• Nuclear Engineering and Technology
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• 제56권6호
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• pp.2029-2038
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• 2024

A deep understanding of the characteristics and mechanism of geyser boiling and capillary pumping is necessary to optimize a high-temperature sodium heat pipe. In this work, the Volume of Fluid (VOF) two-phase model and the capillary force model in the mesh wick were used to model the complex phase change and fluid flow in the heat pipe. Computational Fluid Dynamics (CFD) simulations successfully predicted the process of bubble nucleation, growth, aggregation, and detachment from the wall in the liquid pool of the evaporation section of the heat pipe in horizontal and tilted states, as well as the reflux phenomenon of capillary suction within the wick. The accuracy and stability of the capillary force model within the wick were verified. In addition, the causes of geyser boiling in heat pipes were analyzed by extracting the oscillation distribution of heat pipe wall temperature. The results show that adding the capillary force model within the wick structure can reasonably simulate the liquid backflow phenomenon at the condensation; Under the horizontal and inclined operating conditions of the heat pipe, the phenomenon of local dry-out will occur, resulting in a sharp increase in local temperature. The speed of bubble detachment and the timely reflux of liquid sodium (condensate) replenishment in the wick play a vital role in the geyser temperature oscillation of the tube wall. The numerical simulation method and the results of this study are anticipated to provide a good reference for the investigation of geyser boiling in high-temperature heat pipes.

• Nuclear Engineering and Technology
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• 제56권9호
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• pp.3950-3960
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• 2024

As a solution to the problem of spent nuclear fuels (SNFs), the disposal of SNF has gained attention from nations using nuclear energy because of hazards posed to the ecosystem. Among many proposed solutions, the most promising method is to dispose of SNF in a deep geological repository (DGR) which utilizes the multi-barrier concept developed by Finland and Sweden. Here, a new fully-coupled Thermal-Hydraulic (TH) code HADES (High-level rAdionuclide Disposal Evaluation Simulator) is developed using the MOOSE framework. This new code suggests basic numerical tools, such as a non-linear solver and finite element discretization, to assess the safety performance of disposal systems. The new TH code considered various TH behavior using Richards' flow approach, assuming gas pressure is constant. The HADES showed promising results when it was compared to various TH codes validated from DECOVAELX-THMC projects. When the single-canister model was utilized to estimate the TH behavior of the Korean Reference disposal System, although it showed significant saturation reduction due to the evaporation of water, the temperature was maintained under the thermal criteria limit, which is 100 ℃. In addition, the new code estimated temperature and degree of saturation of the multi-canisters model, considering two or three canisters, it showed a slightly lower temperature, 5 ℃, than the single-canister model. From these results, the following are concluded: (1) the new TH code contribute to an additional integrity by estimating TH behavior of KRS; (2) however, due to limitations in single-canister simulation, it is recommended to use multi-canisters simulation to estimate TH behavior accurately. Therefore, this model is anticipated not only to help licensing applications and estimation of various multi-physics phenomena and multi-canister at the disposal site.

• Nuclear Engineering and Technology
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• 제56권8호
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• pp.3286-3297
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• 2024

Traditional text-based system engineering, which has been used in the design and application of passive residual heat removal system (PRHRS) for lead-cooled fast reactors, is prone to several problems such as low development efficiency, long iteration cycles, and model ambiguity. This study aims to effectively address the abovementioned problems by adopting a model-based system engineering (MBSE) method, which has been preliminarily applied to meet the design requirements of a PRHRS. The design process has been implemented based on the preliminary design of the system architecture and consists of three stages: top-level requirement analysis, functional requirements analysis, and design requirements synthesis. The results of the top-level requirements analysis and the corresponding use case diagram can determine the requirements, top-level use cases, and scenario flow of the system. During the functional requirements analysis, the sequence, activity, and state machine diagrams are used to develop the system function model and provide early confirmation. By comparing these sequence diagrams, the requirements for omissions and inconsistencies can be effectively checked. In the design requirements synthesis stage, the Analytic Hierarchy Process is used to conduct preliminary trade-off calculations on the system architecture, after which a white box model is established during the system architecture design. Through these two steps, the analysis and design of the system architecture are ultimately achieved. The resulting system architecture ensures the consistency of the design requirements. Ultimately, a functional hazard analysis was conducted for a specific incident to validate case requirements and further refine the system architecture. Future research can further reduce the design risk, improve the design efficiency, and provide a practical reference for the design and optimization of PRHRS in digital lead-cooled fast reactors.

