• Journal of Energy Engineering
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• v.27 no.2
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• pp.32-48
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• 2018

Monitoring of energy use should be a priority in order to efficiently manage building energy use. Energy use in buildings can be managed by dividing them into energy sources, uses, and ZONE. By energy source, electricity, gas, fuel, and district heating are supplied to run the building's facilities. The purpose can be divided into five main applications, including cooling, heating, lighting, hot water and ventilation, but not many elevators and electric heaters that are difficult to include in the five applications are classified. ZONE Star refers to the comparison or separate management of areas for which the purpose of the building is similar or different. In addition, energy efficiency management requires control of the temperature, humidity, and people who will be measuring energy in the building, and the recent problem of fine dust should directly affect the ventilation of the building.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.4 no.2
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• pp.153-159
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• 2006

It is a serious task to the decommissioning of the uranium conversion plant that the demolition of the lagoon sludge. The main component of the sludge is ammonium nitrate and that is the very explosive material. Therefore, the bio-denitrification is a attractive process to remove the nitrate. In this work, some process variables was tested such as incubation temperature, nitrate concentration, electron donor, C/N ratio, seeding ratio, and pH with an anaerobic bacteria as Pseudomonas halodenitrificans. The results would be used as basic data to the continuous bio-denitrification process.

• Nuclear Engineering and Technology
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• v.9 no.4
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• pp.223-236
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• 1977

An integral computer code has been developed for a mechanical and thermal design and performance analysis of an oxide fuel rod in a pressurized water reactor. The code designated as FROD 1.0 takes into account the phenomena of radial power depression within the pellet, cracking, densification and swelling of the pellet, fission gas release, clad creep, pellet-clad contact, heat transfer to coolant and buildup of corrosion layers on the clad surface. The FROD 1.0 code yields two-dimensional temperature distributions, dimensional changes, stresses, and internal pressure of a fuel rod as a function of irradiation time within a reasonable computation time. The code may also be used for the analyses of oxide fuel rods in other thermal reactors. As an application of FROD 1.0 the behavior of fuel rod loaded in the first core of Go-ri Nuclear Power Plant Unit 1 is predicted for the two power histories corresponding to steady state operation and Codition II of the ANS Classification. The results are compared with the design criteria described in the Final Safety Analysis Report and a discrepancy between these two values is discussed herein.

• Journal of the Korean Society for Nondestructive Testing
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• v.19 no.6
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• pp.411-419
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• 1999

It has been well recognized that a long term service at elevated temperature of $350^{\circ}C{\sim}550^{\circ}C$ induces embrittlement damage due to carbide precipitation and/or P, Sb and Sn segregation at grain boundaries and thereby deteriorates the grain boundary strength of heat resisting components in the energy-related plants. Therefore, it is very important to assess quantitatively the extent of embrittlement damage of heat resisting components to secure the reliable and efficient service condition and to prevent brittle failure in service. However, because fracture tests are limited in size and number of specimen obtained from the structural components, nondestructive test method is required. In this study, the optimum electrochemical parameters are investigated and discussed to evaluate nondestructive embrittlement damage for aged 2.25Cr-1Mo steels by means of electrochemical polarization test method (ECPTM) in proper corrosive environment. In addition, the electrochemical test results are compared with embrittlement degree evaluated by semi-nondestructive SP test.

• Applied Chemistry for Engineering
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• v.20 no.2
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• pp.177-185
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• 2009

The failure analysis of scales deposited on automotive thermostat housing has been carried out. Observations using energy dispersive spectroscopy and electron probe micro analyzer indicate that the main components of scales are some of additives of coolant used. For a detailed investigation of organic matters pyrolysis-GC/MS is employed. The result shows that the main organic component is benzoic acid and furthermore, a small amount of acetophenone, benzene and phenyl group is detected. Based on the results of failure analysis performed, the scales on automotive thermostat housing appear due to the deposition of coolant components, followed by crevice corrosion, into gap between housing and rubber horse. New accelerated test methodology, which could mimic the scale formation and the crevice corrosion on thermostat housing, is developed considering the above results. In order to reproduce the real operating conditions, the accelerating factors, i.e. temperature and humidity, are changed and programmed. The reproducibility of the accelerated test proposed is confirmed after analyzing the scales obtained from the accelerated test.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.83-89
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• 2003

A temperature- and pressure-reducing process is utilized to handle the spent fuel assembly in the post-irradiation examination facility. This process includes three separated unit processes. First one is the decontamination process to clean the spent fuel assembly casks. The second process is the temperature-reducing process to reduce the temperature elevated by decay process in the spent fuel assembly. The third process is the filtration process to remove insoluble particles existed in the casks using filters. Up-to-date technologies as well as practical theories related to the temperature- and pressure-reducing process is reviewed in this report. The test-operation process for various tests and the test results of the temperature- and pressure-reducing process for J-44 and K-23 spent fuel assemblies are also described in detail. This report must be effectively used for the normal operation of the facility with the awareness of unprecedented problems which could occur by continuing operation of the PIE facility.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2006.05a
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• pp.1027-1031
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• 2006

Recently, mobile-type analysis system when emergency patient can check his blood condition in the transportation or vessel has being required. Under the present system, it takes lots off-time to know the blood analysis result of patient, so, it may lead to a dangerous situation. But, in this study, analysis time makes to fall down to $1{\sim}min$. to emergency treatment patient more quickly, and you can check the information by wireless PC through Bluetooth base. It is able to measure in about 7minutes from 25minutes of warming-up time in existing facilities by testing temperature peculiarity curve, to operate system without error even minute temperature change by adoption DUAL heating. And Bluetooth base was adopted to reduce power consumption and be able to hospital networking by keeping and sending analyzed data when it needs.

