• Nuclear Engineering and Technology
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• 제50권2호
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• pp.306-312
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• 2018

There is an increasing need in the United States and around the world to move used nuclear fuel from wet storage in fuel pools to dry storage in casks stored at independent spent fuel storage installations or interim storage sites. Under normal conditions, the Nuclear Regulatory Commission limits cladding temperature to $400^{\circ}C$ for high-burnup (>45 GWd/mtU) fuel, with higher temperatures allowed for low-burnup fuel. An analysis was conducted with FRAPCON-4.0 on three modern fuel designs with three representative used nuclear fuel storage temperature profiles that peaked at $400^{\circ}C$. Results were representative of the majority of US light water reactor fuel. They conservatively showed that hoop stress remains below 90 MPa at the licensing temperature limit. Results also show that the limiting case for hoop stress may not be at the highest rod internal pressure in all cases but will be related to the axial temperature and oxidation profiles of the rods at the end of life and in storage.

• Nuclear Engineering and Technology
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• 제50권7호
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• pp.1190-1197
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• 2018

Analysis of the GRSW-A model coupled into the FALCON code is extended by simulation of central void formation in fuel pellets due to high-temperature fuel restructuring. The extended calculation is verified against published, well-known experimental data. Good agreement with the data for a central void diameter in pellets of the rod irradiated in an Experimental Breeder Reactor is shown. The new calculation methodology is employed in comparative analysis of modern BWR fuel behavior under assumed high-power operation. The initial fuel porosity is shown to have a major effect on the predicted central void diameter during the operation in question. Discernible effects of a central void on peak fuel temperature and Pellet-Cladding Mechanical Interaction (PCMI) during a simulated power ramp are shown. A mitigating effect on PCMI is largely attributed to the additional free volume in the pellets into which the fuel can creep due to internal compressive stresses during a power ramp.

• 한국농공학회논문집
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• 제48권3호
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• pp.63-71
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• 2006

A downdraft gasifier was made of stainless steel for biomass gasification. Internal reactor had a 300 mm diameter and 8 air intakes. Three thermocouples were installed to measure the temperature inside the reactor. Three different biomass fuels were provided in the experiments to find out the effects of fuel conditions on gasification processes; charcoals, woodchips, and mixture of woodchip and charcoals. Two different experiments were conducted fer charcoal experiments, small and larger sizes of charcoal fuels. It took about 10 minutes after ignition to generate combustible producer gas when charcoal was f9d, but 20 or more minutes for woodchips. When the gasification was stabilized, the highest temperature was observed just below the combustion zone. The air flow rate for woodchip experiment was provided at 25% of a stoichiometric requirement of combustion, which was within the range of typical air flow rate fer woody biomass gasification. Carbon monoxide concentrations were also within the values reported in the previous studies, ranging 20 to 30% depending on fuel types. It could be seen that fuel size and heating value were very important parameters in biomass gasification. These parameters should be taken into account in operating and designing biomass gasifiers.

• Corrosion Science and Technology
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• 제12권2호
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• pp.102-112
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• 2013

A very high-temperature gas reactor (VHTR) is one of the next generation nuclear reactors owing to its safety, high energy efficiency, and proliferation-resistance. Heat is transferred from the primary helium loop to the secondary helium loop through an intermediate heat exchanger (IHX). Under VHTR environment Alloy 617 is being considered a candidate Ni-based superalloy for the IHX of a VHTR, owing to its good creep resistance, phase stability and corrosion resistance at high temperature. In this study, high-temperature corrosion tests were carried out at 850 - $950^{\circ}C$ in air and impure helium environments. Alloy 617 specimens showed a parabolic oxidation behavior for all temperatures and environments. The activation energy for oxidation was 154 kJ/mol in helium environment, and 261 kJ/mol in an air environment. The scanning electron microscope (SEM) and energy-dispersive x-ray spectroscopy (EDS) results revealed that there were a Cr-rich surface oxide layer, Al-rich internal oxides and depletion of grain boundary carbide after corrosion test. The thickness and depths of degraded layers also showed a parabolic relationship with the time. A corrosion rate of $950^{\circ}C$ in impure helium was higher than that in an air environment, caused by difference in the outer oxide morphology.

• 한국축산시설환경학회지
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• 제21권1호
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• pp.21-28
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• 2015

We studied the possibility on the application of the Thermophilic Aerobic Oxidation (TAO) process to anaerobic digestate stabilization. In treating digestate with TAO reactor the internal temperature of the reactor was increasing higher and $51^{\circ}C$ and over was maintained after 6 days on. The physiochemical compositions of liquids increased from pH 8.1 to 9.8 and EC decreased from 29.8 to 12.0 mS/cm in treating process of digestate with TAO reactor. CODcr decreased from 22,654 to 18,843 mg/L, showed about 16.82% of remove efficiency. TN and $NH_4-N$ decreased from 4,813 to 1,733 mg/L, from 3,815 to 812 mg/L respectively, which showed about 64.0% and 78.7% of removal efficiency respectively.

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2009년도 춘계학술대회 논문집
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• pp.731-734
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• 2009

KIER has been developed a compact and highly efficient fuel processor which is one of the key component of the residential PEM fuel cells system. The fuel processor uses methane steam reforming to convert natural gas to a mixture of water, hydrogen, carbon dioxide, carbon monoxide and unreacted methane. Then carbon monoxide is converted to carbon dioxide in water-gas-shift reactor and preferential oxidation reactor. A start-up time of the fuel processor is about 1h and CO concentration among the final product is maintained less than 5 vol. ppm. To achieve high thermal efficiency of 80% on a LHV basis, an optimal thermal network was designed. Internal heat exchange of the fuel processor is so efficient that the temperature of the reformed gas and the flue gas at the exit of the fuel processor remains less than $100^{\circ}C$. A compact design considering a mixing and distribution of the feed was applied to reduce the reactor volume. The current volume of the fuel processor is 17L with insulation.

