• Nuclear Engineering and Technology
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• 제40권5호
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• pp.387-396
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• 2008

Many experimental analyses for annular film dryouts, which is one of the Critical Heat Flux (CHF) mechanisms, have been performed because of their importance. Numerical approaches must also be developed in order to assess the results from experiments and to perform pre-tests before experiments. Various thermal-hydraulic codes, such as RELAP, COBRATF, MARS, etc., have been used in the assessment of the results of dryout experiments and in experimental pre-tests. These thermal-hydraulic codes are general tools intended for the analysis of various phenomena that could appear in nuclear power plants, and many models applying these codes are unnecessarily complex for the focused analysis of dryout phenomena alone. In this study, a numerical model was developed for annular film dryout using the drift-flux model from uniform heated tube geometry. Several candidates of models that strongly affect dryout, such as the entrainment model, deposition model, and the criterion for the dryout point model, were tested as candidates for inclusion in an optimized annular film dryout model. The optimized model was developed by adopting the best combination of these candidate models, as determined through comparison with experimental data. This optimized model showed reasonable results, which were better than those of MARS code.

• Nuclear Engineering and Technology
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• 제55권5호
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• pp.1604-1615
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• 2023

In an open-pool type research reactor with a downward forced flow in the core, pipes can be under sub-atmospheric pressure because of the large pressure drop at the reactor core in the atmospheric pool. Sub-atmospheric pressure can result in air inflow into the pipe from the pressure difference between the atmosphere and the inside of the pipe, which in a postulated pipe break scenario can lead to the breakdown of the cooling pump. In this study, a plant-scale experiment was conducted to study air inflow in large piping systems by considering the actual operational conditions of an advanced research reactor. The air inflow rate was measured, and the entrained air was visualized to investigate the behavior of air inflow and flow regime depending on the pipe break size. In addition, the developed drift-flux model for a large vertical pipe with a diameter of 600 mm was compared with other correlations. The flow regime transition in a large vertical pipe under downward flow was also studied using the newly developed drift-flux model. Consequently, the characteristics of two-phase flow in a large vertical pipe were found to differ from those in small vertical pipes where liquid recirculation was not dominant.

• 대한기계학회논문집A
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• 제33권3호
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• pp.265-268
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• 2009

We present the experimental study to realize a DNA separation chip using asymmetrically-switched nonuniform electric fields. The DNA separation chip redistributes DNA molecules within a specific area based on the size- and field-dependent nonlinearity of DNA drift velocity. The present chip is composed of a width variable channel to distribute nonuniform electric field, a DNA loading slit and a pair of electrodes to apply electric field. We focus on the design of DNA separation chips with identifying the nonlinearity of DNA drift velocity using three different DNA molecules (11.1kbp, 15.6kbp, and 48.5kbp) in the chips. It is demonstrated that different size of DNA shows different net migration in different direction under the asymmetrically-switched nonuniform electric field.

• 수산해양기술연구
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• 제40권4호
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• pp.255-267
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• 2004

기선권현망어업의 어구 개량과 조업시스템 개선을 목적으로 자루그물을 A, B 2가지로 달리한 축소형 개량어구를 설계, 제작하여 현장조업선에 의한 해상실험을 실시하여 어구의 형상을 관찰한 결과를 요약하면 다음과 같다. 1. 축소형 개량어구의 실제 전개율은 오비기에서 20% 정도로 가장 작았고, 뒤쪽으로 갈수로 커지며, 자루그물에서는 110% 정도로 가장 컸으며, B형이 A형에 비하여 5~10%정도 크게 나타났다. 자루그물 입구와 뒤끝의 망고 변화폭은 A형이 9.0~13.6, 9.3·10.4m이고, B형이 10.9~14.8, 5.8~8.0m로 나타나서 B형이 A형에 비하여 자루그물 입구는 1~2m 크고, 뒤끝은 2~3m 작았다. 2. 축소형 개량어구는 오비기의 수직방향 전개성능이 개선되어 수비에 이르기까지의 예망수층이 완만하게 형성되었으며, 예망수층의 변화폭이 기존어구에 비해 적게 나타났다. 나발 그물이 포켓형상을 개선시켜 그물코의 날림현상 감소와 수비에서 자루그물까지의 어구형상이 완만하게 이루어졌으며, 예망속도가 느린 경우에도 어구의 형상이 안정되었다. 3. 축소형 개량어구 B형은 자루그물의 변화폭이 적었고, 이중깔대기의 부착으로 인해 입망된 어군의 도피율이 감소하였다.

