• Environmental Engineering Research
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• 제19권3호
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• pp.269-274
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• 2014

On-site sanitation systems are typically installed to treat grey and toilet wastewaters in areas without sewer and centralized treatment systems. It is well known that, due to inappropriate design and operation, treatment performance of these systems in developing countries is not satisfactory in the removal of pathogens and organic matters. This research aimed to investigate the hydraulic conditions occurring in some on-site sanitation systems and the effects of hydraulic retention times (HRTs) on the system performance. The experiments were conducted with a laboratory-scale septic tank (40L in size) and an actual septic tank (600L in size), to test the hydraulic conditions by using tracer study with HRTs varying at 12, 24 and 48 hr. The experimental results showed the dispersion numbers to be in the range of 0.017-0.320 and the short-circuit ratios in the range of 0.014-0.031, indicating the reactors having a high level of sort-circuiting and approaching complete-mix conditions. The removal efficiency of $BOD_5$ was found to be 67% and the $k_{30}$ values for $BOD_5$ was $2.04day^{-1}$. A modified complete-mix model based on the relationship between $BOD_5$ removal efficiencies and HRTs was developed and validated with actual-scale septic tank data having a correlation coefficient ($R^2$) of 0.90. Therefore, to better protect our environment and minimizing health risks, new generation toilets should be developed that could minimize short-circuiting and improving treatment performance.

• Environmental Engineering Research
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• 제23권3호
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• pp.294-300
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• 2018

Cometabolism technology was employed to degrade lignin wastewater in Sequencing Batch Biofilm Reactor. Cometabolic system (with glucose and lignin in inflow) and the control group (only lignin in inflow) were established to do a comparative study. In contrast with the control group, the average removal rates of lignin increased by 14.7% and total oarganic carbon increased by 32% in the cometabolic system with glucose as growth substrate, under the condition of 5 mg/L DO, $0.2kgCOD/(m^3{\cdot}d)$ lignin and glucose $1.0kgCOD/(m^3{\cdot}d)$. Functional groups of lignin are degraded effectively in cometabolic system proved by fourier transform infrared spectroscopy and Gas Chromatography-Mass Spectrometer, and the degradation products were amides (mainly including acetamide, N-ethylacetamide and N, N-diethylacetamide), alcohols (mainly including glycerol and ethylene glycol) and acids. Meanwhile, results of Polymerase Chain Reaction-Denaturing Gradient Gel Electrophoresis showed great differences in microbial population richness between cometabolic system and the control group. The Margalef's richness index and Shannon-Wiener's diversity index of microorganism in cometabolic system were 3.075 and 2.61, respectively. The results showed that extra addition of glucose, with a concentration of 943 mg/L, was beneficial to lignin biodegradation in cometabolic system.

• 분석과학
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• 제13권4호
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• pp.474-483
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• 2000

사용후핵연료에 함유되어 있는 핵분열생성물을 분석하기 위하여 여러 원소를 동시에 분석할 수 있고, 분석감도가 커서 시료의 방사능과 폐기물의 양을 감소시킬 수 있는 유도 결합 플라스마 원자방출분광기/차폐 시스템을 구성하였다. 방사성 물질이 직접 접촉되는 플라스마 들뜸원과 시료용액 도입부를 스테인리스 스틸 재질의 글로브박스 내부에 설치하였으며, 고주파 들뜸전원, 분광기, 검출기 그리고 전기, 전자 및 아르곤 가스 공급 제어장치는 외부에 설치하였다. 분석능과 방사선 안전의 관점에서 시스템의 특성을 검증하였으며, 사용후핵연료 용해용액과 원자력발전소의 일차냉각수를 대상으로 핵분열생성물과 방사성 부식생성물 분석에 대한 적용성을 평가한 결과 $0.01-0.1mgL^{-1}$ 농도범위에서 상대표준편차는 5% 이하였다.

