• 한국추진공학회지
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• 제22권3호
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• pp.8-13
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• 2018

ZPP(Zirconium Potassium Perchlorate)는 산화제 potassium perchlorate, 금속원료 zirconium, 결합제 Viton 조성의 점화제이다. ZPP는 항공우주산업, 추진제 점화원, 자동화 산업에 사용되고 있다. 본 연구에서는 PMD(Pyrotechnic Mechanical Device)에 사용되는 ZPP의 제조공정 및 형상/열량/압력값과 같은 특성을 연구하였다. ZPP 제작 시, 원료들을 고속으로 교반하여 ZPP가 균일한 입자크기 및 형상으로 제작될 수 있도록 혼화공정을 설계하였다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 추계학술발표회논문집(1)
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• pp.669-674
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• 1997

LAVA(Lower-plenum Arrested Vessel Attack) 실험은 중대사고시 고온의 노심 용융물이 냉각수가 존재하는 원자로 용기 하부 반구내로 재배치되는 경우 노심 용융물과 하부반구의 열적 거동 모사와 노심용융물과 하부 반구 사이의 구조 분석 및 고화 후의 용융물형상에 대한 관측을 통하여 노심용융물의 자연 냉각 현상을 규명하고자 하는 실험 연구이다. 원자로 용기 하부 반구를 1/8로 선형 축소한 반구형 반응 용기 내부로 $Al_2$O$_3$/Fe Thermite 용융물을 주입하여 용융물과 하부 반구 사이의 구조 및 하부 반구의 열적 거동을 분석하는 실험을 2회 수행하였다. 각각 20, 40kg의 $Al_2$O$_3$/Fe Thermite 용융물을 주입시 킨 LAVA_PRE, LAVA-1 실험 결과 용융물 주입에 따른 하부 반구의 파손은 발생하지 않았으며, 유사한 실험조건에서 수행된 일본 ALPHA실험에 비해서는 하부 반구의 최대 온도가 500 K 이상 높게 측정되었고 냉각율 또한 현저히 낮게 나타났다. 이는 $Al_2$O$_3$/Fe Thermit 용융물중 과열상태의 Fe성분이 하부 반구와 용접되었기 때문으로 판단되며 보다 정확한 하부 반구의 열적거동을 모사하기 위하여 반구 시편에 대한 재료, 조직 검사를 수행하고 있다. 추후의 실험에서는 하부 반구 내외부의 압력 부하에 따른 반응 양상 및 Fe 용융물(금속용융물) 성분을 제거하고 순수한 $Al_2$O$_3$용융물(산화용융물) 만을 주입하여 용융물 성분에 따른 하부 반구의 열적거동을 분선 할 예정이다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 추계학술발표회논문집(1)
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• pp.784-789
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• 1997

원자력 발전소에서의 중대사고시, 고온의 노심 용융물이 원자로 공동으로 떨어지면 노심용융물과 콘크리트간의 반응(MCCI)에 의한 여러가지 현상으로 인해 격납용기의 건전성을 위협할 수 있다 본 연구에서는 국내 원전에서의 MCCI 현상에 대한 실험과 해석결과를 살펴보았다. 실험은 영광원전 3,4호기 원자로 공동구조물의 콘크리트를 대상으로 thermite 20kg을 사용한 것이며 해석은 MELCOR 코드내의 MCCI 상세해석 모듈인 CORCON-MOD3를 이용하였다. 해석에 사용된 콘크리트의 화학성분과 열물성은 실험을 통하여 측정한 값을 사용하였으며 해석결과는 실험 결과와 비교하였다. 또한 GORCON 코드에서의 MCCI 현상의 해석시 용융물의 초기온도, 용융물의 질량, 콘크리트의 종류에 따른 예측결과들을 비교하였다. MCCI 현상의 해석시 콘크리트의 종류에 따른 가스발생량과 구성성분의 변화가 크게 나타남으로 콘크리트의 화학적 구성성분을 적합하게 입력하여야 한다. 콘크리트로의 종류에 따른 하부로의 열유속은 크게 차이가 없으나 침식율은 크게 차이가 나며 이는 콘크리트의 상변화 잠열의 차이에서 기인한 것이다. CORCON 코드는 실험에 비해 작은 침식율을 예측하고 있으며 콘크리트의 침식율은 용융물의 양에 비해 초기온도의 변화에 더 큰 영향을 받는 것으로 예측하고 있다.

