• 한국항공우주학회지
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• 제50권2호
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• pp.75-82
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• 2022

내부 압력과 압축하중을 받는 발사체 추진제 탱크 구조의 좌굴 하중을 비파괴적으로 예측할 수 있는 기법이 필요하다. 기하학적 초기 결함이 존재하는 단순 원통 구조의 전역 좌굴 하중은 좌굴이 발생하지 않는 범위에서의 고유진동수-압축하중의 상관관계를 이용한 Vibration correlation technique (VCT)을 사용하여 비파괴적으로 예측 가능하다. 본 연구에서는 내부 압력과 압축하중을 동시에 받는 추진제 탱크 구조 형태인 얇은 금속재 단순 원통 구조의 진동 및 좌굴 시험을 수행하였고 VCT를 이용하여 전역 좌굴 하중을 예측하였다. 두께가 얇은 구조의 진동 시험을 위해 스피커를 이용한 비접촉식 가진 방법을 이용하였고 응답은 고분자 압전 센서(PVDF)로 측정하였다. VCT로 예측된 전역 좌굴 하중을 좌굴 시험에서 측정된 좌굴 하중과 비교하여 비파괴적 전역 좌굴 하중 예측 기법을 검증하였다.

• 한국추진공학회지
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• 제27권1호
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• pp.49-57
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• 2023

자가증기 가압시스템은 저비용, 고신뢰도의 장점으로 차세대 재사용 발사체들의 추진기관에 널리 채택되고 있다. 자가증기 가압시스템은 구조가 간단하나 탱크 내부에서 일어나는 열과 물질의 전달과정에 대한 이해가 필요하다. 이러한 이유로 자가증기 가압시스템의 모사시험을 구상하였다. 모사시험설비는 해외 가압시험설비 사례와 전문가의 자문을 기반으로 구성하였는데, 실제 자가증기 가압시스템과 달리 추진제 탱크를 단열하여 외부환경에 의한 영향을 배제하고자 하였으며, 열과 물질 전달현상의 연구의 편의를 위하여 가압가스 공급라인과 추진제 배관을 분리하였다. 제작된 자가증기가압 모사시험설비를 이용하여 극저온 추진제에서 가압가스의 응축현상, 헬륨을 이용한 가압과 증발된 추진제를 이용한 자가증기가압의 효율성 비교, 그리고 자가증기의 온도에 따른 가압능력을 평가할 수 있다.

• Nuclear Engineering and Technology
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• 제42권2호
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• pp.211-218
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• 2010

An analysis model on debris transport in the containment floor of pressurized water reactors is developed in which the flow field is calculated by Eulerian conservation equations of mass and momentum and the debris particles are traced by Lagrange equations of motion using the pre-determined flow field data. For the flow field calculation, two-dimensional Shallow Water Equations derived from Navier Stokes equations are solved using the Finite Volume Method, and the Harten-Lax-van Leer scheme is used for accuracy to capture the dry-to-wet interface. For the debris tracing, a simplified two-dimensional Lagrangian particle tracking model including drag force is developed. Advanced schemes to find the positions of particles over the containment floor and to determine the position of particles reflected from the solid wall are implemented. The present model is applied to calculate the transport fraction to the Hold-up Volume Tank in Advanced Power Reactors 1400. By the present model, the debris transport fraction is predicted, and the effect of particle density and particle size on transport is investigated.

• Nuclear Engineering and Technology
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• 제41권8호
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• pp.1045-1052
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• 2009

A calculation model is developed to predict the transient free surface flow on the containment floor following a loss-of-coolant accident (LOCA) of pressurized water reactors (PWR) for the use of debris transport evaluation. The model solves the two-dimensional Shallow Water Equation (SWE) using a finite volume method (FVM) with unstructured triangular meshes. The numerical scheme is based on a fully explicit predictor-corrector method to achieve a fast-running capability and numerical accuracy. The Harten-Lax-van Leer (HLL) scheme is used to reserve a shock-capturing capability in determining the convective flux term at the cell interface where the dry-to-wet changing proceeds. An experiment simulating a sudden break of a water reservoir with L-shape open channel is calculated for validation of the present model. It is shown that the present model agrees well with the experiment data, thus it can be justified for the free surface flow with accuracy. From the calculation of flow field over the simplified containment floor of APR1400, the important phenomena of free surface flow including propagations and interactions of waves generated by local water level distribution and reflection with a solid wall are found and the transient flow rates entering the Holdup Volume Tank (HVT) are obtained within a practical computational resource.

• 한국추진공학회지
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• 제19권5호
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• pp.98-103
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• 2015

가속도추종 유로개방장치는 고속 비행체의 가압식 연료탱크에서 연료가 쏠림현상으로 인해 단절되는 것을 막아 연속적으로 흐르게 한다. 기개발된 이 유로개방장치를 실제 고속으로 시험하는 것은 까다로운 시험조건과 비용문제로 많은 어려움이 따른다. 따라서 본 논문에서는 저속 항공기에 탑재해 기본적인 역중력 시험(Negative-g test)을 수행하고 RecurDyn으로 해석한 결과와 비교하였다. 그리고 고속비행체의 비행궤적에 따른 유로개방장치의 동역학적 거동을 RecurDyn으로 알아보았다.