• 조명전기설비학회논문지
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• 제15권3호
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• pp.57-66
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• 2001

본 논문에서는 전력계통의 안정도를 향상시키기 위하여 동기 발전기와 정지형 무효전력 보상기예 대한 퍼지-PI 제어기를 설계하기 위한 제어 기법을 설명하였다. 정지형 무효전력 보상기는 고정된 용량의 커패시터와 싸이리스터 제어에 의하여 용량이 가변되는 인덕터가 병렬로 연결된 구조를 가지고 있으며, 시스템 전압을 제어할 뿐만 아니라 동기 발전기의 제동을 개선하기 위해 설계되었다. 본 논문에서 제안한 SVC 계통의 퍼지-PI 제어기의 파라미터는 퍼지 추론 기법에 의해 자동 동조되어진다. 퍼지 추론 기법은 일반적인 기법과는 달리 인간의 경험과 전문가의 지식을 제어 규칙으로 제어 동작을 결정하였다. 그리하여 인간의 추론 과정과 매우 유사한 MMGM을 이용하여 PI 이득의 퍼지 추론 기법을 SVC 계통에 적용하여 설명하였다. 제안된 방법의 강인성을 입증하기 위해 중부하시, 정상부하시 및 경부하시에 초기 전력을 변동시킨 경우에 대하여 시스템의 회전자각, 각속도 편차 특성 및 단자전압의 동특성을 고찰하여 기존의 전력시스템안정화장치보다 응답특성이 우수함을 보였다.

• 한국가스학회지
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• 제6권1호
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• pp.86-91
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• 2002

본 연구에서는 장치가 가지고 있는 신뢰도 데이터와 가격을 고려하여 공정에서 요구하는 신뢰도에 도달할 수 있도록 최적화 분석을 수행하여 어떠한 장치를 선택하는가에 대한 방법을 제시하였다. 이산함수를 이용한 목적함수와 제한 조건을 이용하여 보다 실질적인 최적화 문제를 구성하였다. 재? 반응기를 대상으로 하여 시스템에서 요구하는 신뢰도 목표 값에 도달하기 위해 가격에 따라 다른 고장률을 가지는 장치에 대하여 최적화 분석을 수행하였다. 이러한 최적화 분석을 수행하기 위해 mixed-integer programming(MIP) 방법을 사용하였다. 재? 반응기의 신뢰도 목표값이 $1.65{\times}10^{-04}$일 경우에 최적화 분석 수행결과는 가격과 고장률이 모두 좋은 장치로 분석되었다. 그러나 신뢰도 목표값이 낮을 경우 최적화 분석의 수행결과는 비싼 장치의 선택보다 가격과 신뢰도가 낮은 장치를 선택함으로써 원하는 신뢰도 목표값에 도달할 수 있었다.

• 한국가스학회지
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• 제24권4호
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• pp.32-38
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• 2020

화학반응기에 발생한 화재·폭발 사고사례를 기반으로 화학반응기에 설치되어 있는 예방조치의 문제점을 분석하였다. 화학반응기는 다품종의 화학제품을 생산하며, 반응폭주시 급격히 상승하는 압력을 해소하기 위해 파열판을 설치하고 파열판의 기능을 유지하기 위해 배출물질을 대기로 배출하도록 허용하고 있어 화재·폭발사고가 발생하였다. 이를 개선하기 위한 방안으로 안전건전성수준(SIL3)을 기반으로 한 안전계장시스템(SIS)을 화학반응기의 예방조치로 적용하였다. 화학반응기의 원재료를 적하하는 배관에 긴급차단밸브를 직렬로 2개 설치하여 반응폭주시 긴급차단밸브 2개 중 1개만 작동하여도 원재료 공급을 차단할 수 있도록 하고, 반응응제제 공급배관에는 자동 ON/OFF 밸브를 병렬로 설치하여 반응폭주시 1개의 밸브만 열려도 반응억제제가 투입될 수 있게 하였다.

• Nuclear Engineering and Technology
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• 제48권2호
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• pp.457-469
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• 2016

During the late phase of severe accidents of light water reactors, a porous debris bed is expected to develop on the bottom of the flooded reactor cavity after breakup of the melt in water. The geometrical configuration, i.e., internal and external characteristics, of the debris bed is significant for the adequate assessment of the coolability of the relocated corium. The internal structure of a debris bed was investigated experimentally using the DAVINCI (Debris bed research Apparatus for Validation of the bubble-Induced Natural Convection effect Issue) test facility. Particle sedimentation under the influence of a two-phase natural convection flow due to the decay heat in the debris bed was simulated by dropping various sizes of particles into a water vessel with air bubble injection from the bottom. Settled particles were collected and sieved to obtain the particle mass, size distribution in the radial and axial positions, and the bed porosity and permeability. The experimental results showed that the center part of the particle bed tended to have larger particles than the peripheral area. For the axial distribution, the lower layer had a higher fraction of larger particles. As the sedimentation progressed, the size distribution in the upper layers can shift to larger sizes because of the higher vapor generation rate and stronger flow intensity.

