• KEPCO Journal on Electric Power and Energy
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• 제8권2호
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• pp.93-96
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• 2022

The boiler tubes of thermal power plants are exposed to harsh environment of high temperature and high pressure, and the deterioration state of materials rapidly increases. In particular, parent material and welds of the materials used are subjected to a temperature change and various constraints, resulting in deformation and its growth, resulting in frequent leakage accidents caused by tube failure. The power plant checks the integrity of boiler tubes through non-destructive testing as it may act as huge costs loss and limitation of power supply during power station shutdown period due to boiler tube leakage. However, the current non-destructive testing is extremely limited in the field to detect micro cracks. In this study, the ability of metal magnetic memory technique to detect flaws of size that are difficult to inspect by the visual or general non-destructive methods was verified in the early stage of their occurrence.

• 사물인터넷융복합논문지
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• 제8권1호
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• pp.23-29
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• 2022

본 연구의 개발대상 제품은 선박 및 발전용 EGB(Exhaust Gas Boiler-폐열보일러) 종류로써 디젤 엔진, 가스 엔진, 가스 터빈 등에서 나오는 배기 가스의 여열을 이용하여 물을 가열하여 고온·고압의 증기나 온수를 발생시키는 열회수 장치이다. 발생된 증기나 온수는 선박의 선실 난방 및 온수 시설이나 HFO Heating, 터빈 구동에 필요한 동력원으로 사용된다. 폐열보일러의 원리는 여열을 가진 고온의 배기 가스가 보일러의 Tube를 통과하면서 물을 데우는 역할을 한다. 데워진 물은 스팀 형태로 선실이나 터빈장치로 보내어져 사용하게 되는 구조이다. 본 연구에서는 EGB의 열전달 부품인 관형 튜브를 Plate Tube로 대체하여 열전달 표면을 늘려 효율을 극대화하는데 목표가 있다.

• 대한전기학회논문지
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• 제37권11호
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• pp.786-795
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• 1988

In this paper a boiler control system simulator is designed and inplemeted in order to evaluate performance of the Fault Tolerant Control System. It simulates a boiler control system of a thermal power plant containtng boiler process, peripheral units and analog controller. The simulator uses a low order linear model for boiler first order models for the peripheral unit. Specifically the model of the analog controller is modularized and transformed to digital form if order to be implemented using a micro-processor board. The experimental results show the usability of the developed simulator for the performance test of the FTCS.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1986년도 한국자동제어학술회의논문집; 한국과학기술대학, 충남; 17-18 Oct. 1986
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• pp.178-180
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• 1986

본 연구에서는 산업용 팩키지 보일러의 최적한 연소제어를 위하여 O/sub 2/ 제어기의 구성 및 PID제어 알고리즘을 도입하고 그것에 따른 하드웨어 및 소프트웨어를 고찰하였으며 그 결과 하드와이어드 논리제어기나 기존의 PC보다 분산제어의 효율적 처리가 가능하였다. BD/Micro PC 시스템에서 시퀀스 제어를 필요로하는 기능은 BD PC가, 아날로그 시스템을 다루는 PID 제어같은 기능은 .mu.C가 담당함으로서 제어범위가 넓어져 각종의 연산기능확대, BD PC와 .mu.C와의 데이터 링크, 그리고 고장진단등의 기능이 추가되었다.

• 동력기계공학회지
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• 제13권5호
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• pp.95-102
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• 2009

A steam generator (boiler) in thermal power plants, consisting of more than 30,000 parts and components, can lead to the plant shutdown with damage to even the small part of the components; esp., like weld failures on boiler tubes. Consequently it is greatly demanded to improve the quality of the weld on the boiler tube for the stable operation of the power plants. Because of the feature of the welding, which is done past by melting the work pieces and adding a filler material that cools to become a strong coalescence, there is a great possibility that weld failures take place. As a result, it is regulated to make a non-destructive testing, like radiography test, to detect defects and flaws in the weld. The current film radiography test provides a lower image quality exceeding 2.0% of a basic quality level for a penetrameter, it is very likely to fail to detect micro defect. As a result, the prevention for the boiler tube failure has not been made effectively. In this study, computed radiography technology has been applied as a digital radiography test to the boiler tube weld, and Se-75 radiation source was used to improve the image quality, instead of Ir-192 source. As a result of this study, it is proven to save the time and cost for test and to enhance the quality level of penetrameter penetrating image, which enables to upgrade the quality of radiography test to the boiler tube weld.

• 대한환경공학회지
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• 제27권10호
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• pp.1081-1089
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• 2005

