• Nuclear Engineering and Technology
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• 제24권1호
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• pp.52-62
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• 1992

국내 원자력 발전소의 주요 기종인 가압 경수로에서는 일차 냉각계통을 통한 부식생성물 (CRUD)의 이동에 의해 노심에서 방사화된 후 노외표면에 침적된 방사성 핵종은 원전 종사자 방사선 피폭의 주원인이 된다. 따라서, 부식생성물에 의한 방사선 피폭을 감소시키기 위한 최적 화학운전 방안이 요망된다. 본 연구에서는 운전중인 국내 4개 발전소의 실제 수화학 운전 자료를 분석하였으며, 냉각재 화학운전 자료를 평가하기 위해 냉각재 수화학 조건에 따라 방사능 생성양을 계산할 수 있는 Computer 코드를 이용하였다. 실제 수화학 운전조건과 가정된 Elevated Li 운전조건에 따른 운전결과를 Computer 코드에 의해 예측하여 비교한 결과, Elevated Li 수화학 운전방법을 적용할 경우, 현재 적용되는 수화학 운전방법에 비하여 노심에서 부식생성물의 침적을 감소시킴으로써 노외 방사능 양을 상당히 감소시킬 수 있음을 알았다. 또한 계통 구성재 질과 핵연료봉의 건전성이 보장되는 한 냉각재 pH를 상승시키면 노외 방사능 생성감소에 유리함을 밝혔다.

• 한국유체기계학회 논문집
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• 제5권1호
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• pp.49-54
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• 2002

HANARO, 30 MW of research reactor, was installed at the depth of 13m in an open pool. The $90\%$ of primary coolant was designed to pass through the core and to remove the reaction heat of the cote. The rest, $10\%$, of the primary coolant was designed to bypass the core. And the reactor coolant through and bypass the core was inhaled at the top of chimney by the coolant pump to prevent the radiated gas from being lifted to the top of reactor pool. But, the part of core bypass coolant was not inhaled by the reactor coolant pump and reached at the top of reactor pool by natural convection, and increased the radiation lovel on the top of reactor pool. To reduce the radiation level by protecting the natural convection of the core bypass flow, the hot water layer (HWL, hereinafter) was installed with the depth of 1.2 m from the top of reactor pool. As the HWL was normally operated, the radiation level was reduced to five percent ($5\%$) in comparing with that before the installation of the HWL. When HANARO was operated at a higher temperature than the normal temperature of the HWL by operating the standby heater, it was found that the radiation level was more reduced than that before operation. To verify the reason, the heat loss of the HWL was calculated by Visual Basic Program. It was confirmed through the results that the larger the temperature difference between the HWL and reactor hall was, the more the evaporation loss increased. And it was verified that the radiation level above was reduced mote safely by increasing the capacity of heater.

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2001년도 유체기계 연구개발 발표회 논문집
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• pp.221-226
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• 2001

HANARO, 30MW of research reactor, was installed at the depth of 13m of open pool, The $90\%$ of primary coolant was designed to pass through the core and to remove the reaction heat of the core. The rest $10\%$, of the primary coolant was designed to bypass the core. And the reactor coolant through and bypass the core was inhaled at the top of chimney by the coolant pump to protect that the radiated gas was lifted to the top of reactor pool. But, the part of core bypass coolant was not inhaled by the reactor coolant pump and reached at the top of reactor pool by natural convection and increased the radiation level on the top of reactor pool. To reduce the radiation level by protecting the natural convection of the core bypass flow, the hot water layer (HWL, hereinafter) was installed with the depth of 1.2m from the top of reactor pool. As the HWL was normally operated, the radiation level was reduced to five percent ($5\%$) in comparing with that before the installation of the HWL. When HANARO was operated with higher temperature than the normal temperature of the HWL by operating the standby heater, it was found that the radiation level was more reduced than that before operation. To verify the reason, the heat loss of the HWL was calculated. It was confirmed through the results that the larger the temperature difference between the HWL and reactor hall was, the more the evaporation loss was increased. And it was verified that the radiation level above was reduced more safely by increasing the capacity of heater.

• 한국자동차공학회논문집
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• 제22권3호
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• pp.179-185
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• 2014

Average temperature and temperature uniformity in a battery cell are the important criteria of the thermal management of the battery pack for hybrid electric vehicles and electric vehicles (HEVs and EVs) because high power with large size cell is used for the battery pack. Thus, liquid cooling system is generally applied for the HEV/EV battery pack. The liquid cooling system is made of multiple cooling plates with coolant flow paths. The cooling plates are inserted between the battery cells to reject the heat from batteries to coolant. In this study, the cooling plate with U-shaped coolant flow paths is considered to evaluate the effects of coolant flow condition on the cooling performance of the system. The counter flow and parallel flow set up is compared and the effect of flow rate is evaluated using CFD tool (FLUENT). The number of counter-flows and flow rate are changed and the effect on the cooling performance including average temperature, differential temperature, and standard deviation of temperature are investigated. The results show that the parallel flow has better cooling performance compared with counter flow and it is also found that the coolant flow rate should be chosen with the consideration of trade-off between the cooling performance and pressure drop.