• Asian-Australasian Journal of Animal Sciences
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• 제20권9호
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• pp.1407-1416
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• 2007

Ten, first lactation, 87.5%HF dairy cattle were used to investigate effects of long-term administration of recombinant bovine somatotropin (rbST) on nutrient uptake by the mammary gland at different stages of lactation. Measurements of arterial plasma concentrations and arterial-venous differences of metabolites across the mammary gland were performed in combination with measurment of mammary blood flow to estimate the mammary uptake. Animals in experimental groups were injected subcutaneously every 14 days from day 60 of lactation with a prolonged-release formulation of 500 mg of rbST (POSILAC, Monsanto, USA) or with sterile sesame oil without rbST in the control group. During early lactation, the milk yield of rbST-treated animals was higher than that of the control animals (p<0.05). The peak milk yield in both groups of animals declined from the early period of lactation with progression to mid- and late-lactation. No significant changes were observed in the concentration of milk lactose, while the concentrations of milk protein significantly increased as lactation advanced to mid- and late-lactation in both groups. Milk fat concentrations were significantly higher in rbST-treated animals than in control animals, particularly in early lactation (p<0.05). Mammary blood flow (MBF) markedly increased during rbST administration and was maintained at a high level throughout lactation. The mean arterial plasma concentrations for glucose and acetate of rbST-treated animals were unchanged. The net mammary glucose uptake of rbST-treated animals increased approximately 20% during early lactation, while it significantly decreased (p<0.05), including the arteriovenous differences (A-V differences) and extraction ratio across the mammary gland, as lactation advanced to mid- and late-lactation. A-V differences, mammary extraction and mammary uptake for acetate increased during rbST administration and were significantly higher (p<0.05) than in the control animals in early and mid-lactation. Mean arterial plasma concentrations for ${\beta}$-hydroxybutyrate and free glycerol were unchanged throughout the experimental periods in both groups. A-V differences and extraction ratio of ${\beta}$-hydroxybutyrate across the mammary gland did not alter during rbST administration. Mean arterial plasma concentrations for free fatty acids ($C_{16}$ to $C_{18}$), but not for triacylglycerol, increased in rbST-treated animals and were significantly higher than in control animals during early lactation (p<0.01). These findings suggest that an increase in MBF during rbST administration would not be a major determinant in the mediation of nutrient delivery and uptake by the mammary gland for increased milk production. Local changes in biosynthetic capacity within the mammary gland would be a factor in the utilization of substrates resulting in the rate of decline in milk yield with advancing lactation.

• KSBB Journal
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• 제11권3호
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• pp.360-366
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• 1996

전기장에서의 유기산의 이동성향을 파악하기 위하여 아세트산을 대상으로 하여 한외여과막과 이온교 환막을 사용한 전기투석에 대해 연구하였다. 전기장에 의한 한외여과막에서의 전기적 삼투흐름은 전반적으로 anodic side에서 cathodic side로 진행되었다. 막을 통한 이온의 순수이동은 전기척 삼투흐름 에 대한 전기적 이동속도로부터 결정되였으며, 실험 에서의 순수 전기적 삼투흐름방향은 아세트산의 이 동에 많은 영향을 미치는 것으로 사료된다. 격막을 통한 전기척 삼투흐름에 의해 특성화된 한외여과막의 표면전하는 모두 음전하를 띠었다. 각기 재질이 다른 regenerated celiuloseCYM series)와 polysul foneCPM series) 재질의 한외여과막을 사용한 실험에서 아세트산이온의 이통양상에 매우 다르게 나타 났으며 전반적으로 YM series의 한외 여과막에서 아세트산이옹의 이동이 원할한 것으로 나타났다. 이는 전기적 삼투흐름측정에 따르면 YM series의 격막에 비해 PM series의 격막이 전해질용액에셔 상대적으로 큰 음전하를 띠는 것으로 추측된다. 아세트산 이온의 이동은 전기장의 세기, 전극사이 의 거리, 전극표면적, 이온세기, 온도, 격막의 pore 크기등에 영향을 받았으며, 일정한 전류장의 조건에서 이온교환막에서의 아세트산 이온의 이통은 한외 여과막에 비하여 1.5 에서 3배 수준이였다. 전기장 펄스형성에 의한 이온교환막에서의 아세트산이온의 이동은 10sec/hr의 펄스전기장에서 약 10%의 증가 를보였다.

