• 대한용접접합학회:학술대회논문집
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• 대한용접접합학회 2005년도 추계학술발표대회 개요집
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• pp.73-75
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• 2005

The objective of this study is to estimate the feasibility of X-ray diffraction method application for fatigue life assessment of the high-temperature pipeline steel such as main steam pipe, reheater pipe and header etc. in power plant. In this study, X-ray diffraction tests using various types of specimen simulated low cycle fatigue damage were performed in order to analyze fatigue properties when fatigue damage conditions become various stages such as 1/4, 1/2 and 3/4 of fatigue life, respectively. As a result of X-ray diffraction tests for specimens simulated fatigue damages, we conformed that the variation of the full width at half maximum intensity decreased in proportion to the increase of fatigue life ratio.

• 에너지공학
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• 제25권2호
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• pp.86-93
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• 2016

화력발전소 터빈 본관 내부는 고온의 스팀 배관, 탈기기, 스팀 저장 탱크, 수증기 차단 밸브 등의 존재로 터빈 본관 작업 공간의 공기가 고온으로 올라가서 작업자가 장시간 작업하기 곤란한 경우가 발생한다. 터빈 빌딩 작업공간의 공기를 냉각하기 위해 터빈 빌딩 창문을 개방하여 외부의 찬 공기로 냉각하고 상부에 환풍기를 설치하여 외부로 배출한다. 이렇게 한 경우에도 국부적으로 고온의 영역이 존재하여 작업 공간의 냉각을 위한 추가적인 환풍기 설치가 필요하고, 이 경우 환풍기의 위치와 유량에 대한 최적화가 필요하다. 본 연구는 여러 가지 경우의 열 유동 해석을 통해 쾌적한 작업환경을 위한 추가적인 환풍기의 위치와 용량을 최적화한 방안을 제시 하는 것을 목적으로 하였다. 본 연구를 통해 기존 환풍기 위치와 용량을 기준으로 터빈 본관 내부의 고온 영역인 탈기기 영역근처의 열원을 배출하는 환풍기를 추가로 설치하는 것이 전체온도를 $3.0^{\circ}C$, 가장 고온의 영역인 탈기기영역의 온도를 $4.2^{\circ}C$ 저감할 수 있었다.

• 비파괴검사학회지
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• 제20권1호
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• pp.10-17
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• 2000

화력발전소 보일러의 주증기관, 헤더, 스팀드럼 등과 같은 주요 고온배관설비에서 발생하는 크리프 손상을 측정하는 비파괴적 측정방법에는 레프리카, 전기저항법 및 경도법 둥이 적용되고 있으나, 이들 방법들은 측정절차 및 준비가 복잡할 뿐만 아니라 접근이 가능한 설비표면에만 적용되는 제한점을 가지고 있다. 따라서 본 논문은 이들 종래의 방법을 신뢰성 있고 정량적인 초음파 비파괴평가법으로 보완 및 적용을 위하여, 실제 고온배관의 운전조건을 모의하여 수행한 크리프 인공열화실험 및 이들 크리프손상재에 대한 초음파실험을 통한 주파수분석 연구로서, 크리프손상 상태별 초음파 신호 분류를 위해 초음파신호의 각종 주파수특성을 평가하였다.

• 비파괴검사학회지
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• 제20권1호
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• pp.18-26
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• 2000

화력발전소 보일러 고온배관인 주증기관, 헤드 및 증기드럼 등의 설비들은 장시간동안 고온고압의 가혹한 조건으로 운전됨에 따라 크리프손상에 의해 열화되고 있다. 이들 설비의 크리프손상측정에 적용되는 종래의 비파괴기법인 레프리카법, 전기저항법 및 경도법 등은 복잡한 측정절차 및 접근성, 검사결과의 신뢰도 및 측정정도 등 여러가지면에서 단점이 많다. 따라서 본 논문에서는 화력발전소 주요 고온배관에서 발생되는 경년열화인 크리프손상에 대한초음파 측정연구를 수행한 결과로서, 고온배관재료인 Cr-Mo강의 크리프 인공열화재를 대상으로 이들에 대한 크리프손상 상태별 초음과 음속(sound velocity) 및 감쇠(attenuation)의 초음파 신호특성을 평가하였다.

