• Nuclear Engineering and Technology
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• 제52권9호
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• pp.2107-2118
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• 2020

The nuclear reactor coupled with supercritical carbon dioxide (S-CO₂) Brayton cycle has good prospects in generation IV reactors. Turbomachineries (turbine and compressor) are important work equipment in circulatory system, whose performances are critical to the efficiency of the energy conversion system. However, the sharp variations of S-CO₂ thermophysical properties make turbomachinery performances more complex than that of traditional working fluids. Meanwhile, almost no systematic analysis has considered the effects of turbomachinery efficiency under different conditions. In this paper, an in-house code was developed to realize the geometric design and performance prediction of S-CO₂ turbomachinery, and was coupled with systematic code for Brayton cycle characteristics analysis. The models and methodology adopted in calculation code were validated by experimental data. The effects of recompressed fraction, pressure and temperature on S-CO₂ recompression Brayton cycle were studied based on detailed design of turbomachinery. The results demonstrate that the recompressed fraction affects the turbomachinery characteristic by changing the mass flow and effects the system performance eventually. By contrast, the turbomachinery efficiency is insensitive to variation in pressure and temperature due to almost constant mass flow. In addition, the S-CO₂ thermophysical properties and the position of minimum temperature difference are significant influential factors of cyclic performance.

• 정보처리학회논문지:소프트웨어 및 데이터공학
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• 제3권2호
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• pp.65-72
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• 2014

변경 결합도는 두 요소들 사이의 향후 변경 연관성을 알려준다. 만약, 소스 파일들이 자주 함께 변경된다면, 그 소스 파일들의 변경 결합도는 높다고 볼 수 있으며, 나중에 다시 함께 변경될 확률이 높다. 일반적으로 소스 파일들 사이의 변경 결합도는 공통 변경 횟수에 기반하여 정의되었다. 그런데 연관성이 낮은 변경들이 일괄적으로 함께 커밋되는 경우, 즉 뒤얽힌 변경(tangled change)과 같은 경우들이 빈번히 발생한다. 따라서 함께 변경된 횟수만으로 소스 파일의 변경 결합도를 결정하는 것은 한계가 있다. 본 논문에서는 기존의 방법을 보완하기 위해, 소스 파일의 변경 시간뿐 아니라 소스 코드 변경 유형의 유사성을 함께 고려하는 것을 제안하였다. 이를 위하여, 우선 추출된 변경 유형 정보를 이용하여 변경 유형 빈도 벡터를 정의하고, 다음에 코사인 유사도 측정을 통해서 각 소스 파일 버전에서 적용된 코드 변경 유사성을 계산한다. 이후 Eclipse 프로젝트인 JDT와 CDT에 대한 사례 연구를 통해 제안된 방법의 효용성을 보였다.

• 시스템엔지니어링학술지
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• 제18권2호
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• pp.58-74
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• 2022

Deterministic accident analysis plays a central role in the nuclear power plant (NPP) safety evaluation and licensing process. Traditionally the conservative approach opted for the point kinetics model, expressing the reactor core parameters in the form of reactivity and power tables. However, with the current advances in computational power, high fidelity multi-physics simulations using real-time code coupling, can provide more detailed core behavior and hence more realistic plant's response. This is particularly relevant for transients where the core is undergoing reactivity anomalies and uneven power distributions with strong feedback mechanisms, such as reactivity initiated accidents (RIAs). This work addresses a RIA, specifically a control element assembly (CEA) withdrawal at power, using the multi-physics analysis tool RELAP5/MOD 3.4/3DKIN. The thermal-hydraulics (TH) code, RELAP5, is internally coupled with the nodal kinetics (NK) code, 3DKIN, and both codes exchange relevant data to model the nuclear power plant (NPP) response as the CEA is withdrawn from the core. The coupled model is more representative of the complex interactions between the thermal-hydraulics and neutronics; therefore the results obtained using a multi-physics simulation provide a larger safety margin and hence more operational flexibility compared to those of the point kinetics model reported in the safety analysis report for APR1400. The systems engineering approach is used to guide the development of the work ensuring a systematic and more efficient execution.