• 한국추진공학회지
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• 제2권3호
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• pp.54-61
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• 1998

재생냉각방식을 사용하는 액체추진제 로켓엔진의 열 전달과정이 전산모사 되었다. 연소가스로부터 연소실 벽으로 전달되는 열 전달과정은 가스측 열 전달이라 한다. 이 열은 그을음과 연소실 금속벽을 통해 반경방향으로 전도되어 냉각제로 전달된다. 최종적으로, 이 열은 연소실 벽에 있는 통로를 따라 흐르는 냉각제에 대류전달된다. 본 연구에서는 위의 3가지 열전달량이 같은 크기임에 착안하여 냉각제측 벽 온도, 가스측 벽 온도, 열전달량을 결정한다. 냉각제 유동통로갯수 및 형상(높이, 폭), 연소실 및 노즐 외부형상(크기), 산화제 및 연료 물성치, 냉각제 물성치, 산화제/연료 혼합비, 냉각제 주입온도, 연소실 및 노즐 벽면 상에 연소시 생기는 그을음 두께가 주어지면 연소실 축방향에 따른 반경방향 온도분포 및 열 전달 량의 합리적인 수치 결과가 얻어진다.

• 한국추진공학회지
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• 제21권1호
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• pp.72-83
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• 2017

본 연구에서는 유도탄 사출관 내부의 수치모사를 통해 이상 유동에 대한 열 유체역학적 분석을 수행하였다. 고정된 해석영역에서 계산이 진행되었고 증발이 완료된 물을 냉각제로 사용하였다. 고온의 공기와 냉각제간의 상호작용 및 유동장을 해석하기 위해, Realizable $k-{\varepsilon}$ 난류 모델과 VOF (Volume Of Fluid) 모델을 선정하고 냉각제 유량에 따른 수치 해석을 진행하였다. 해석결과, 사출관 상부 압력은 냉각제 유량에 따라 비선형적으로 증가하였다. 그리고 내부에서의 유동 진행 과정과 온도분포, 냉각제분포가 밀접한 연관이 있음을 확인하였다. 사출관 하부의 초기 온도는 냉각제량의 증가에 비례하여 감소하지만, 특정시간 이후 경향이 역전되면서 오히려 온도의 상승을 유발하였다. 또한, 혼합가스의 순환유동에 의해 초기의 온도변화가 요동하는 경향도 확인되었다.

• 한국추진공학회지
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• 제22권6호
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• pp.84-93
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• 2018

냉각제 분사조건이 변화할 때 혼합가스 사출시스템 (또는 가스-스팀 발사체계) 냉각효율 및 발사체 사출성능의 변화를 확인하기 위해 3차원 수치모사를 수행하였다. 선행연구를 참조하여 구축한 1차원 모델을 통해 3차원 단상(single-phase) 계산모델을 검증한 후, Discrete Phase Model을 활용하여 고온의 기체에 냉각제 분사를 모사한 이상(two-phase) 유동 계산을 수행하였다. 냉각제 유량과 분사구 개수를 각각 변화시키면서 계산을 수행한 결과, 분사구 개수를 증가시켰을 경우 냉각효율이 보다 개선되었다. 또한 분사조건에 따라 냉각제 액적 서로간의 coalescence 발생 빈도 및 공간분포 변화가 발생하여 액적의 직경이 달라졌고, 이는 냉각제 증발률에 영향을 미쳤다. 냉각제의 증발은 breech 내부의 온도를 감소시키는 반면에 압력감소를 억제하여 사출시스템 최적화 설계에 있어 중요한 요소임을 확인하였다.

