교환기의 열용량을 정상운전 조건에서 260 kW가 되도록 설계하여 각 수조에서 발생되는 열원을 제거하는지에 대해 평가하였고, 원자로 운전 모드와 관계없이 정상적으로 유체계통이 운전된다면 각 수조의 수조수 온도는 제한치 이하를 유지하고 있음을 확인하였다.

• Journal of Radiation Protection and Research
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• 제36권4호
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• pp.174-182
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• 2011

With the reactor operation conditions - 4.3 wt% $^{235}U$ initial enrichment, burn-up 55,000 MWd/MTU, average power 34 MW/MTU for three periods burned time for 539.2 days per period and cooling time for 100 hours after shut down, to set up the condition to determine the minimum height (depth) of spent fuel storage pool to shut off the radiation out of the spent fuel storage pool and to store spent fuels safely, the dose rate on the specific position directed to the surface of spent fuel storage pool induced by the neutron and gamma-ray from spent fuels are evaluated. The length of spent fuel is 381 cm, and as the result of evaluation on each position from the top of spent fuel to the surface of spent fuel storage pool, it is difficult for neutrons from spent fuels to pass through the water layer of maximum 219 cm (600 cm from the floor of spent fuel storage pool) and 419 cm (800 cm from the floor of spent fuel storage pool) for gamma-ray. Therefore, neutron and gamma-ray from spent fuels can pass through below 419 cm (800 cm from the floor) water layer directed to the surface of spent fuel storage pool.

• Safety and Health at Work
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• 제3권2호
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• pp.101-103
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• 2012

To identify the allergy problem of a 36-year old swimming instructor, who experiences heavy itching and rashes whenever she comes in contact with pool water. Patch tests were performed with European standard series and materials from the work floor. A positive patch test to aluminum chloride and flocculant was observed. Occupational dermatitis is, based on a contact allergy to aluminum chloride in the flocculant.

• Nuclear Engineering and Technology
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• 제41권7호
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• pp.929-944
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• 2009

The present study is concerned with the extension of the Effective Convectivity Model (ECM) to the phase-change problem to simulate the dynamics of the melt pool formation in a Light Water Reactor (LWR) lower plenum during hypothetical severe accident progression. The ECM uses heat transfer characteristic velocities to describe turbulent natural convection of a melt pool. The simple approach of the ECM method allows implementing different models of the characteristic velocity in a mushy zone for non-eutectic mixtures. The Phase-change ECM (PECM) was examined using three models of the characteristic velocities in a mushy zone and its performance was compared. The PECM was validated using a dual-tier approach, namely validations against existing experimental data (the SIMECO experiment) and validations against results obtained from Computational Fluid Dynamics (CFD) simulations. The results predicted by the PECM implementing the linear dependency of mushy-zone characteristic velocity on fluid fraction are well agreed with the experimental correlation and CFD simulation results. The PECM was applied to simulation of melt pool formation heat transfer in a Pressurized Water Reactor (PWR) and Boiling Water Reactor (BWR) lower plenum. The study suggests that the PECM is an adequate and effective tool to compute the dynamics of core melt pool formation.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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• pp.812-817
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• 1998

Experimental studies on heat transfer and solidification of the molten metal pool with overlying coolant with boiling were performed The simulant molten pool material is tin (Sn) with the melting temperature of 232$^{\circ}C$. Demineralized water and R113 are used as the working coolant. This work examines the crust formation and the heat transfer characteristics of the molten metal pool immersed in the boiling coolant. The Nusselt number and the Rayleigh number in the molten metal Pool region of this study are compared between the water coolant case and the R113 coolant case. The experimental results or the water coolant are higher than those for R113. Also, the empirical relationship of the Nusselt number and the Rayleigh number is compared with the literature correlations measure from mercury. The present experimental results are higher than the literature correlations. It is believed that this discrepancy is caused by the effect of heat loss to the environment on the natural convection heat transfer in the molten pool.

• 한국수자원학회논문집
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• 제56권spc1호
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• pp.1037-1048
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• 2023

하천에 설치된 댐, 보 등과 같은 횡단구조물은 수생태계에 영향을 미치며 종적 연결성을 단절하기 때문에 어류의 이동을 확보하기 위하여 어도가 설치된다. 그러나 어도 내부의 흐름 특성 및 어종에 따라 어류의 통과효율의 차이가 발생한다. 본 연구에서는 3차원 RANS 모형과 자유수면 해석을 위한 VOF (volume of fluid)기법을 적용한 수치모형을 활용하여 계단식 어도에서 발생하는 난류흐름을 수치모의 하였다. 계단식 어도의 pool의 길이 변화 및 상류 수위 변동을 고려하였으며 이들의 변화에 따라 평균유속 및 난류운동에너지 분포를 분석하였다. 표면류 및 잠입류 특성을 잘 재현하였으며 pool의 길이가 증가하면서 표면류에서 잠입류로 변화하였고 상류 수위가 증가함에 따라 표면류 특성이 명확하게 나타났다. 어도 내 어류의 이동과 관련된 수리학적 인자는 유속 및 난류운동에너지 등이 있으며 이를 바탕으로 어류의 소상 가능성을 검토하였다.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.162-167
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• 2003

조사재시험시설에 설치되어 있는 풀$(3m{\times}6m{\times}10m)$은 조사재운반용 수송용기(Cask)를 풀에 하역하여 풀물 속에서 조사재(시료)를 꺼내어 핫셀 내로 반입/반출하는 목적으로 사용한다. 수송용기를 풀에 하역하여 시료를 취출시 또는 버켓 엘리베이터에 장착시 모든 작업은 육안으로 행하여지기 때문에 항상 풀물을 양호한 수준으로 관리하여 수중취급 작업을 용이하게 하여야 하며, 방사성 오염관리 측면에서는 물에 잔존해 있는 방사성물질을 원자력법령에서 정하는 규정치 이하로 관리하여야 한다. 본 논문에서는 조사재시험시설에 설치하여 운용하고 있는 풀물정화장치 운전에 의한 방사능오염 및 수질에 대한 거동을 반출입된 시료별로 오염분포를 기술하였다.