• 자원환경지질
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• 제22권4호
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• pp.381-393
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• 1989

익산지역의 지하수 유동계를 평가하기 위한 수리지질학적 모델링이 수행되었다. 연구지역의 범위는 $790km^2$이다. 본 지역의 지질은 쥬라기의 대보화강암과 편마상화강암 그리고 선캠브리아기의 변성암으로 구성되어 있다. 채수량은 편마상화강암지역에서 가장 높으며 이는 10km내지 25m두께의 비교적 두껍게 발달된 풍화대 때문이다. 본 모델 시뮬레이션에는 콜로라도 주립대학의 유한차분법모델이 사용되었다. 본 모델은 불균일한 격자간격을 가지며, 28행과 31열로 이루어져 있다. 본 모델은 정류상태와 부정류상태에서 보정되었다.. 정류상태 시뮬레이션의 결과를1985년 9월의 수위등고선과 비교하여 투수율과 우기의 순충전률을 결정하였다. 부정류상태 시뮬레이션은 지하수 채수에 따른 대수층의 반응을 알기 위한 것이다. 부정류상태를 보정에서는 1986년5월의 수위등고선과 맞춤으로서 비산출율의 크기와 분포 그리고 건기의 채수량과 충전량을 결정하였다. 보정된 모델을 이용하여 1985년 10월부터 1995년 9월까지의 지하수채수 및 자연적인 충전에 의한 지하수위변동을 예측하여 보았다. 보정된 모델은 광역적인 지하수개발계획에 이용될 수 있다. 그러나 국부적인 지하수위변동을 예측하는데는 이용될 수 없다.

• 지질공학
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• 제20권2호
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• pp.121-126
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• 2010

현재 방사성폐기물 처분기술 개발을 위해 운영되고 있는 시설인 KURT는 부지특성조사의 일환으로 안정성 평가차원에서 확대하여 이뤄지고 있다. 본 연구는 KURT 주변지역의 구성된 지질모델을 기초로 하여 부지규모의 수리지질학적 유동특성에 대한 연구를 하였다. 연구지역에 분포된 시추공을 이용하여 스테레오 넷으로 도시한 결과 NS, NW, EW, 저경사 단열대군으로 구분할 수 있었으며 지질 모델의 구성요소로는 상부 토양층 및 풍화대, 저경사 단열대, 단열대로 구분되었다. 구분된 단 열대에 수리시험을 통하여 지하수가 대수층을 통해 이동할 수 있는 유동력을 제공하는 수리전도도 및 수리경사에 영향을 미치는 단열의 크기 와 방향성에 대한 정규분포 통계 분석을 수행함으로 연구지역 내 NS 방향의 단열이 우세함을 확인하였다. 또한, 저경사 단열대의 수리전도도의 값은 3.61E-07 m/s로 주요 단열대보다 큰 값을 가지며, 기반암이나 기반암에 존재하는 단열대와 수리학적 특성이 상이하다.

• 한국수자원학회논문집
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• 제40권12호
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• pp.995-1005
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• 2007

본 연구에서는 하천유역에서 소수력 개발 대상지점에서의 최적규모를 결정하는 방안을 제시하였다. 제시된 방안은 지형 및 수문자료의 구축, 발전소 모의운영, 경제성분석, 최적규모 결정과 같은 일련의 절차로 이루어진다. 최적규모 결정을 위해 경제성 평가지표 가운데 하나인 순현가를 이용하였고, 이를 통해 최적 설계유량과 시설물의 최적규모를 도출하였다. 초기비용의 산출을 위하여 기존 소수력발전소의 비용 자료를 검토하여 함수식을 개발하였고, 편익 산정시 현재 공시된 전력 기준단가를 이용하였다. 이러한 일련의 절차를 기존에 조사된 금강수계의 초강유역에 위치한 댐식, 수로식 소수력 지점 2개소에 적용하였으며, 최종적으로 설계유량과 시설물의 규모 변화에 따른 NPV 민감도를 확인하여 최적규모를 결정하였다. 본 연구에서 제시한 방법은 소수력 개발지점에서의 최적규모 및 경제성 여부를 사업추진 이전에 개략 추정하여 잠재수력 부존량을 확인함으로써 사업시행주체의 의사결정 지원 측면에서 활용도가 높을 것으로 기대된다.