• 한국초전도ㆍ저온공학회논문지
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• 제15권4호
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• pp.26-29
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• 2013

Smart fault current controller (SFCC) proposed in our previous work consists of a power converter, a high temperature superconducting (HTS) DC reactor, thyristors, and a control unit [1]. SFCC can limit and control the current by adjusting firing angles of thyristors when a fault occurs. SFCC has complex structure because the HTS DC reactor generates the loss under AC. To use the DC reactor under AC, rectifier that consists of four thyristors is needed and it increases internal resistance of SFCC. For this reason, authors propose a hybrid type superconducting fault current limiter (SFCL). The hybrid type SFCL proposed in this paper consists of a non-inductive superconducting coil and two thyristors. To verify the feasibility of the proposed hybrid type SFCL, simulations about the interaction of the superconducting coil and thyristors are conducted when fault current flows in the superconducting coil. Authors expect that the hybrid type SFCL can control the magnitude of the fault current by adjusting the firing angles of thyristors after the superconducting coil limits the fault current at first peak.

• 대한기계학회논문집A
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• 제25권4호
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• pp.756-763
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• 2001

In the process of integrity evaluation for nuclear power plant components, a series of fracture mechanics evaluation on surface cracks in reactor pressure vessel(RPV) must be conducted. These fracture mechanics evaluation are based on stress intensity factor, K. However, under pressurized thermal shock(PTS) conditions, the combination of thermal and mechanical stress by steep temperature gradient and internal pressure causes considerably high tensile stress at the inside of RPV wall. Besides, the internal pressure during the normal operation produces high tensile stress at the RPV wall. As a result, cracks on inner surface of RPVs may experience elastic-plastic behavior which can be explained with J-integral. In such a case, however, J-integral may possibly lose its validity due to constraint effect. In this paper, in order to verify the suitability of J-integral, tow dimensional finite element analyses were applied for various surface cracks. A total of 18 crack geometries were analyzed, and $\Omega$ stresses were obtained by comparing resulting HRR stress distribution with corresponding actual stress distributions. In conclusion, HRR stress fields were found to overestimate the actual crack-tip stress field due to constraint effect.

• 방사성폐기물학회지
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• 제18권2_spc호
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• pp.327-336
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• 2020

HANARO (High-flux Advanced Neutron Application Reactor)는 우라늄의 핵분열 연쇄반응에서 생성된 중성자를 이용하여 다양한 연구개발을 수행하는 열출력 30 MW 규모의 연구용 원자로이다. 탈기탱크는 HANARO의 부속시설에 설치되어 있다. 탈기탱크는 내부환경요인으로 인해 기체오염물질을 발생시킨다. 탈기탱크는 기체오염물질을 허용 가능한 수준 이하로 유지하기위해 필요하며 기체시료채취판넬의 분석기에 의해 모니터링 된다. 응축수가 발생하여 기체시료채취판넬의 분석기 내부로 유입된다면, 분석기의 측정 챔버 내부에 부식이 발생하여 고장을 야기한다. 응축수의 생성 원인은 탈기탱크에 존재하는 기체가 분석기로 유입되는 과정에서 탈기탱크와 분석기사이 온도 차이다. 응축수 생성을 억제하고 계통 내부에 생성된 응축수를 효율적으로 제거하기 위해 탈기탱크와 기체시료채취판넬 사이에 히팅시스템이 설치되었다. 이 연구에서 우리는 히팅시스템의 효율성을 알고자 한다. 또한 Wall Condensation Model을 이용하여 유체 입구온도, 외부온도 및 히팅 케이블 설정온도 변화에 따른 파이프 온도와 평균응축량의 변화를 모델링하였다.

• Korean Chemical Engineering Research
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• 제53권6호
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• pp.818-823
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• 2015

본 연구에서는 전산유체역학(CFD)을 이용하여 마이크로채널 내부의 Fischer-Tropsch(FT) 반응을 모사하였고, 나아가 반응채널의 너비와 높이, 냉각채널과의 거리 그리고 채널 사이 간격을 변수로 두고 채널 내부 온도에 대해 민감도 분석을 수행하였다. 마이크로채널 반응기는 채널 간의 열교환을 고려하기 위한 5개의 반응채널과 냉각채널을 대신한 냉각면으로 이루어져 있으며 채널의 높이와 너비를 포함한 변수들의 길이는 0.5 mm ~ 5.0 mm 범위에서 설정하였다. 반응물로는 $H_2$와 CO의 혼합기체($H_2/CO$ molar ratio=2)를 사용하였으며 반응기의 운전 조건은 $GHSV=10000h^{-1}$, 압력 20 bar와 온도 483 K($210^{\circ}C$)이다. 민감도 분석의 결과로 반응채널 내부의 최대 온도는 채널의 높이에 비례하며 너비에 대해서는 특정 길이 이상에서 영향을 받지 않는 것을 확인하였으며 이 중에 냉각채널과의 거리와 채널 사이 간격은 채널 내부 온도에 거의 영향을 미치지 않았다. 따라서 채널 레이아웃에서 반응채널의 높이는 짧을수록(약 2 mm 이하), 너비는 길수록(약 4 mm 이상) 열제거뿐만 아니라 생산량 측면에서 이득을 얻을 수 있었다.