• 한국안전학회지
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• 제37권4호
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• pp.129-138
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• 2022

A new method for injecting cooling water into the Korean research reactor (KRR) in the event of beam tube rupture is proposed in this paper. Moreover, the research evaluates the risk to the reactor core in terms of core damage frequency (CDF). The proposed method maintains the cooling water in the chimney at a certain level in the tank to prevent nuclear fuel damage solely by gravitational coolant feeding from the emergency water supply system (EWSS). This technique does not require sump recirculation operations described in the current procedure for resolving beam tube accidents. The reduction in the risk to the core in the event of beam tube rupture that can be achieved by the proposed change in the cooling water injection design is quantified as follows. 1) The total CDF of the KRR for the proposed design change is approximately 4.17E-06/yr, which is 8.4% lower than the CDF of the current design (4.55E-06/yr). 2) The CDF for beam tube rupture is 7.10E-08/yr, which represents an 84.1% decrease compared with that of the current design (4.49E-07/yr). In addition to this quantitative reduction in risk, the modified cooling water injection design maintains a supply of pure coolant to the EWSS tank. This means that the reactor does not require decontamination after an accident. Thermal hydraulic analysis proves that the water level in the reactor pool does not cause damage to the nuclear fuel cladding after beam tube rupture. This is because the amount of water in the chimney can be regulated by the EWSS function. The EWSS supplies emergency water to the reactor core to compensate for the evaporation of coolant in the core, thus allowing water to cover the fuel assemblies in the reactor core over a sufficient amount of time.

• 한국압력기기공학회 논문집
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• 제20권1호
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• pp.49-55
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• 2024

Stainless 630 (or 17-4PH) is a precipitation-hardening martensitic stainless steel that has excellent mechanical properties and corrosion resistance. These characteristics make the STS630 to be used as a consisting material for various components such as spider, pin, spring, and spring retainer, of the control rod drive mechanism (CRDM) in pressurized water reactors (PWRs). In general, it is well known that the oxide layer of stainless steel consists of a duplex layer, a compact inner layer of FeCr₂O₄ spinel, and a coarse-grained outer layer of Fe₃O₄ spinel in PWR primary coolant condition. However, the characteristics of the oxide layer can be sensitively influenced by various water chemistry conditions such as temperature, dissolved oxygen, dissolved hydrogen, pH, pH adjuster type, and exposure time. In this work, we investigate the corrosion properties of the STS630 as a function of coolant temperature in an NH3 alkaline solution for its boron-free application in a small modular reactor, to confirm the feasibility for usage as a boron-free SMR structural material. As a result, oxide layer of corroded STS630 is consist of double-layer oxides consisting of a Cr-rich dense inner oxide and a Fe-rich polyhedral outer particles like as that in commercial PWR primary coolant. The corrosion rate of STS630 increases with increase in test time and temperature and the corrosion rate-time model equation was developed based on experimental data. Overall, it is expected that the results in this study provides useful data for the corrosion behavior of STS630 in alkaline environments, contributing to the development of selecting suitable materials for SMRs.

• Korean Chemical Engineering Research
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• 제52권6호
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• pp.826-833
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• 2014

해양 중소규모 가스전의 경제성에 대한 화두가 던져진 이후 전통 석유의 가격변동과 세계적인 환경규약 등에 맞물려 석유화학관련 산업계에서는 이를 효과적으로 대처하고 천연가스를 활용할 수 있는 공정을 개발하고자 하였다. 이에 Fischer-Tropsch 반응을 기반으로 하는 해상 GTL 공정(offshore gas-to-liquid process)이 제안되었고 부유시스템 platform으로 공정을 적용시키고자 마이크로채널 반응기가 떠오르고 있다. 본 논문에서는 단일 마이크로채널 반응기를 Fischer-Tropsch 반응을 기반으로 하여 Matlab과 ASPEN Hysys를 연동하여 모사하고 이로 얻어진 반응열을 도입해 상용 전산유체역학(computational fluid dynamics, CFD) 소프트웨어인 ANSYS fluent로 멀티 마이크로채널 반응기 모델을 제작하였다. 그리고 4가지의 설계변수인 냉각채널 넓이, 높이, 냉각채널과 반응채널의 간격, 냉각채널 간의 간격을 설정하고 이들의 변화에 따른 열유동을 3가지의 변수인 열유속, 냉각 및 반응채널의 최대온도의 변화를 시각화하여 그 경향성을 확인하였다. 경향성 분석 결과, 냉각채널의 넓이와 높이는 짧을수록 총 열유속이 높아졌으며 최대온도 역시 높아졌으나 냉각채널과 반응채널의 간격은 열유동에 거의 영향을 미치지 못하였다. 냉각채널 간의 간격은 짧을수록 총 열유속이 높아졌으며 최대온도는 낮아졌다. 따라서 적절한 냉각채널의 넓이와 높이를 제안하고 짧은 간격의 냉각채널 구조를 도입하여 반응채널의 열량을 충분히 제거할 수 있는 반응기설계에 대한 휴리스틱을 제안할 수 있었다. 이처럼 멀티채널 반응기의 모델을 설계하고 이로부터 적절한 변수를 선택해 그 경향성을 확인할 수 있는 방법을 통해 설계 단계에서부터 적절한 반응기 구조에 대한 제안을 하는데 도움을 줄 것이다.