• Corrosion Science and Technology
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• 제3권6호
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• pp.233-239
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• 2004

Primary water stress corrosion cracking of steam generator tubings occur on many tubes in pressurized water reactors(PWRs), and they are repaired using sleeves or plugs. In order to develop proper repair criteria, it is necessary to know the leak behavior of the tubes, which have stress corrosion cracks. Crack development tests were carried out on the tubes at room temperature, and leak rate and burst pressure were measured on the degraded tubes at room temperature and a high temperature. No leakage was detected on the tubes where 100 % through wall crack developed, at 1560 psi, which is an operating pressure difference of pressurized water reactors(PWRs). In some tests, leak rates of the tubes increased with time at a constant internal water pressure. A test tube showed a very small amount of leakage at 2700 psi in a high temperature pressure test at $282^{\circ}C$, but it disappeared after the pressure increased slightly. Even cracks are 100 % through wall, they need to open in order to reach a certain amount of leak rate at the operating pressure difference.

• 한국가스학회지
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• 제11권4호
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• pp.47-53
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• 2007

고압 가스 배관망의 안전관리는 매우 중요한 문제로 배관의 외적 손상으로 구멍이 생길 경우 발생하는 누출은 폭발 및 환경오염을 포함한 막대한 경제적 손실을 야기할 수 있다. 누출 검지를 위한 PLDS(Pipeline leak detection system린 기술로 저압확장파 검지 기술이 적용되고 있으며 본 논문에서는 CFD++ 상용코드를 활용하여 배관 누출시 유동특성을 이론적으로 해석하여 저압확장파의 발생 메커니즘과 음속으로 확장되는 전파특성을 규명하였다. 또한 긴 배관망에 적용하기 위한 1차원 해석 방법을 제시하고 신뢰성을 CFD해석 결과로 검증하였다.

• 한국진공학회지
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• 제16권4호
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• pp.235-243
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• 2007

지금 국내에서는 토카막 핵융합실험장치, 대전류 중성입자빔 실험장치 및 우주 모의실험실 같은 거대시설의 건설과 운용이 활발하다. 이런 시설의 핵심설비인 대형 진공용기는 중소형 용기에 비해 누설 가능성은 높은 반면 기체누설을 검사하는 것은 까다롭다. 중소형 용기에서 널리 사용되는 헬륨누설검사 방법을 어떻게 효율적으로 이런 대형 용기에 적용할 수 있는가 알아보기 위해, 다양한 가상적인 누설검사 시스템들을 구성하고 압력분포 및 헬륨 분압을 계산하여 주어진 장치조건에서 적절한 검사 시스템을 찾는 방법에 대해 논한다.

• 한국유체기계학회 논문집
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• 제11권1호
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• pp.26-32
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• 2008

The safe operation of high pressure pipe line systems is of significant importance. Leaks due to faulty operation from the pipelines can lead to considerable product losses and to exposure of community to dangerous gases. There are several leak detection methods of pipeline network which have recently been suggested. The negative pressure wave detection technology, which has advantages of short time detection availability, accurate leaking location estimate capability and cost effective, is concentrated in this study. Theoretical analysis of the flow characteristics for leaking through a hole on the pipe wall has been performed by using Fluent 6.3, commercial CFD package. The results of 3-dimensional analysis near leaking hole confirm the occurrence of negative pressure wave, and the results of 2-dimensional analysis verify the characteristics of propagation of the wave which travels with speed equal to the speed of sound in the pipeline contents. Characteristics of leakage and pressure in a pipe with a hole have been analyzed for the various pipe and hole sizes.

• Corrosion Science and Technology
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• 제3권1호
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• pp.30-33
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• 2004

It has been reported that some events of a rupture of seam generator tube have occurred in nuclear power plants around the world. Main causes of the leakage are from various types of corrosion in the steam generator(SG) tubings. Primary water stress corrosion cracking(PWSCC) of steam generator tubings have occurred in many tubes in Korean plant, and they were repaired using sleeves or plugs, In order to develop proper repair criteria, it is necessary to ascertain the leak behavior of the tubings. A high pressure leak and burst testing system was manufactured. Various types of Electro Discharged Machined (EDM) notches were developed on the SG tubes. Leak rate and burst pressure were measured on the tubes at room temperature. Burst pressure of the part through wall defected tubes depends on the defect depth, Water flow rates after the burst were independent of the t1aw types; tubes having 20 to 60 mm long EDM notches showed similar flow rates regardless of the defect depth. A fast pressurization rate gave the tube a lower burst pressure than the case of a slow pressurization.

