• 터널과지하공간
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• 제9권4호
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• pp.306-314
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• 1999

핵폐기물 저장공간과 같이 대규모 터널형 지하공간내에서의 환기량, 온/습도, 오염물질 농도 예측은 공간건설 및 운영을 위하여서 뿐만 아니라 화재등과 같은 비상시의 대처방안 강구를 위하여 반드시 필요하다. 본 연구에서는 압축성 가정하에서 autocompression의 영향을 고려한 자연환기압 계산 fan 및 regulator의 최적 위치 및 용량 결정, 암반 열물성 및 암반 표면으로부터의 증발, 응축에 의한 수분함유량 변화를 고려한 온/습도 계산, 이류확산에 기초한 오염물질 농도 분포 계산 기능을 갖춘 네트워크형 지하공간 환경예측 모델을 개발하였다. 온/습도 예측 모델을 군수물자 지하 저장공간에 적용한 결과 실측값과 상대오차는 건구온도 1.5~2.9%, 습도온도 0.6~6.1%로 나타났다. 도로터널 2개소를 대상으로한 실험결과 외부 입기만에 의한 확산계수는 9.78과 17.35$m^2$/s 큰 편이었으나 차량 운행과 환기설비의 작동시에는 이류확산만을 고려한 경우 CO 및 매연 농도의 상대오차가 5.88과 6.62%로 비교적 작게 나타났다. 이는 대부분의 터널형 지하공간에서의 농도 분포는 이류확산만에 의하여 추정이 가능함을 의미한다.

• 방사성폐기물학회지
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• 제2권1호
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• pp.13-22
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• 2004

This study presents the thermal analyses of a spent fuel dry storage cask under normal and off-normal conditions. The environmental temperature is assumed to be 15 $^{\circ}C$ under the normal condition. The off-normal condition has an environmental temperature of 38 $^{\circ}C$. An additional off-normal condition is considered as a partial blockage of the air inlet ducts. Two of the four air inlet ducts are assumed to be completely blocked. The significant thermal design feature of the storage cask is the air flow path used to remove the decay heat from the spent fuel. Natural circulation of the air inside the cask allows the concrete and fuel cladding temperatures to be maintained below the allowable values. The finite volume computational fluid dynamics code FLUENT was used for the thermal analysis. The maximum temperatures of the fuel rod and concrete overpack were lower than the allowable values under the normal and off-normal conditions.

• 한국자기학회지
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• 제23권2호
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• pp.77-81
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• 2013

본 연구의 목적은 회전자기장에서 회전수 및 자기장강도 변화에 따른 이중원관내 자성유체의 자연대류 열전달 특성에 관하여 고찰하는 것이다. 회전자기장은 6극 3상 유도전동기를 사용하여 인가하였고, 인버터 드라이버와 전압변환기를 이용하여 회전수 및 자기장강도를 제어하였다. 실험에 사용된 경계조건으로 이중원관 내부원관은 $30^{\circ}C$로 유지하고 외부원관은 $25^{\circ}C$로 유지하였으며, 회전자기장은 반시계방향으로만 인가하여 실험을 수행하였다. 그 결과 이중원관내 자성유체의 자연대류 열전달 특성은 회전자기장의 회전수 및 자기장강도 증가에 따라 열확산이 증가하여 고온부과 저온부의 열교환이 활발히 이루어졌으며, 이중원관 내 자성유체의 열확산 방향은 인가자기장과 같은 방향인 반시계방향으로 진행되었다.

• 대한기계학회논문집
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• 제9권2호
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• pp.213-221
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• 1985

본 논문에서는 아래면이 고온이고 옆면중의 일부가 저온으로 유지되는 4각형 밀폐공간에서의 자연대류에 대한 수치적 시뮬레이션을 하고, 동등한 경계조건을 가지 는 실험결과와 비교하여 수치모델의 정당성을 입증하고, 정당화된 수치모델의 여러 가 지 변수를 변화시키면서 4각형 밀폐공간내의 열전달 현상을 연구하였다. 실험과 수 치해석의 변수로서 같은 경계조건에 대하여, 종횡비, Gr수 등을 변화시켜 비교하고, 더 나아가 수치모델에 대하여 단열조건의 변화, 저온부의 위치등 경계조건의 변화에 대한 영향을 살폈다.