• 한국정밀공학회지
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• 제25권7호
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• pp.116-123
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• 2008

In the fossil power plant, the reliability of the components which consist of the many welded parts depends on the quality of welding. The residual stress is occurred by the heat flux of high temperature during weld process. This decreases the mechanical properties as the strength of fatigue and fracture or causes the stress corrosion cracking and fatigue fracture. Especially, the accidents due to the residual stress occurred at the weld parts of high-temperature and high-pressure pipes and steam headers. Also, the residual stress of the welded part in the recently constructed power plants has been brought into relief as the cause of various accidents. The aim of this study is the measurement of the residual stress using the x-ray diffraction method. The merits of this are more accurate and applicable than other methods. The materials used for the study is P92 steel for the use of high temperature pipe on super critical condition. The variables of tests are the post-weld heat treatment, the surface roughness and the depth from the original surface. The test results were analyzed by the distributed characteristics of the full width at half maximum intensity (FWHM) in x-ray diffraction intensity curve and by the relation of hardness with FWHM.

• 동력기계공학회지
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• 제18권5호
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• pp.66-73
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• 2014

This study was considered to occur the local wall thinning at elbow which is flowing the steam and high-pressure water of high-temperature. The angle of elbow is ${\Theta}=45^{\circ}$ and $67.545^{\circ}$. The damage behaviors of inner or outer wall thinning elbow under internal pressure were calculated by FEA(finite element analysis). We compared the simulated results by FEA with experimental data. The FEA results are as follows: In the FEA results of three types of wall thinning ratio, the circumferential and longitudinal stresses show the similar values regardless of the angle of elbow, respectively. The circumferential strain was greater at elbow of small angle, but the longitudinal strain was nearly same. The FEM stress of outer wall thinning elbow was slightly higher than that of the inner wall thinning elbow, and strain was also slightly higher. In the experiments, the circumferential strain was increased with the increase in the internal pressure, and increased rapidly on about 0.2% of strain. The longitudinal strain was small. The strain at break was much smaller than 0.2%. In the relation between pressure and eroded ratio, the criteria that can be used safely under operating pressure and design pressure were obtained. The results of FEA were in relatively good agreement with those of the experiment.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2003년도 춘계학술대회 논문집
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• pp.1458-1462
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• 2003

High temperature and high pressure heavy water flows through the pipes in atomic power plants. The curved parts of pipes are critical parts in that they change the direction of steam flow, and these parts are especially affected by severe wear. Therefore, most pipes in atomic power plants are tested by non-destructive examination by workers who use ultrasonic sensors to measure the wall thickness of pipes. But not only are these pipes located in a very dangerous environment, but the space is also very limited. For the safety of workers, it is necessary to design a device that uses a mobile robot that can inspect curved pipes. This paper presents the design and construction of a small device that can generate the necessary contact forces between ultrasonic sensors and pipe walls in a limited space. And a mobile robot is used in place ortho worker for successful non-destructive examination.

• 대한기계학회논문집A
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• 제28권12호
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• pp.1968-1973
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• 2004

Structural degradations are often experienced on the components of nuclear power plants in reactor pressure vessels (RPV) and steam generators (SG) when these components are exposed to high temperature and high pressure for a long period of time. Such conditions result in the change of microstructures and of mechanical properties of materials, which requires an evaluation of the safeguards related to structural integrity. In a primary reactor cooling system (RCS), a dissimilar weld zone exists between cast stainless steel (CF8M) in a pipe and low-alloy steel (SA508 cl.3) in a nozzle. Thermal aging is observed in CF8M as the RCS is exposed for a long period of time under the operating temperature between 290 and 33$0^{\circ}C$. Under the same conditions, it is well known that degradation is not observed in low alloy steel. An investigation of the effect of thermal aging on the various mechanical properties of the dissimilar weld zone is required. The purpose of the present investigation is to find the effect of thermal aging on the dissimilar weld zone. The specimens are prepared by an artificially accelerated aging technique maintained for various times at 43$0^{\circ}C$, respectively. Then, The various mechanical test for the dissimilar welds are performed.