• 한국전산유체공학회지
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• 제7권1호
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• pp.10-19
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• 2002

The non-staggered(collocated) grid approach in which all the solution variables are located at the centers of control volumes is very popular for incompressible flow analyses because of its numerical efficiency on the curvilinear or unstructured grids. Rhie and Chow's paper is the first in using non-staggered grid method for SIMPLE algorithm, where pressure weighted interpolation was used to prevent decoupling of pressure and velocity. But it has been known that this non-staggered grid method has stability problems when pressure fields are nonlinear like in natural convection flows. Also Rhie-Chow scheme generates large numerical diffusion near curved walls. The cause of these unwanted problems is too large pressure damping term compared to the magnitude of face velocity. In this study the magnitude of pressure damping term of Rhie-Chow's method is limited to 1∼10% of face velocity to prevent physically unreasonable solutions. The wall pressure extrapolation which is necessary for cell-centered FVM is another source of numerical errors. Some methods are applied in a unstructured FV solver and analyzed in view of numerical accuracy. Here, two natural convection problems are solved to check the effect of the Rhie-Chow's method on numerical stability. And numerical diffusion from Rhie-Chow's method is studied by solving the inviscid flow around a circular cylinder.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 춘계학술대회논문집B
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• pp.176-180
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• 2001

In this paper, we have studies the images have been reconstructed by using combination of images which has been acquired by the variation of operating frequency. When inner images has been reconstructed, inner image has been superposition by surface state effect. In this case, image enhancement the phase object and enhance the contrast of inner image. In the result of the specimen for the round defect with 2mm diameter, for the types of the depth are 1.5mm, 2mm, 2.5mm, and 3mm, it has been show that the shape of defect has better than before this processing and phase contrast grow large twice. And we have constructed the acoustic microscope by using quadrature detector that is able simultaneously to acquired the amplitude and phase of the reflected signal. Father more we have studied the reconstruction method of the amplitude and phase images and the enhancement method of the defect images' contrast.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2004년도 춘계학술대회
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• pp.2141-2145
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• 2004

As part of study on thermal hydraulic behavior in the reactor cavity under external vessel cooling in the APR (Advanced Power Reactor) 1400, one dimensional two phase flow of steady state in the reactor cavity have been analyzed to investigate a coolant circulation mass flow rate in the annulus region between the reactor vessel and the insulation material using the RELAP5/MOD3 computer code. The RELAP5/MOD3 results have shown that a two phase natural circulation flow of 300 - 600 kg/s is generated in the annulus region between the reactor vessel and the insulation material when the external vessel cooling has been applied in the APR 1400. An increase in the heat flux of the inner vessel leads to an increase of the coolant mass flow rate. An increase in the coolant outlet area leads to an increase in the coolant circulation mass flow rate, but the coolant inlet area does not effective on the coolant circulation mass flow rate. The change of the lower coolant outlet to a lower position affects the coolant circulation mass flow rate, but the variation trend is not consistent.

• 한국추진공학회:학술대회논문집
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• 한국추진공학회 2017년도 제48회 춘계학술대회논문집
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• pp.445-450
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• 2017

ZPP(Zirconium Potassium Perchlorate)는 산화제 potassium perchlorate, 금속원료 zirconium, 결합제 Viton 조성의 점화제이다. ZPP는 항공우주산업, 추진제 점화원, 자동화 산업에 사용되고 있다. 본 연구에서는 PMD(Pyrotechnic Mechanical Device)에 사용되는 ZPP의 제조공정 및 형상/열량/압력값과 같은 특성을 연구하였다. ZPP 제작 시, 원료들을 고속으로 교반하여 ZPP가 균일한 입자크기 및 형상으로 제작될 수 있도록 혼화공정을 설계하였다.

