• 한국산학기술학회논문지
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• 제20권3호
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• pp.638-644
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• 2019

본 연구에서는 전산유체역학 해석을 이용하여 알루미늄 피라미드 트러스 심재 샌드위치의 열유동 특성을 분석하였다. 규칙적 다공질 금속인 피라미드 트러스 코어를 샌드위치 구조물에 채용할 경우 공기 매질이 자유롭게 유입, 유출될 수 있는 개방형 코어인 점을 고려하여 하중을 지지할 수 있는 구조성능과 함께 방열체로서 다기능성을 구현할 수 있는 구조가 된다. 따라서, 유입되는 공기의 속도변화, 설계변수인 트러스각에 따른 압력강하와 열전달 메카니즘을 확인하기 위해 ANSYS/Fluent를 이용하여 수치해석을 실시하였다. 해석모델에 사용된 샌드위치 패널은 알루미늄으로 이루어져 있으며, 샌드위치 패널의 위 면재와 아래 면재 사이에는 15개의 피라미드 트러스 유닛셀이 반복되고 있다. 폭 방향으로는 무한히 넓은 유닛셀을 모사하기 위해 대칭조건을 지정하였으며, 입구에는 균일한 속도분포를 경계조건으로 입력하였다. 해석결과 입구부와 첫 유닛셀까지의 구간에서 입구영향이 관찰되었으며, 입구영향을 배제하고 마찰계수와 누셀수를 분석하였다. 공기의 속도가 증가할수록 마찰계수는 감소하였으며, 누셀수는 증가하는 경향을 보인다. 한편, V=1m/s에서 5m/s에서의 마찰계수와 누셀수 변화가 확연하였으며, 이는 층류에서 난류로 유동패턴이 변하기 때문에 거시적으로 열전도보다 대류열전달의 비중이 커졌기 때문이다. 또한, 설계변수인 트러스각에 대해서는 의미가 있을 정도의 마찰계수와 누셀수의 변화는 관찰되지 않았다. 따라서, 트러스각이 강도, 강성 등 구조성능에 민감한 점을 감안하면 다기능성을 염두에 둔 알루미늄 피라미드트러스 심재 설계 시 설계변수의 변화는 구조성능에 더 민감할 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제31권1호
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• pp.68-79
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• 1999

The YGN Units 3&4 plant conditions during shutdown operation were reviewed to identify the possible event scenarios following the loss of shutdown cooling (SDC) event. For the five cases of typical reactor coolant system (RCS) configurations under the worst event sequence, such as unavailable secondary cooling and no RCS inventory makeup, the thermal hydraulic analyses were performed using the RELAP5/MOD3.2 code to investigate the plant behavior following the event. The thermal hydraulic analyses include the estimation of time to boil, time to core uncovery, and time to core heat up to determine the containment closure time to prevent the uncontrolled release of fission products to atmosphere. The result indicates that the containment closure is recommended to be achieved within 42 minutes after the loss of SDC for the steam generator (SG) inlet plenum manway open case or the large cold leg open case under the worst event sequence. The containment closure time is significantly dependent on the elevation and size of the opening and the SG secondary water level condition. It is also found that the containment closure needs to be initiated before the boiling time to ensure the survivability of the workers in the containment. These results will provide useful information to operators to cope with the loss of SDC event.

• Nuclear Engineering and Technology
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• 제45권5호
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• pp.581-588
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• 2013

This paper deals with the Safety Analysis for $CANDU^{(R)}$ 6 nuclear reactors as affected by main Heat Transport System (HTS) aging. Operational and aging related changes of the HTS throughout its lifetime may lead to restrictions in certain safety system settings and hence some restriction in performance under certain conditions. A step in confirming safe reactor operation is the tracking of relevant data and their corresponding interpretation by the use of appropriate thermal-hydraulic analytic models. Safety analyses ranging from the assessment of safety limits associated with the prevention of intermittent fuel sheath dryout for a slow Loss of Regulation (LOR) analysis and fission gas release after a fuel failure are summarized. Specifically for fission gas release, the thermal-hydraulic analysis for a fresh core and an 11 Effective Full Power Years (EFPY) aged core was summarized, leading to the most severe stagnation break sizes for the inlet feeder break and the channel failure time. Associated coolant conditions provide the input data for fuel analyses. Based on the thermal-hydraulic data, the fission product inventory under normal operating conditions may be calculated for both fresh and aged cores, and the fission gas release may be evaluated during the transient. This analysis plays a major role in determining possible radiation doses to the public after postulated accidents have occurred.