• 대한원격탐사학회:학술대회논문집
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• 대한원격탐사학회 2003년도 Proceedings of ACRS 2003 ISRS
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• pp.28-30
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• 2003

Hot Spring Law of Taiwan was passed in legislative assembly on 3 June 2003. Hot springs would become one of the most important natural resources for recreation purposes. Both public and private sectors will invest large amount of capital in this area in the near future. The value of remote sensing technology is to give a critical tool for observing the landscape to find out mega-scaled geological structures, which may not be able to be found by conventional approaches. The occurrences of the hot springs in Taiwan are mostly in metamorphic and sedimentary rocks , other than in volcanic environments. Local geothermal anomaly or heat of springs transfer by liquid convection other than conduction or radiation. The deeply -seated fractures of hard rocks are the conduit of the convection of hot water, which could be as deep as 3000 meters in a hypothetical model of Taiwan. Clues to find outcrops of hot spring can be obtained by a structure-controlled model deduced by geological lineaments observed by satellite images and stereoscopic interpretation of aerial photographs. A case study conducted in Eastern Taiwan will be demonstrated.

• 설비공학논문집
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• 제9권3호
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• pp.312-322
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• 1997

The natural convective flow in a two-dimensional square enclosure with horizontal partitions is investigated numerically. The enclosure was composed of the lower hot and the upper cold horizontal walls and the adiabatic vertical walls, and two identical partitions were positioned perpendicularly at the mid-height of the right and left walls, respectively. The governing equations are solved by using the finite element method with Galerkin method. Calculations are made for different partition lengths, partition conductivites, and Rayleigh numbers based on the temperature difference between two horizontal walls and the enclosure height with water(Pr=4.95). An oscillatory motion of the natural convective flow is affected significantly by the variation of the gap width and Rayleigh number. When the gap width is comparatively short, the heat transfer rate is raised with the increase of the thermal conductivity of partitions. However, for sufficiently large gap widths at higher Rayleigh numbers, the average Nusselt numbers of the conductive partitions are smaller than those of the adiabatic partitions.

• 한국안전학회지
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• 제35권3호
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• pp.96-104
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• 2020

The numerical simulations were conducted to investigate the thermal-fluid phenomena occurred inside the experimental apparatus during a PCCS, used to remove heat released in accidents from a containment of light water nuclear power plant, operation. Numerical simulations of the flow and heat transfer caused by wall condensation inside the containment simulation vessel (CSV), which equipped with 18 vertical heat exchanger tubes, were conducted using the commercial computational fluid dynamics (CFD) software ANSYS-CFX. Shear stress transport (SST) and the wall condensation model were used for turbulence closure and wall condensation, respectively. The simulation using the actual size of the apparatus. However, rather than simulating the whole experimental apparatus in consideration of the experimental cases, calculation resources, and calculation time, the simulation model was prepared only in CSV. Selective simulation was conducted to verify the effects of non-condensable gas(NC gas) concentration, CSV internal pressure, and wall sub-cooling conditions. First, as a result of the internal flow of CSV, it was observed that downward flow due to condensation occurred surface of the vertical tube and upward flow occurred in the distant place. Natural convection occurred actively around the heat exchanger tube. Due to this rising and falling internal flow, natural circulation occurred actively around the heat exchanger tubes. Next, in order to check the performance of built-in condensation model using according to the non-condensable gas concentration, CSV internal flow and wall sub-cooling, the heat flux values were compared with the experimental results. On average, the results were underestimated with and error of about 25%. In addition, the influence of CSV internal pressure and wall sub-cooling was small, but when the condensate was highly generated due to the low non-condensable gas concentration, the error was large compared to the experimental values. This is considered to be due to the nature of the condensation model of the CFX code. However, in spite of the limitations of CFD, it is valid to use the built-in condensation model of CFD for PCCS performance prediction from a conservative perspective.