• 한국전산유체공학회:학술대회논문집
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• 한국전산유체공학회 2009년 추계학술대회논문집
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• pp.121-128
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• 2009

During a hypothetical high-pressure accident in a nuclear power plant (NPP), molten corium can be ejected through a breach of a reactor pressure vessel (RPV) and dispersed by a following jet of a high-pressure steam in the RPV. The dispersed corium is fragmented into smaller droplets in a reactor cavity of the NPP by the steam jet and released into other compartments of the NPP by a overpressure in the cavity. The fragments of the corium transfer thermal energy to the ambient air in the containment or interact chemically with steam and generate hydrogen which may be burnt in the containment. The thermal loads from the ejected molten corium on the containment which is called direct containment heating (DCH) can threaten the integrity of the containment. DCH in a NPP containment is related to many physical phenomena such as multi-phase hydrodynamics, thermodynamics and chemical process. In the evaluation of the DCH load, the melt dispersion rates depending on the RPV pressure are the most important parameter. Mostly, DCH was evaluated by using lumped-analysis codes with some correlations obtained from experiments for the dispersion rates. In this study, MC3D code was used to evaluate the dispersion rates in the APR1400 NPP during the high-pressure accidents. MC3D is a two-phase analysis code based on Eulerian four-fields for melt jet, melt droplets, gas and water. The dispersion rates of the corium melt depending on the RPV pressure were obtained from the MC3D analyses and the values specific to the APR1400 cavity geometry were compared to a currently available correlation.

• 한국전산유체공학회지
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• 제10권3호
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• pp.9-18
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• 2005

During a hypothetical severe accident in a nuclear power plant (NPP), hydrogen is generated by the active reaction of fuel-cladding and steam in the reactor pressure vessel and released with steam into the containment. In order to mitigate hydrogen hazards possibly occurred in the NPP containment, hydrogen mitigation system (HMS) is usually adopted. The design of the next generation NPP (APR1400) designed in Korea specifies 26 passive autocatalytic recombiners and 10 igniters installed in the containment for the hydrogen mitigation. in this study, the analysis of the hydrogen and steam behavior during a total lose of feed water (TLOFW) accident in the APR1400 containment has been conducted by using the CFD code GASFLOW. During the accident, a huge amount of hot water, steam, and hydrogen is released in the in-containment refueling water storage tank (IRWST). The current design of the APR1400 includes flap-type dampers at the IRWST vents which are operated depending on the pressure difference between inside and outside of the IRWST. it was found that the flaps strongly affects the flow structure of the steam and hydrogen in the containment. The possibilities of a flame acceleration and transition from deflagration to detonation (DDT) were evaluated by using Sigma-Lambda criteria. Numerical results indicate the DDT possibility could be heavily reduced in the IRWST compartment when the flaps are installed.

• 한국대기환경학회지
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• 제22권1호
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• pp.15-24
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• 2006

Precipitation samples were collected at Anmyeon (1997 - 2004), Uljin, and Gosan (1998 ~ 2004), the background area of the Korean Peninsula. These samples were analyzed for the concentration of 9 major ionic components ($F^{-}$,$Cl^{-}$, $NO_{3}^{-}$, $SO_{4}^{2-}$, $Na^{+}$, $NH_{4}^{+}$, $K^{+}$, $Mg^{2+}$, $Ca^{2+}$) with including a pH and an electric conductivity. Data quality for these samples was verified by ion balance and conductivity balance which are based on GAW manual for precipitation chemistry and the number of valid data at Anmyeon, Uljin, and Gosan is 249, 173, and 188, respectively. During the study period, the precipitation-weighted average pH at Anmyeon, Uljin, and Gosan was found to be 4.81, 4.87 and 4.89, respectively and each annual average pH was showed below pH 5.6 for every site. From the frequency survey on the precipitation acidity, the occurrence rate of acid rain below pH 5.6 is greater than $80\%$ for every site. Particularly, the highest occurrence rate for strong acid rain below pH 4.5 was found at Anmyeon, $32.1\%$, compared with other sites ($10.4\%$ at Uljin, $15.4\%$ at Gosan). That's because acidifying species (nss-$SO_{4}^{2-}$, $NO_{3}^{-}$) are remarkably high concentration at Anmyeon.