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.439-458
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• 2013

REX-10 is a fully-passive small modular reactor in which the coolant flow is driven by natural circulation, the RCS is pressurized by a steam-gas pressurizer, and the decay heat is removed by the PRHRS. To confirm design decisions and analyze the transient responses of an integral PWR such as REX-10, a thermal-hydraulic system code named TAPINS (Thermal-hydraulic Analysis Program for INtegral reactor System) is developed in this study. Based on a one-dimensional four-equation drift-flux model, TAPINS incorporates mathematical models for the core, the helical-coil steam generator, and the steam-gas pressurizer. The system of difference equations derived from the semi-implicit finite-difference scheme is numerically solved by the Newton Block Gauss Seidel (NBGS) method. TAPINS is characterized by applicability to transients with non-equilibrium effects, better prediction of the transient behavior of a pressurizer containing non-condensable gas, and code assessment by using the experimental data from the autonomous integral effect tests in the RTF (REX-10 Test Facility). Details on the hydrodynamic models as well as a part of validation results that reveal the features of TAPINS are presented in this paper.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2747-2756
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• 2023

Reinforced Concrete (RC) shear walls are one of the civil structures in nuclear power plants to resist lateral loads such as earthquakes and wind loads effectively. Risk-informed and performance-based regulation in the nuclear industry requires considering possible accidents and determining desirable performance on structures. As a result, rather than predicting only the ultimate capacity of structures, the prediction of performances on structures depending on different damage states or various accident scenarios have increasingly needed. This study aims to develop machine-learning models predicting drifts of the RC shear walls according to the damage limit states. The damage limit states are divided into four categories: the onset of cracking, yielding of rebars, crushing of concrete, and structural failure. The data on the drift of shear walls at each damage state are collected from the existing studies, and four regression machine-learning models are used to train the datasets. In addition, the bagging ensemble method is applied to improve the accuracy of the individual machine-learning models. The developed models are to predict the drifts of shear walls consisting of various cross-sections based on designated damage limit states in advance and help to determine the repairing methods according to damage levels to shear walls.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.19-33
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• 2024

In nuclear thermal-hydraulic system codes, most correlations used for vertical pipes, under downward two-phase flow, have been developed considering small pipes or pool systems. This suggests that there could be uncertainties in applying the correlations to accident scenarios involving large vertical pipes owing to the difference in the characteristics of two-phase flows, or flow conditions, between large and small pipes. In this study, we modified the Multi-dimensional Analysis of Reactor Safety KINS Standard (MARS-KS) code using correlations, such as the drift-flux model and two-phase multiplier, developed in a plant-scale air-inflow experiment conducted for a pipe of diameter 600 mm under downward two-phase flow. The results were then analyzed and compared with those based on previous correlations developed for small pipes and pool conditions. The modified code indicated a good estimation performance in two plant-scale experiments with large pipes. For the siphon-breaking experiment, the maximum errors in water flow for modified and original codes were 2.2% and 30.3%, respectively. For the air-inflow accident experiment, the original code could not predict the trend of frictional pressure gradient in two-phase flow as / increased, while the modified MARS-KS code showed a good estimation performance of the gradient with maximum error of 3.5%.

• Nuclear Engineering and Technology
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• 제51권5호
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• pp.1417-1427
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• 2019

In this study, we evaluated the performance of a commercial pixelated cadmium zinc telluride (CZT) detector for spectroscopy and identified its feasibility as a Compton camera for radiation monitoring in a nuclear power plant. The detection system consisted of a $20mm{\times}20mm{\times}5mm$ CZT crystal with $8{\times}8$ pixelated anodes and a common cathode, in addition to an application specific integrated circuit. The performance of the various radioisotopes $^{57}Co$, $^{133}Ba$, $^{22}Na$, and $^{137}Cs$ was evaluated. In general, the amplitude of the induced signal in a CZT crystal depends on the interaction position and material non-uniformity. To minimize this dependency, a drift time correction was applied. The depth of each interaction was calculated by the drift time and the positional dependency of the signal amplitude was corrected based on the depth information. After the correction, the Compton regions of each spectrum were reduced, and energy resolutions of 122 keV, 356 keV, 511 keV, and 662 keV peaks were improved from 13.59%, 9.56%, 6.08%, and 5%-4.61%, 2.94%, 2.08%, and 2.2%, respectively. For the Compton imaging, simulations and experiments using one $^{137}Cs$ source with various angular positions and two $^{137}Cs$ sources were performed. Individual and multiple sources of $^{133}Ba$, $^{22}Na$, and $^{137}Cs$ were also measured. The images were successfully reconstructed by weighted list-mode maximum likelihood expectation maximization method. The angular resolutions and intrinsic efficiency of the $^{137}Cs$ experiments were approximately $7^{\circ}-9^{\circ}$ and $5{\times}10^{-4}-7{\times}10^{-4}$, respectively. The distortions of the source distribution were proportional to the offset angle.