• 한국정보통신학회:학술대회논문집
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• 한국정보통신학회 2022년도 춘계학술대회
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• pp.519-521
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• 2022

UAV의 장시간 운용을 위한 다양한 종류의 전력공급 방식과 연료 기술이 등장하고 있다. 현재 시중에 유통되고 있는 50cm 안팎의 회전익 UAV의 경우 주로 재충전이 가능한 2차 전지가 주로 탑재되고 있으며, 완충 시 정지비행(hovering) 기준 보통 30분 내외의 비행시간을 갖는다. 배터리의 용량과 무게는 UAV의 운영시간과 밀접한 관계가 있고 결국 응용의 다양성에 영향을 준다. 운영시간의 다변화를 위한 방안으로 무선충전기술을 UAV에 적용하는 연구가 활발히 진행되고 있으며, 방식에 따라 원거리(decoupled) 충전과 근거리(coupled) 충전 방식으로 나뉜다. 본 연구에서는 근거리 충전 방식 중 하나인 자기유도기(무선충전기)를 활용할 때, 충전시스템에 정밀하게 안착(착륙)하여 UAV가 효과적으로 재충전될 수 있도록 QR 코드를 적용하고 이를 인식하고 3D 위치 측위를 통한 UAV의 위치보정 방안을 제안한다.

• 화약ㆍ발파
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• 제34권2호
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• pp.31-38
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• 2016

유체 동역학 코드는 고속 충돌을 모델링하는 수치해석 툴로서 재료가 유체처럼 거동한다고 가정하며, 화약을 이용한 암반발파와 같은 충돌 문제를 푸는 데 광범위하게 사용된다. 암반발파를 현실적으로 모사하기 위해서는 화약을 수치해석적으로 모델링할 필요가 있으며, 이를 통해 암반과 화약의 상호작용 문제를 완전 연계된 방식으로 풀 수 있다. 화약을 수치 모델링하기 위해서는 특정 물리적 조건에서 재료의 상태를 나타내는 상태 방정식이 수립되어야 한다. 본 고에서는 발파 과정을 수치 모델링하기 위한 유체 동역학 코드, 화약의 상태 방정식과 관련 매개변수의 결정방법에 대해 소개하였다.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4460-4473
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• 2022

The behaviour of the fission gas plays an important role in the fuel rod performance. In a previous work, we presented a physics-based model describing intra- and inter-granular behaviour of radioactive fission gas. The model was implemented in SCIANTIX, a mesoscale module for fission gas behaviour, and assessed against the CONTACT 1 irradiation experiment. In this work, we present the multi-scale coupling between the TRANSURANUS fuel performance code and SCIANTIX, used as mechanistic module for stable and radioactive fission gas behaviour. We exploit the coupled code version to reproduce two integral irradiation experiments involving standard fuel rod segments in steady-state operation (CONTACT 1) and during successive power transients (HATAC C2). The simulation results demonstrate the predictive capabilities of the code coupling and contribute to the integral validation of the models implemented in SCIANTIX.

• Advances in Energy Research
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• 제5권2호
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• pp.91-105
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• 2017