• 한국추진공학회지
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• 제20권1호
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• pp.76-81
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• 2016

부력을 이용한 연료공급밸브는 고속 비행체의 가압식 연료탱크 내 연료가 역 중력 상태에서 한 방향으로 이동하는 것을 쫓아 유로를 열어주어 지속적으로 흐르게 한다. 가혹한 시험조건과 고비용 등의 문제로 이 연료공급밸브를 실제 고속으로 시험하는 것은 쉽지 않은 일이다. 따라서 본 연구는 고속 시험 전에 저속항공기에 탑재해 기본적인 회전기동 및 역중력 시험(Negative-g test)을 수행한 내용을 포함하고 있다. 시험 결과를 바탕으로 각 기동에서 밸브의 작동 특성을 파악하고 분석하였다.

• Nuclear Engineering and Technology
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• 제47권4호
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• pp.434-442
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• 2015

The advanced passive pressurized water reactor (PWR) is being constructed in China and the passive residual heat removal (PRHR) system was designed to remove the decay heat. During accident scenarios with increase of heat removal from the primary coolant system, the actuation of the PRHR will enhance the cooldown of the primary coolant system. There is a risk of power excursion during the cooldown of the primary coolant system. Therefore, it is necessary to analyze the thermal hydraulic behavior of the reactor coolant system (RCS) at this condition. The advanced passive PWR model, including major components in the RCS, is built by SCDAP/RELAP5 code. The thermal hydraulic behavior of the core is studied for two typical accident sequences with PRHR actuation to investigate the core cooling capability with conservative assumptions, a main steam line break (MSLB) event and inadvertent opening of a steam generator (SG) safety valve event. The results show that the core is ultimately shut down by the boric acid solution delivered by Core Makeup Tank (CMT) injections. The effects of CMT boric acid concentration and the activation delay time on accident consequences are analyzed for MSLB, which shows that there is no consequential damage to the fuel or reactor coolant system in the selected conditions.

• Nuclear Engineering and Technology
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• 제48권4호
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• pp.893-905
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• 2016

Numerous advanced reactor concepts have been proposed to replace light water reactors ever since their establishment as the dominant technology for nuclear energy production. While most designs seek to improve cost competitiveness and safety, the implausibility of doing so with affordable materials or existing nuclear fuel infrastructure reduces the possibility of near-term deployment, especially in developing countries. The organic nuclear concept, first explored in the 1950s, offers an attractive alternative to advanced reactor designs being considered. The advent of high temperature fluids, along with advances in hydrocracking and reforming technologies driven by the oil and gas industries, make the organic concept even more viable today. We present a simple, cost-effective, and safe small modular nuclear reactor for offshore underwater deployment. The core is moderated by graphite, zirconium hydride, and organic fluid while cooled by the organic fluid. The organic coolant enables operation near atmospheric pressure and use of plain carbon steel for the reactor tank and primary coolant piping system. The core is designed to mitigate the coolant degradation seen in early organic reactors. Overall, the design provides a power density of 40 kW/L, while reducing the reactor hull size by 40% compared with a pressurized water reactor while significantly reducing capital plant costs.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 추계학술발표회논문집(1)
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• pp.469-474
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• 1997

To provide tile information ell severe accident progression is very important for advanced or new type of nuclear power plant (NPP) design. A parametric study, therefore was performed to investigate the effect of thermal hydraulic design parameters ell severe accident progression of pressurized water reactors (PWRs), Nine parameters, which are considered important in NPP design or severe accident progression, were selected among the various thermal hydraulic design parameters. The backpropagation neural network (BPN) was used to determine parameters, which might more strongly affect the severe accident progression, among mile parameters. For training. different input patterns were generated by the latin hypercube sampling (LHS) technique and then different target patterns that contain core uncovery time and vessel failure time were obtained for Young Gwang Nuclear (YGN) Units 3&4 using modular accident analysis program (MAAP) 3.0B code. Three different severe accident scenarios, such as two loss of coolant accidents (LOCAs) and station blackout(SBO), were considered in this analysis. Results indicated that design parameters related to refueling water storage tank (RWST), accumulator and steam generator (S/G) have more dominant effects on the progression of severe accidents investigated, compared to tile other six parameters.

• 한국환경과학회지
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• 제16권6호
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• pp.699-706
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• 2007

Many lakes or irrigative reservoirs in Korea are rapidly contaminated due to the ever increasing pollutants. Although lots of treatment processes have been recommended and practiced, economical and technical improvement is currently needed. In this study, contaminated irrigation reservoir was treated using the proposed process which is consisted of fine air bubbles, coagulation and flotation. Fine bubbles, approximate diameter of 3 to $10{\mu}m$, were generated using cavitation in the pressurized tank and polyaluminum chloride was used as coagulants. This fine bubbles, coagulation and flotation effectively controlled the low density algae, for example, Chlorophyll-a was removed more than 97 %. Removal efficiency of COD, SS, T-N and T-P were 80.7%, 94.3%, 64.1 % and 92.4%, respectively. Pollutants released from the sediments was removed more than 80% of organics and 60-70 % of nutrients. Consequently, fine bubbles coagulation and flotation process could be effectively used as an alternative treatment method for the purpose of control of lake water quality.