• The Korean Journal of Ecology
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• 제16권4호
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• pp.489-499
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• 1993

1989년 8월부터 1990년 5월까지 4계절에 걸쳐 낙동강 지류인 배내천 중류에서 drift net를 이용하여 표류하는 수서곤충을 채집하고 저서 채집 결과와 비교하였다. 총 6목 31과 4속 44종 4452개체가 채집되었는데, 가장 많은 종이 채집된 계절은 가을이었으나, 개체수는 Baetis, Pseudocloeon, Eporus, Heptagenia속 등의 하루살이목이 급중한 봄에 가장 높게 채집되었다. 일반적으로 저서 채집보다는 표류 채집에서 적은 종류가 출현하였다. 주요목별로 계절적 출현 양상을 비교해본 결과 파리목은 저서 채집과 표류채집에서 전체적으로 22%의 비율로 유사하게 출현하였고, 하루살이 목은 저서 채집(33%)보다 표류채집(62%)에서 높은 비율로 채집되었으며, 이보다 낮게 출현한 강도래목과 날도래목은 표류 채집보다 저서 채집에서 상대적으로 높게 나타났다. 겨울을 제외하고는 표류 채집에서 하루살이목에 속하는 Pseudocloeon sp., Heptagenia sp., Baetis sp. 등이 제1우점종으로 나타났다. 반면에 저서 채집에서는 날도래목은 Lepidostoma sp. 와 파리목인 Diamesa sp.등이 제1우점종으로 나타났 다. 일반적으로 collector와 scraperdo 해당하는 1차 소비자들이 많이 표류하였는데, collector는 겨울에 많이 표류한 반면, scraper는 겨울에 상대적으로 적게 표류하였다. 대체로 유속이 느린 곳에 서식하는 shredder나, 2차 소비자인 predatro들은 적게 표 류하였다. Habit group으로서는 clinger와 swimmer들이 많이 표류한 반면 burrower 와 sprawler들은 전반적으로 적게 출현하였다. Clinger는 여름에 상대적으로 적게 표류하였고, Swimmer는 봄에 많이 출현하였다.

• 해양환경안전학회지
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• 제25권5호
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• pp.535-541
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• 2019

본 연구는 해상풍력발전단지 내 어업의 가능성을 살펴보고자, 어구 및 어법이 해상풍력발전단지 내 터빈과 해저케이블에 미치는 위험도를 평가하였다. 서남해 해상풍력발전단지를 연구 대상 해역으로 설정하여, 주변 국가어항의 선박 현황을 조사하였다. 어선의 현황을 참조하여 22개의 어구 및 어법에 대하여 위험도 평가 기준을 설정하고, 전문가를 통해 위험도를 평가하였다. 위험도가 낮아 해상풍력발전단지 내에서도 조업이 가능하다고 판단되는 어구 및 어법은 외줄낚시, 대낚시, 멸치챗배였으며, 위험도가 보통으로서 조업이 가능하기는 하나, 주의가 필요하다고 생각되는 어구 및 어법은 바닥주낙, 뜬주낙, 끌낚시, 오징어채낚기, 문어단지, 주꾸미소호, 연안통발, 주목망, 낭장망, 고정자망, 유자망이었다. 위험도가 높아 해상풍력발전단지 내 조업이 어렵다고 판단되는 어구 및 어법은 형망, 빔트롤, 건착망류였으며, 위험도가 아주 높아 해상풍력발전단지 내 어업이 허용되기 어렵다고 판단되는 어구 및 어법은 안강망, 기선권현망, 오터트롤, 외끌이기선저인망, 쌍끌이기선저인망이었다.