• Nuclear Engineering and Technology
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• 제43권6호
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• pp.583-592
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• 2011

The radiological characteristics for waste classification were assessed for neutron-activated decommissioning wastes from a CANDU reactor. The MCNP/ORIGEN2 code system was used for the source term analysis. The neutron flux and activation cross-section library for each structural component generated by MCNP simulation were used in the radionuclide buildup calculation in ORIGEN2. The specific activities of the relevant radionuclides in the activated metal waste were compared with the specified limits of the specific activities listed in the Korean standard and 10 CFR 61. The time-average full-core model of Wolsong Unit 1 was used as the neutron source for activation of in-core and ex-core structural components. The approximated levels of the neutron flux and cross-section, irradiated fuel composition, and a geometry simplification revealing good reliability in a previous study were used in the source term calculation as well. The results revealed the radioactivity, decay heat, hazard index, mass, and solid volume for the activated decommissioning waste to be $1.04{\times}10^{16}$ Bq, $2.09{\times}10^3$ W, $5.31{\times}10^{14}\;m^3$-water, $4.69{\times}10^5$ kg, and $7.38{\times}10^1\;m^3$, respectively. According to both Korean and US standards, the activated waste of the pressure tubes, calandria tubes, reactivity devices, and reactivity device supporters was greater than Class C, which should be disposed of in a deep geological disposal repository, whereas the side structural components were classified as low- and intermediate-level waste, which can be disposed of in a land disposal repository. Finally, this study confirmed that, regardless of the cooling time of the waste, 15% of the decommissioning waste cannot be disposed of in a land disposal repository. It is expected that the source terms and waste classification evaluated through this study can be widely used to establish a decommissioning/disposal strategy and fuel cycle analysis for CANDU reactors.

• Nuclear Engineering and Technology
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• 제50권2호
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• pp.223-228
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• 2018

AREVA NP (Courbevoie, Paris, France) is actively developing several enhanced accident-tolerant fuels cladding concepts ranging from near-term evolutionary (Cr-coated zirconium alloy cladding) to long-term revolutionary (SiC/SiC composite cladding) solutions, relying on its worldwide teams and partnerships, with programs and irradiations planned both in Europe and the United States. The most advanced and mature solution is a dense, adherent chromium coating on zirconium alloy cladding, which was initially developed along with the CEA and EDF in the French joint nuclear R&D program. The evaluation of the out-of-pile behavior of the Cr-coated cladding showed excellent results, suggesting enhanced reliability, enhanced operational flexibility, and improved economics in normal operating conditions. For example, because chromium is harder than zirconium, the Cr coating provides the cladding with a significantly improved wear resistance. Furthermore, Cr-coated samples exhibit extremely low corrosion kinetics in autoclave and prevents accelerated corrosion in harsh environments such as in water with 70 ppm Li leading to improved operational flexibility. Finally, AREVA NP has fabricated a physical vapor deposition prototype machine to coat full-length cladding tubes. This machine will be used for the manufacturing of full-length lead test rods in commercial reactors by 2019.

• Nuclear Engineering and Technology
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• 제48권6호
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• pp.1321-1329
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• 2016

To get an insight into the operating characteristics of the passive residual heat removal system of molten salt reactors, a two-phase natural circulation test facility was constructed. The system consists of a boiling loop absorbing the heat from the drain tank, a condensing loop consuming the heat, and a steam drum. A steady-state experiment was carried out, in which the thimble temperature ranged from $450^{\circ}C$ to $700^{\circ}C$ and the system pressure was controlled at levels below 150 kPa. When reaching a steady state, the system was operated under saturated conditions. Some important parameters, including heat power, system resistance, and water level in the steam drum and water tank were investigated. The experimental results showed that the natural circulation system is feasible in removing the decay heat, even though some fluctuations may occur in the operation. The uneven temperature distribution in the water tank may be inevitable because convection occurs on the outside of the condensing tube besides boiling with decreasing the decay power. The instabilities in the natural circulation loop are sensitive to heat flux and system resistance rather than the water level in the steam drum and water tank. RELAP5 code shows reasonable results compared with experimental data.