• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2678-2686
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• 2023

This work demonstrates the results of full-scale numerical experiments of a hybrid thorium-containing fuel plant operating in a state close to critical due to a controlled source of D-T neutrons. The proposed facility represented a level of generated power (~10-100 MW_t) in a small pilot. In this work, the simulation of the D-T neutron plasma source operation in conjunction with the facility blanket was performed. The fission of fuel nuclei and the formation of spatial-energy release were studied in this simulation, in pulsed and stationary modes of the facility operation. The optimization results of neutronic and fluid dynamics studies to level the emerging offsets of the radial energy formed in the volume of the facility multiplying part due to the pulsed operation of the D-T neutron plasma source were presented. The results will be useful in improving the power control-based subcriticality monitoring method in coupled systems of the "pulsed neutron source-subcritical fuel assembly" type.

• Elastomers and Composites
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• 제58권3호
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• pp.121-127
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• 2023

The effect of diisocyanate type on the decomposition temperature of polyurethane (PU) hydrolysis was investigated in a subcritical water medium up to 250℃. PU samples were prepared using different types of diisocyanate: two aromatic diisocyanates (4,4'-methylene diphenyl diisocyanate (MDI) and methyl phenylene diisocyanate (TDI)), one unbranched aliphatic diisocyanate (hexamethylene diisocyanate (HDI)), and two cyclic aliphatic diisocyanates (4,4'-methylene dicyclohexyl diisocyanate (H₁₂MDI) and isophorone diisocyanate (IPDI)). The pressure had no effect on hydrolysis in the range of 70-250 bar. The decomposition temperature of the PU samples increased in the following order: TDI-PU (199℃) < H₁₂MDI ≈ IPDI ≈ HDI (218-220℃) < MDI-PU (237℃). This order of increase in temperature is related to the electron-donating ability of the group to connected to the nitrogen of the urethane unit. When the temperature of the (PU + water) mixture reached the specific decomposition temperature, the PU samples hydrolyzed completely within 5 min into primary amine and 1,4-butanediol. The hydrolysis products from MDI-PU and H₁₂MDI-PU were separated into a liquid phase rich in (BD + water) and a solid low phase rich in amine, whereas the products from TDI-, IPDI-, and HDI-PU existed in a single aqueous phase.

• 대한토목학회논문집
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• 제43권6호
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• pp.749-762
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• 2023

천수 방정식 흐름률 계산에 근사 Riemann 해법을 채택한 수심 적분 모형을 도수 실험에 적용하였다. 도수 때문에 단일 수로에서 서로 다른 흐름 양상이 동시에 나타나므로 흐름 저항에 대해 수심이나 유속에 무관한 Manning 조도 계수보다는 흐름 조건을 반영할 수 있는 Weisbach 저항 계수를 채택하였다. 모의 결과는 실험 결과에 잘 부합되었으며, Weisbach 계수로부터 환산한 Manning 계수는 사류 구간과 상류 구간에서 각 각 적절하게 설정되고 있음을 확인하였다. 도수 실험과 비교에서 정수압 가정에 기반한 천수 방정식의 한계가 드러나 비정수압 천수 흐름 모형 도입의 필요성이 높아졌다.

• Nuclear Engineering and Technology
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• 제56권3호
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• pp.793-802
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• 2024

In the framework of the European project SAMOSAFER, this numerical study focuses on some thermal aspects of the Emergency Draining Tank (EDT) located underneath the core of a Molten Salt Reactor. In case of an emergency, this tank passively receives the liquid fuel salt and is designed to ensure a subcritical state. An important requirement is that the fuel does not overheat to maintain the EDT Hastelloy container integrity. The present EDT is based upon a group of hexagonal cooling assemblies arranged in a hexagonal grid and cooled down thanks to conduction through the inert salt layer up to an air flow in charge of removing the heat. This numerical thermal study relies on a conjugated heat transfer analysis coupling a Finite Element solid thermal code (SYRTHES) and two instances of a Finite Volume CFD codes (Code_Saturne). Calculations on an initial design suggest that a simple center airpipe flow is likely to not sufficiently cool the device. Alternative solutions have been evaluated. Introduction of fins to enhance the heat transfer do not bring a noticeable improvement regarding maximum temperature reached. However, a solution in which the central pipe air flow is replaced by several cooling channels located closer to the fuel is investigated and suggests a better cooling.