• Nuclear Engineering and Technology
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• 제42권4호
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• pp.382-393
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• 2010

Thermal mixing by steam jets in a pool is dominantly influenced by a turbulent water jet generated by the condensing steam jets, and the proper prediction of this turbulent jet behavior is critical for the pool mixing analysis. A turbulent jet flow induced by a steam jet discharged through a vertical upward single hole into a subcooled water pool was subjected to computational fluid dynamics (CFD) analysis. Based on the small-scale test data derived under a horizontal steam discharging condition, this analysis was performed to validate a CFD method of analysis previously developed for condensing jet-induced pool mixing phenomena. In previous validation work, the CFD results and the test data for a limited range of radial and axial directions were compared in terms of profiles of the turbulent jet velocity and temperature. Furthermore, the behavior of the turbulent jet induced by the steam jet through a horizontal single hole in a subcooled water pool failed to show the exact axisymmetric flow pattern with regards to an overall pool mixing, whereas the CFD analysis was done with an axisymmetric grid model. Therefore, another new small-scale test was conducted under a vertical upward steam discharging condition. The purpose of this test was to generate the velocity and temperature profiles of the turbulent jet by expanding the measurement ranges from the jet center to a location at about 5% of $U_m$ and 10 cm to 30 cm from the exit of the discharge nozzle. The results of the new CFD analysis show that the recommended CFD model of the high turbulent intensity of 40% for the turbulent jet and the fine mesh grid model can accurately predict the test results within an error rate of about 10%. In this work, the turbulent jet model, which is used to simply predict the temperature and velocity profiles along the axial and radial directions by means of the empirical correlations and Tollmien's theory was improved on the basis of the new test data. The results validate the CFD model of analysis. Furthermore, the turbulent jet model developed in this study can be used to analyze pool thermal mixing when an ellipsoidal steam jet is discharged under a high steam mass flux in a subcooled water pool.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4571-4584
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• 2022

The analysis of rapid flow transients in Reactor Coolant Pumps (RCP) is essential for a reactor safety study. An accurate and precise analysis of the RCP coastdown is necessary for the reactor design. The coastdown of RCP affects the coolant temperature and the colloidal crud in the primary coolant. A realistic and kinetic model has been used to investigate the behavior of activated colloidal crud in the primary coolant and steam generator that solves the pump speed analytically. The analytic solution of the non-dimensional flow rate has been determined by the energy ratio β. The kinetic energy of the coolant fluid and the kinetic energy stored in the rotating parts of a pump are two essential parameters in the form of β. Under normal operation, the pump's speed and moment of inertia are constant. However, in a coastdown situation, kinetic damping in the interval has been implemented. A dynamic model ACCP-SMART has been developed for System Integrated Modular and Advanced Reactor (SMART) to investigate the corrosion due to activated colloidal crud. The Fickian diffusion model has been implemented as the reference corrosion model for the constituent component of the primary loop of the SMART reactor. The activated colloidal crud activity in the primary coolant and steam generator of the SMART reactor has been studied for different equilibrium corrosion rates, linear increase in corrosion rate, and dynamic RCP coastdown situation energy ratio b. The coolant specific activity of SMART reactor equilibrium corrosion (4.0 mg s^-1) has been found 9.63×10^-3 µCi cm^-3, 3.53×10^-3 µC cm^-3, 2.39×10^-2 µC cm^-3, 8.10×10^-3 µC cm^-3, 6.77× 10^-3 µC cm^-3, 4.95×10^-4 µC cm^-3, 1.19×10^-3 µC cm^-3, and 7.87×10^-4 µC cm^-3 for ²⁴Na, ⁵⁴Mn, ⁵⁶Mn, ⁵⁹Fe, ⁵⁸Co, ⁶⁰Co, ⁹⁹Mo, and ⁵¹Cr which are 14.95%, 5.48%, 37.08%, 12.57%, 10.51%, 0.77%, 18.50%, and 0.12% respectively. For linear and exponential coastdown with a constant corrosion rate, the total coolant and steam generator activity approaches a higher saturation value than the normal values. The coolant and steam generator activity changes considerably with kinetic corrosion rate, equilibrium corrosion, growth of corrosion rate (ΔC/Δt), and RCP coastdown situations. The effect of the RCP coastdown on the specific activity of the steam generators is smeared by linearly rising corrosion rates, equilibrium corrosion, and rapid coasting down of the RCP. However, the time taken to reach the saturation activity is also influenced by the slope of corrosion rate, coastdown situation, equilibrium corrosion rate, and energy ratio β.