• Proceedings of the Korean Vacuum Society Conference
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• 2013.08a
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• pp.106.2-106.2
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• 2013

본 논문은 반도체 및 평판 디스플레이 생산공정에서 가동되고 있는 건식 진공펌프들의 정밀 상태진단 및 예지 보수를 위한 pump monitoring system (PMS)의 제품화에 필요한 프로그램의 개발 내용을 소개한다. 본 연구에서 소개하는 건식 진공펌프들의 정밀 상태진단 및 예지보수기법은 PCT 특허 2 건으로 이미 등록된 내용이며, 본 논문은 이들 기법의 실제 구현에서 직면하는 기술적 문제점과 극복 방안을 제시한다. 본 논문에서는 현재 반도체 공정에 사용되고 있는 건식 진공펌프들로부터 측정하는 다중 상태변수들의 조사 결과를 소개한다. 이들 상태변수 측정치들이 갖는 개략적 특성을 통계적 분포함수로 분석한 결과를 우선 보인다. 특히 펌프 구동모터들의 소비 전류신호는 두 평균값에 대한 분포 즉 두 종의 분포함수를, 그리고 온도, purge gas 유량, 배기구 압력 등은 정상적 평균값에 대한 한나의 분포를 보였다. 따라서 구동모터들의 소비전류의 분포 즉 두 상하 수준('low and high' current level)에 따라 batch data를 구분하는 방법의 개발이 필요하였다. 본 연구에서는 step 함수형 eigenvector를 적용하여 소비전류 신호의 상하수준 천이 영역과 방향을 동시에 인식할 수 있는 기법을 개발 적용하였으며, 3300회의 배출가스 부하에 변화에 대한 천이 영역과 방향을 인식에 하나의 실패도 보이지 않음을 확인하였다. 기존의 측정 상태변수에는 회전기계류의 정밀 상태진단 및 예지보수에 핵심적인 기계진동 측정용 진동센서를 포함하고 있지 않은 기술적 문제점이 발견되었다. 기존 진동센서들의 높은 가격 뿐 아니라 진동센서의 출력신호를 저/중/고역 주파수 대역의 실효치로 환산하는 기술적 한계 때문에 진공펌프 상태진단에 아직 사용하고 있지 않고 있다. 본 연구에서는 진동선서 비용의 저감화 방안뿐 아니라 로터 회전 대역(250Hz 이하 저주파 영역), 베어링 진동 대역(250 Hz~2.5 kHz의 중간 주파수 영역), 그리고 기어 진동 대역(2.5 kHz~10 kHz 주파수 영역)별 실효치를 실 시간 측정할 수 있는 진동측정 모듈의 제품화 모델을 개발하였다. 개발 제품의 성능 뿐 아니라 현장 시험결과를 소개한다. 마지막으로 본 연구팀이 개발한 PCT 특허 2 건에 포함된 건식 진공펌프들의 정밀 상태진단 및 예지보수기법에 대한 현장 시험결과를 간략히 소개한다.

• Journal of Energy Engineering
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• v.8 no.4
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• pp.605-611
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• 1999

Conventional methods for assessing remaining life of critical high temperature components in fossil power plants rely on nondestructive inspection practices and accompanying life analysis based on fracture mechanics By using these conventional methods. It has been difficult to perform uninterrupted in-service inspection for life prediction. Thus, efforts have been made for developing on-line remaining life monitoring systems employing information on the shape of structures, operating variables and material properties. In thus study, a software for on-line life monitoring system which performs real-time life evaluation of a high temperature system headers was developed. The software is capable of evaluating creep and fatigue life usage from the real-time stress data calculated by using temperatures/stress transfer Green functions derived in advance for the specific headers. The major benefits of the developed software life in determining future operating schedule, inspection interval, and replacement plan by monitoring real-time life usage based on prior operating history.

• Composites Research
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• v.35 no.3
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• pp.161-174
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• 2022

SiC fiber-reinforced SiC matrix composite is a promising accident-tolerant fuel cladding material to improve the safety of light water nuclear reactors. Compared to the current zirconium alloy fuel cladding as well as metallic accident-tolerant fuel cladding, SiC composite fuel cladding has exceptional accident-tolerance such as excellent structural integrity and extremely low corrosion rate during severe accident of light water nuclear reactors, which reduces reactor core temperature and delays core degradation processes. In this paper, we introduce the concept, technical issues, and properties of SiC composite accident-tolerant fuel cladding during operation and accident scenarios of light water nuclear reactors.