• 대한기계학회논문집B
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• 제41권5호
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• pp.353-363
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• 2017

부하변동과 외란에 따른 관류보일러 물-증기 계통의 동적 거동을 물리적 모델링 접근방법으로 모사하였다. 본 논문에서는 수관의 질량, 에너지와 운동량 방정식을 고려한 아임계 영역의 동적 모사를 보고한다. 500MWe 급의 절탄기, 증발기와 과열기로 이루어진 단순한 보일러 시스템을 가정하였고, 증발기 모델링은 참고문헌 데이터와 검증을 진행 하였다. 이 시스템에 대하여 외란에 따른 정량적 응답특성을 살펴보았다. 또한, 수연비(증기량과 연료의 유량비)가 설계조건과 크게 다른 탈 설계 운전 사례에 대한 보일러 시스템의 동적 응답평가를 진행 하였다. 그 결과를 통해 적절한 수연비의 제어와 재순환 시스템과 분무 감온기 설계의 중요성이 재확인 되었다.

• 한국수자원학회논문집
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• 제38권4호
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• pp.259-269
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• 2005

본 연구에서는 제방의 월류 및 붕괴에 따른 홍수파가 제내지로 전파되는 경우의 물리적인 특성을 고려하여 하천에 대한 홍수류 해석은 Preissmann 기법을 적용하였으며, 제내지에서의 범람해석을 위해 2차원 모형을 적용하여 해석할 수 있도록 구성하였고, 이들 두 모형이 상호 작용할 수 있는 하도-제내지 연결부 수치해석 모형을 개발하였다. 본 모형에서는 잠수효과의 해석을 위한 관련방정식을 도입하여 제내지에서의 수위 상승에 따른 하천으로부터의 월류량을 정확하게 계산할 수 있도록 구성하였다. 본 연구모형을 2002년 9월 낙동강 유역 실제 제방붕괴의 경우에 적용하여 제내지에서의 2차원 범람양상을 유속분포와 범람수심에 대해서 주요 시간대별로 계산하여 도시하였으며 모의결과는 당시의 실측자료 및 홍수범람범위와 잘 일치되는 것으로 나타났다.

• 한국수자원학회논문집
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• 제36권5호
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• pp.777-785
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• 2003

본 연구에서는 비구조격자 좌표계상에서 천수방정식 해석을 위한 수치모형을 개발하였다. Fractional step method를 이용하여 이차원의 천수방정식을 두개의 일차원 문제로 분리하여 계산 효율이 우수한 수치연산을 수행하였다. 분리된 일차원 문제는 이차정확도의 TVD 기법을 이용하여 해석하였다. TVD 기법은 HLLC 기법을 이용하여 Riemann 해를 구한후 WAF 기법을 기반으로 이용하였으며 WAF 흐름율 제한자를 이용하여 이차정확도 문제에 수반되는 비물리적인 수치진동을 제어하였다. 개발된 모형을 다양한 문제에 적용한 결과, 해석해와 계산된 결과가 매우 잘 일치하였으며, 본 모형이 불연속해나 상류사류의 혼합흐름 및 이동경계 문제 등에 이용될 수 있음을 보였다.