본 연구에서는 기존에 중유를 사용하는 상용보일러에서 오리멀젼 연료의 활용 가능성을 평가하기 위하여 소형 보일러에서 오리멀젼 연료의 기본적인 연소특성을 실험과 더불어 수치해석하였다. 오리멀젼의 주요 연소특성은 최고 화염온도가 버너로부터 $20{\sim}30\;cm 뒤쪽에 나타나는 화염지연현상과 비교적 넓게 분포하는 화염의 형태로 이는 오리멀젼 제조과정에서 포함된 높은 수분함량과 미세한 수부액적으로 이한 미소폭발 현상에 기인한다. 오리멀젼 연료의 연소특성에 미치는 영향을 평가하기 위하여 연료공급량, 무화유체의 종류, 그리고 계산에 사용된 현상학적인 복사모델과 같은 중요한 설계 및 운전인자에 대한 일련의 변수연구를 수행하였다. 연소특성인 최고 화염온도 지연현상은 연료공급 속도를 조절함으로써 어느 정도 저감시킬 수 있었으며 연소생성물로 CO와 $SO_2$ 그리고 NO가스의 연소로 내 발생특성을 평가하였다. 또한 무화용 유체로 증기를 사용하였을 경우 로내 연소상태는 무화용 공기에 비해 안정화 되고 고온영역이 감소되는 결과를 보였다. 일반적으로 본 연구에서 수행한 실험조건에 대한 수치해석 결과는 물리적으로 일관성 있는 결과를 제시하였으나 오염물질 생성농도에 대한 보다 정확한 예측을 위해서는 추후 현상학적인 모델개선을 필요로 한다. 결국 본 연구로부터 개발된 컴퓨터 프로그램은 기존의 상용화 중유 보일러에서 오리멀젼 연료로 대체 사용시 개선사항 및 유용한 운전 자료를 제공할 것으로 판단된다.

• Nuclear Engineering and Technology
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• 제19권3호
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• pp.198-204
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• 1987

발전소 과도현상과 비냉각재 상실사고를 모의할 수 있는 가압경수로발전소 모의코드 MCSIM을 개발하였다. 원자로 냉각재계통은 에너지 방정식과 운동량 방정식을 분리 취급하면서 Drift Flux 2상 유동모델, 적분 운동량 방정식 등을 사용하여 모델링하였다. 증기발생기의 모사는 Pot Boiler 모델을 사용하였고, 2차계통을 위해서는 분리 취급된 정상상태 에너지 방정식과 운동량방정식을 핵출력 계산을 위해서는 점 동특성 방정식을 사용하였다. 현재의 코드성능을 시험하기 위해 완전 냉각재 유동상실사고와 제어봉 집합체 인출 사고를 계산하여 그 결과를 원자력 5/6호기 최종 안전 보고서의 결과와 비교하였다.

• 대한기계학회논문집
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• 제17권2호
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• pp.300-312
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• 1993

The material deterioration of service-exposed boiler tube steels in fossil power plant was evaluated by using the electrochemical technique namely, modified electrochemical potentiokinetic reactivation(EPR). It was focused that the passivation of Mo$_{6}$C carbide which governs the mechanical properties of Mo alloyed steels did not occur even in the passivity region of steel in sodium molybdate solution and the reactivation peak current (Ip) observed as the result of non-passivation indicating the precipitation of Mo$_{6}$C carbides. To obtain the optimal test conditions for the field test by using the specially designed electrochemical cell, the effects of scan rate, the surface roughness and the pH of electrolyte on Ip value were also investigated. Furthermore, the change of mechanical properties occurred during the long time exposure at high temperature was evlauated quantitatively by small punch(SP) tests and micro hardness test taking account of the metallurgical changes. It is known that reactivation peak current (Ip) has a good relationship with Larson-Miller Parameter(LMP) which represents the information about material deterioration occurred at high temperature environment. In addition it was possible to estimate the ductile-brittle transition temperature (DBTT) by means of the SP test. The Sp test could be, therefore, suggested as a reliable test method for evaluating the material degradation of boiler tube steels. From the good correaltion between the SP DBTT and Ip values shown in this study, it was knows that the change of mechanical properties could be evaluated non-destructively by measurring only Ip values.ues.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4477-4490
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• 2023

Fuel locking mechanisms (FLMs) are essential in upward-flow research reactors to prevent accidental fuel separation from the core during reactor operation. This study presents a novel design concept for a remotely controlled plate-type nuclear fuel locking mechanism. By employing electromagnetic field analysis, we optimized the design of the electromagnet for fuel unlocking, allowing the FLM to adapt to various research reactor core designs, minimizing installation space, and reducing maintenance efforts. Computational flow analysis quantified the drag acting on the fuel assembly caused by coolant upflow. Subsequently, we performed finite element analysis and evaluated the structural integrity of the FLM based on the ASME boiler and pressure vessel (B&PV) code, considering design loads such as dead weight and flow drag. Our findings confirm that the new FLM design provides sufficient margins to withstand the specified loads. We fabricated a prototype comprising the driving part, a simplified moving part, and a dummy fuel assembly. Through basic operational tests on the assembled components, we verified that the manufactured products meet the performance requirements. This remote-controlled micro locking mechanism holds promise in enhancing the safety and efficiency of plate-type nuclear fuel operation in upflow research reactors.

• 한국분무공학회지
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• 제10권3호
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• pp.9-16
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• 2005

To investigate spray and combustion of emulsified fuel of W/O type, we mixed water with light oil by using ultrasonic energy adding system. We measured the SMD of sprayed droplet to find atomization characteristics of emulsified fuel with using the Malvern 2600D system. Major parameters are the weight ratio of water($0{\sim}30%$ by 10%) in emulsified fuel injection pressure(lobar), and the measurement distance($10{\sim}100mm$ by 10mm). Combustion visualizing system is made up commonly used boiler system and digital camera 1/500s to investigate combustion phenomena. As a result, the more water contents increased, the more SMD increased. The water particle of emulsified fuel made short flame in continuos spray combustion phenomena because of micro explosion.