• Nuclear Engineering and Technology
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• 제25권2호
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• pp.204-214
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• 1993

본 논문은 원자력발전소의 배관설계에 파단전 누설(leak-before-break : LBB) 개념이 적용됨에 따라 새롭게 해석대상이 된 분기관파단에 의한 노심지지배럴의 쉘응답을 계산한 것이다. 앞으로 직경 10인치 이상의 고에너지 배관에 대해 LBB 개념이 적용될 것으로 예상되는 바, 이 경우 LBB 적용대상에서 제외되는 유일한 1차측 배관인 3인치 가압기 분무관의 파단을 가정하였고 이때 노심 지지배럴에 가해지는 쉘응답을 구하였다. 이들 응답을 직경 10인치 이상인 배관파단시의 응답과 비교한 결과 앞으로 직경 10인치 이상의 배관에 대해 LBB 개념이 적용될 경우 배관파단에 대한 노심지지배럴의 쉘응답은 무시할 수 있음을 보였다.

• Journal of Advanced Marine Engineering and Technology
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• 제35권7호
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• pp.907-913
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• 2011

Swirling flows are related to the spiral motion in the tangential direction in addition to the axial and radial direction using several swirl generators. These type of flows are used in combustion chambers to improve flame stability, heat exchanger to enhance heat transfer coefficients, agricultural spraying machines and some vertical pipes to move slurries or transport of materials. However, only a few studies three dimensional velocity profiles in a vertical pipe have been reported. In this present paper, 3 dimension particle image velocimetry(PIV) technique was employed to measure the velocity profiles in water along a vertical circular pipe with Reynolds number from 6000 to 13,000. A tangential inlet condition was used as the swirl generator to produce the required flow. The velocities were measured with swirling flow in the water along the test section using the PIV technique.

• 한국전산유체공학회지
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• 제7권3호
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• pp.44-52
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• 2002

An analytic methodology was developed for free surface motions between liquid metal coolant and cover gas in order to calculate the phenomena of gas entrainment in hot pool surface through IHX EMP and reactor core. The methodology was setup by applying the first order VOF convection model to CFX4 general purpose fluid dynamics analysis code. The methodology was validated by applying it to an experimental apparatus designed for free surface motions of KALIMER reactor. The distributions of free surface calculated by the present methodology were almost coincident with the experimental data. The developed methodology was applied to the KALIMER reactor of full power operating condition. The shapes of the free surface were nearly uniform. From the results, it was found that the altitude of the free surface from the IHX inlet nozzle of KALIMER reactor is high enough not to affect to free surface motions of generating gas bubbles from the turbulent shear flows such as hydraulic jump and water falls.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1998년도 추계학술대회 논문집 학회본부 C
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• pp.1054-1060
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• 1998

Previous counter-current flow limitation (CCFL) and critical heat flux (CHF) studies included investigations on the inlet entrance, inclined channel and gap effects for the most part. In this study, the local CHF correlation was presented to be used in the numerical analysis for the 3 dimensional hemispherical geometry. Also, first-principle analyses were performed to determine the maximum heat removal capability from the debris through the gap that may be formed during a core melt accident. The maximum heat removal capability by gap cooling can be applied in quantitatively assessing the severe accident management measures.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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• pp.254-259
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• 1996

The hydraulic tests for 16$\times$16 JDFA were performed to obtain the pressure loss coefficients using the FACTS. The pressure loss coefficients are calculated by converting the each properties of experimental values for inlet region, mixing vane grid, outlet region and core region by performing a power fit of the pressure loss coefficient values to the corresponding Reynolds number. The test results are compared with the existing calculated values and evaluated by using the CALOPR code in terms of pressure drop. It is turned out that the differences between the test results and the calculated values are about by 3.8% for the pressure loss coefficients and by 8.5% for the pressure drop.

• 한국분무공학회지
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• 제6권2호
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• pp.9-15
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• 2001

The internal flow characteristics of a gasoline direct injector have been studied to improve fuel economy and reduce exhaust emissions. Computational Fluid Dynamics (CFD) is used to examine the internal flow of the GDI with the purpose of designing the optimum geometry of the injector. This study tests orifice length, cone angle, swirl angle, orifice diameter and needle lift. The results show that optimum sizes of the orifice length, cone angle, swirl angle, orifice diameter and needle lift are 0.8mm, $140^{\circ},\;120^{\circ},\;80mm\;and\;70{\mu}m$, respectively. The size of the lift does not affect the formation of the air core signficantly near the tip of the needle compared to the ball-type needle. The vena contracta phenomenon near the orifice inlet can be released by smoothing the edge.

• 한국대기환경학회지
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• 제6권2호
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• pp.161-167
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• 1990

The reaction of sulfur dioxide with cupric oxide supported on zeolite was investigated over a temperature range of $250{\sim}450^{{\circ}C$. After the completion of the $SO_2$ removal reaction, the cupric sulfate produced was regenerated to copper by hydrogen or LPG. The experimental results showed that the removal efficiency of $SO_2$ was improved with temperature increase and with $SO_2$ inlet concentration decrease. The reaction of $SO_2$ with CuO/Zeolite was well explained by the shrinking unreacted core model using first order chemical reaction control and diffusion control. THe reaction rate constant and the effective diffusivity were respectively as follows: 1k (cm/s) = 2.519 exp[-10991 (cal/mol)/RT] $De(cm^2/s) = 2.06 \times 10^{-5} exp[-8380 (cal/mol)/RT]$