• 한국세라믹학회지
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• 제42권12호
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• pp.842-845
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• 2005

Glass composites containing ceramic fiber have been developed for Solid Oxide Fuel Cell (SOFC) seals. Effect of glass type, loading pressure and thermal cycle the leak rates of composite seals was investigated. Seal performance of two commercial glasses was compared with that of $SiO_2BaO-B_2O_3$ glass synthesized in this work. The leak rate for seals made of pyrex(R) increases from $\~0.0005\;to\;\~0.004sccm/cm$ as the gas pressure increases from 10 to 50 kPa. The soda lime silicate glass seal shows the leak rate two times higher than the one made of pyrex(R) or $SiO_2BaO-B_2O_3$ glass. The viscosity of glass at the seal test temperature is presumed to affect the leak rate of the glass seal. As the applied loading pressure increases from 0.4 to 0.8 MPa at $750^{\circ}C$, the leak rate decreases from 0.038 to 0.024 sccm/cm for composite seals. It has been found that during 50 thermal cycles between $450^{\circ}C\;to\;700^{\circ}C$ leak rates remained almost constant, ranging from 0.025 to 0.03sccm/cm. The results showed an excellent thermal cycle stability as well as sealability of the glass matrix ceramic fiber composite seals.

• 한국가스학회지
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• 제23권6호
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• pp.74-80
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• 2019

수소를 고압으로 압축하여 사용하는 수소충전소는 안전 확보를 위해 설비간의 안전거리를 규정하고 있다. 수소 충전소에서 발생하는 사고 중 대부분의 사고는 누출사고이며, 누출 시 점화로 인해 제트화염이 생성된다. 고압의 수소 누출로 인한 가스 확산 및 제트화염의 해석은 안전거리 설정에 가장 중요한 요소이다. 본 연구에서는 고압의 환경에서 운용되는 수소충전소에서 발생할 수 있는 누출사고를 대비한 안전관리 규정 도출을 위하여 누출원 크기별 누출조건을 모사하고 위험거리 등을 파악하여 향후 안전기준 제정 시 참고자료로 활용하고자 한다.

• 한국진공학회지
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• 제15권4호
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• pp.347-353
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• 2006

국제도량형위원회의 질량 및 관련량 자문위원회 (CCM)가 주관하는 헬륨 투과형 표준리크(standard leak) 핵심측정표준 국제비교 (key comparison, KC)에 참여하기 위하여 기존의 정압형 리크표준기에 porous plug를 추가하여 측정범위를 $10^{-6}$ Pa L/s 까지 확장한 헬륨 미세리크 표준기를 개발하였다. 이를 위해 헬륨 기체에 대한 고진공 및 초고진공 표준기의 압력비와 porous plug의 콘덕턴스를 새롭게 측정하였으며, 개발된 장치를 이용하여 명목 값이 $5.6{\times}10^{-4}$ Pa L/s 인 투과형 표준리크를 직접 교정한 결과 표준기와 차이가 11.1 % 임을 알 수 있었다.

• 동력기계공학회지
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• 제11권3호
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• pp.35-40
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• 2007

Leak would happen because of the damage of high temperature and high-pressure valve in nuclear power plant. condition based prevention maintenance is essential by using the suitable method based on local condition. Energy loss prevention can prevent from an accurate test, Local actually and ability. The methods of test for high energy fluid leak at present are analysis of ${\Delta}T$, AE(Acoustic Emission) analysis, and thermal image. The result for test of secondary system in nuclear power plant Unit reveals that the AE occurred clearly in leakage situation, but thermal image didn't occur. It is identified that leak is occurred when the orifice located front and back of valve operates. It shows that making a impatient judgment by using the single method if it is leakage is containing uncertainty. So we think that using the Multi-Measuring method is more sound judgment than single-measuring method.

• 대한전기학회:학술대회논문집
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• 대한전기학회 1992년도 하계학술대회 논문집 A
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• pp.506-507
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• 1992

When it comes to the 'Leak Detector System' generally, our country has a large income 'Rotary Type Leak Detector' of foreign goods. The completed development of the 'Line Type Leak-Detector' system was produced to check Whether the containers for small and large on the filling line are auto defective. This system is applied to the filling package Processing during the production and contributed to inproving competiveness of domestic containers manufactures of all society of Industry. Also, high precision and realiablity, very compact size, low cost and Easy set-up etc. by checking the experimental data directly plan, Design and making for '1 Compression Head Control Leak Detector System'. This flexcible system can be equipped with multiple Compression heads depending on the requested prodution test rate and test precision.