• 대한기계학회논문집B
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• 제23권1호
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• pp.140-148
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• 1999

Experiments on flame spread in an one-dimensional droplet array up to supercritical pressures of fuel droplet have been conducted In normal gravity and microgravity. Evaporating process around unburnt droplet is observed through high-speed Schlieren and direct visualizations in detail, and flame spread rate is measured using high speed chemiluminescence images of OH radical. Flame spread behaviors are categorized into three: flame spread is continuous at low pressures and is regularly intermittent up to the critical pressure of fuel. flame spread is irregularly intermittent and zig-zag at supercritical pressures of fuel. At atmospheric pressure, the limit droplet spacing and the droplet spacing of maximum flame spread rate in microgravity are larger than those in normal gravity. In microgravity, the flame spread rate with the increase of ambient pressure decreases initially, takes a minimum, and then decreases after taking maximum. This is so because the flame spread time is determined by competing effects between the increased transfer time of thermal boundary layer due to reduced flame diameter and the reduced ignition delay time in terms of the increase of ambient pressure. Consequently, it is found that flame spread behaviors in microgravity are considerably different from those in normal gravity due to the absence of natural convection.

• Nuclear Engineering and Technology
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• 제48권3호
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• pp.785-794
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• 2016

The Argonne National Laboratory of the United States and the Kharkov Institute of Physics and Technology of the Ukraine have been collaborating on the design, development and construction of a neutron source facility at Kharkov Institute of Physics and Technology utilizing an electron-accelerator-driven subcritical assembly. The electron beam power is 100 kW using 100-MeV electrons. The facility was designed to perform basic and applied nuclear research, produce medical isotopes, and train nuclear specialists. The biological shield of the accelerator building was designed to reduce the biological dose to less than 5.0e-03 mSv/h during operation. The main source of the biological dose for the accelerator building is the photons and neutrons generated from different interactions of leaked electrons from the electron gun and the accelerator sections with the surrounding components and materials. The Monte Carlo N-particle extended code (MCNPX) was used for the shielding calculations because of its capability to perform electron-, photon-, and neutron-coupled transport simulations. The photon dose was tallied using the MCNPX calculation, starting with the leaked electrons. However, it is difficult to accurately tally the neutron dose directly from the leaked electrons. The neutron yield per electron from the interactions with the surrounding components is very small, ~0.01 neutron for 100-MeV electron and even smaller for lower-energy electrons. This causes difficulties for the Monte Carlo analyses and consumes tremendous computation resources for tallying the neutron dose outside the shield boundary with an acceptable accuracy. To avoid these difficulties, the SOURCE and TALLYX user subroutines of MCNPX were utilized for this study. The generated neutrons were banked, together with all related parameters, for a subsequent MCNPX calculation to obtain the neutron dose. The weight windows variance reduction technique was also utilized for both neutron and photon dose calculations. Two shielding materials, heavy concrete and ordinary concrete, were considered for the shield design. The main goal is to maintain the total dose outside the shield boundary less than 5.0e-03 mSv/h during operation. The shield configuration and parameters of the accelerator building were determined and are presented in this paper.

• 플랜트 저널
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• 제4권3호
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• pp.60-65
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• 2008

Power plant industry has been developed at high-capacity, high-technology, and innovation. Steam turbine became the most useful equipment that dominate more than 50% of all the world electricity production. And developed new materials of the turbine blade and extended length of the turbine last blade brought reform in steam turbine performance upgrade. In this paper, when do partial load driving in high-capacity steam turbine, optimum driving method found whether there is something. In operating steam turbine, there is a lot of loss from secondary wake and throttle of the 1st stage nozzle by the biggest leading factor that load fluctuation affects in high-pressure steam turbine performance. Effect of internal efficiency by 1 stage nozzle is the biggest here, but here fluid flow and flow analysis were not yet examined closely definitely. So, Analyzed design data and acceptance performance test result to applying subcritical pressure drum type 560 MW, supercritical-pressure once through type 500 MW, and 800 MW steam turbines actually. In conclusion, at partial load driving, partial arc admission(PAA) is more efficient than full arc admission(FAA) efficiency. This is judged by because increase being proportional with gross energy of stream that is pressure - available energy if pressure of stream that is flowed in to the turbine increases, available energy becomes maximum and turbine efficiency improves. Therefore, turbine performance is that preview that first stage performance fell if decline is serious in partial load because first stage performance changes according to load.