• Journal of the Korean Wood Science and Technology
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• 제44권3호
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• pp.370-380
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• 2016

제주도 지역에서 소나무재선충병 피해를 받은 곰솔 원목의 이용확대를 위하여 열처리를 수행하였다. 열처리는 처리 원목의 중심부가 소나무재선충의 사멸온도인 $56^{\circ}C$를 30분간 유지하여야 한다. 곰솔 원목의 초기함수율과 말구지름은 각각 46% ~ 141%, 180 mm ~ 500 mm의 범위이고, 기본비중과 전건비중은 각각 0.47, 0.52이었다. $105^{\circ}C$ 조건에서 함수율과 말구지름에 따라 열처리에 소요되는 시간은 7.7 h ~ 44.2 h의 범위로 측정되었다. 다양한 함수율 및 지름을 갖는 곰솔 원목의 열처리 소요시간을 예측하기 위하여 열처리 진행 중 처리목 내부의 온도분포를 유한차분법을 적용한 2차원 열전달 해석을 통하여 제시하였다. 열전달 해석을 위한 목재의 열적 특성은 함수율에 따른 열전도계수와 비열을 적용하였으며, 자연대류와 강제대류를 합한 형태의 혼합대류에 의한 혼합대류계수를 적용하였다. 실험값과 예측 값의 오차는 3 ~ 45%의 범위로 분석되었다. 곰솔 원목에서 초기함수율이 50%이고, 말구지름이 200 mm, 300 mm, 400 mm인 경우, 예측된 열처리 소요시간은 각각 10.9 h, 18.3 h, 27.0 h이었다. 초기함수율이 75%일 때, 지름에 따라 각각 13.6 h, 22.5 h, 32.8 h이고, 초기함수율이 100%일 때, 지름에 따라 각각 16.2 h, 26.5 h, 38.2 h이었다. 이러한 열처리 소요시간의 예측방법에 소나무와 잣나무 등 다른 소나무재선충병 피해목의 물리적 특성을 적용하면, 함수율과 말구지름에 따른 열처리 소요시간을 제시할 수 있을 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2315-2324
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• 2023

Space nuclear reactors are becoming popular in deep space exploration owing to their advantages of high-power density and stability. Following the fourth-generation nuclear reactor technology, a conceptual design of the dual drum-controlled space molten salt reactor (D²-SMSR) is proposed. The reactor concept uses molten salt as fuel and heat pipes for cooling. A new reactivity control strategy that combines control drums and safety drums was adopted. Critical physical characteristics such as neutron energy spectrum, neutron flux distribution, power distribution and burnup depth were calculated. Flow and heat transfer characteristics such as natural convection, velocity and temperature distribution of the D²-SMSR under low gravity conditions were analyzed. The reactivity control effect of the dual-drums strategy was evaluated. Results showed that the D²-SMSR with a fast spectrum could operate for 10 years at the full power of 40 kWth. The D²-SMSR has a high heat transfer coefficient between molten salt and heat pipe, which means that the core has a good heat-exchange performance. The new reactivity control strategy can achieve shutdown with one safety drum or three control drums, ensuring high-security standards. The present study can provide a theoretical reference for the design of space nuclear reactors.

• 한국전산유체공학회지
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• 제21권2호
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• pp.54-61
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• 2016

When spent fuel assemblies from the reactor of nuclear power plants(NPPs) are transported, the assemblies are exposed to short-term operations that can affect the peak cladding temperature of spent fuel assemblies. Therefore, it needs to perform the analysis of heat transfer on spent fuel dry cask during the operation. For 3 dimensional computational fluid dynamnics(CFD) simulation, it is proposed that the short-term operation is divided into three processes: Wet, dry, and vacuum drying condition. The three processes have different heat transfer mode and medium. Metal transportation cask, which is Korea Radioactive Waste Agency(KORAD)'s developing cask, is evaluated by the methods proposed in this work. During working hours, the boiling at wet process does not occur in the cask and the peak cladding temperatures of all processes remain below $400^{\circ}C$. The maximum peak cladding temperature is $173.8^{\circ}C$ at vacuum drying process and the temperature rise of dry, and vacuum drying process occurs steeply.