Thermal hydraulic (TH) analysis of nuclear power reactors is utmost important. In this way, the numerical codes that preparing TH data in reactor core are essential. In this paper, a subchannel analysis of a Russian pressurized water reactor (WWER1000) core with enhanced numerical code is carried out. For this, in fluid domain, the mass, axial and lateral momentum and energy conservation equations for desired control volume are solved, numerically. In the solid domain, the cylindrical heat transfer equation for calculation of radial temperature profile in fuel, gap and clad with finite difference and finite element solvers are considered. The dependence of material properties to fuel burnup with Calza-Bini fuel-gap model is implemented. This model is coupled with Isotope Generation and Depletion Code (ORIGEN2.1). The possibility of central hole consideration in fuel pellet is another advantage of this work. In addition, subchannel to subchannel and subchannel to rod connection data in hexagonal fuel assembly geometry could be prepared, automatically. For a demonstration of code capability, the steady state TH analysis of a the WWER1000 core is compromised with Thermal-hydraulic analysis code (COBRA-EN). By thermal hydraulic parameters averaging Fuel Assembly-to-Fuel Assembly method, the one sixth (symmetry) of the Boushehr Nuclear Power Plant (BNPP) core with regular subchannels are modeled. Comparison between the results of the work and COBRA-EN demonstrates some advantages of the presented code. Using the code the thermal modeling of the fuel rods with considering the fission gas generation would be possible. In addition, this code is compatible with neutronic codes for coupling. This method is faster and more accurate for symmetrical simulation of the core with acceptable results.

• 한국항공우주학회지
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• 제32권6호
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• pp.34-48
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• 2004

본 연구에서는 대형 구조물의 최적설계에서 문제되는 많은 계산시간과 컴퓨터의 계산능력을 최소화할 수 있도록 부분구조합성법의 하나인 구속모드법을 이용한 연성하중해석 모델 및 모달과도해석을 포함한 최적화 절차를 제시하였다. 제안된 방법의 수치모사를 위한 프로그램을 개발하여 위성체 주요 구조부재인 플랫폼에 대한 최적화를 수행함으로써 그 타당성을 검증하였다. 제안된 기법을 통해 초기설계 단계에서 정확성을 유지하면서 계산시간을 단축할 수 있었고 위성체 구조부재에 대한 최적화를 수행하여 각각의 구조부재에 대한 특성을 파악함으로써 설계 활용방안을 제시하였다.

• Structural Engineering and Mechanics
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• 제21권4호
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• pp.437-450
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• 2005

In this study, a complete analysis of soil-structure interaction problems is presented which includes a modelling of the near surrounding of the building (near-field) and a special description of the wave propagation process in larger distances (far-field). In order to reduce the computational effort which can be very high for time domain analysis of wave propagation problems, a special approach based on similarity transformation of the infinite domain on the near-field/far-field interface is applied for the wave radiation of the far-field. The near-field is discretised with standard Finite Elements, which also allows to introduce non-linear material behaviour. In this paper, a new approach to calculate the involved convolution integrals is presented. This approximation in time leads to a dramatically reduced computational effort for long simulation times, while the accuracy of the method is not affected. Finally, some benchmark examples are presented, which are compared to a coupled Finite Element/Boundary Element approach. The results are in excellent agreement with those of the coupled Finite Element/Boundary Element procedure, while the accuracy is not reduced. Furthermore, the presented approach is easy to incorporate in any Finite Element code, so the practical relevance is high.

• Coupled systems mechanics
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• 제2권1호
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• pp.85-110
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• 2013

Generally, mass concrete structural behavior is governed by the strain components. However, relevant guidelines in dam engineering evaluate the structural behavior of concrete dams using stress-based criteria. In the present study, strain-based criteria are proposed for the first time in a professional manner and their applicability in seismic failure evaluation of an arch dam are investigated. Numerical model of the dam is provided using NSAD-DRI finite element code and the foundation is modeled to be massed using infinite elements at its far-end boundaries. The coupled dam-reservoir-foundation system is solved in Lagrangian-Eulerian domain using Newmark-${\beta}$ time integration method. Seismic performance of the dam is investigated using parameters such as the demand-capacity ratio, the cumulative inelastic duration and the extension of the overstressed/overstrained areas. Real crack profile of the dam based on the damage mechanics approach is compared with those obtained from stress-based and strain-based approaches. It is found that using stress-based criteria leads to conservative results for arch action while seismic safety evaluation using the proposed strain-based criteria leads to conservative cantilever action.