• 한국습지학회지
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• 제26권2호
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• pp.139-146
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• 2024

노후된 관거 및 지하구조물의 균열 보수에 아스팔트계 주입재, 우레탄계 주입재, 시멘트계 주입재, 아크릴계 주입재 등 다양한 주입재가 사용되고 있다. 친환경적이고 습윤상태에서 경화가 잘되고 온도변화에 안정적인 물성을 갖는 아크릴계 누수 보수재에 대하여 연구하였다. 개량된 아크릴 누수 보수재와 기존 아크릴레이트 주입재의 성능 비교를 위하여 KS 규격의 실험방법에 준용하여 수중침지 길이변화율 시험, 수중 유실 저항성 시험, 내화학 성능시험을 실시하였다. 비교 실험해 본 결과 개량된 아크릴 누수 보수재는 기존 아크릴레이트 주입재보다 습윤상태, 온도변화, 화학적 반응에 따른 수축변화가 없었고 수중 저항성 실험에서 유실되지 않았다. 또한, 개량된 아크릴 누수 보수재의 환경적 영향성을 알아보기 위해 어류급성독성 실험과 급성경구독성 실험을 진행하여 관찰해 본 결과 실험체의 사망률이 없었고 특별한 유의점이 발견되지 않았다. 본 연구의 실험결과 개량된 아크릴 누수 보수재가 성능적으로 우수하고 환경적으로 안전하고 인체에 무해하다고 판단되었다. 본 연구의 다양한 실험결과 기존의 아크릴레이트 보수재보다 개량된 아크릴 누수 보수재가 관거 및 지하구조물 균열 부위의 보수재로 사용되기 적합하다고 사료된다. 본 연구는 아크릴 누수 보수재에 대한 적용성 평가에 대한 연구로 향후 기술 개발에 활용자료로 제안하고자 한다.

• 한국반도체및디스플레이장비학회:학술대회논문집
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• 한국반도체및디스플레이장비학회 2006년도 춘계학술대회
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• pp.115-120
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• 2006

MEMS 소자의 접합과 패키징에 Pb free solder를 사용하게 됨에 따라 발생하는 문제들로 인하여 보다 쉽고 간편하게 hermetic이 유지될 수 있는 방법을 검토하게 되었다. 따라서 본 연구는 epoxy 계통의 negative PR인 XP SU-8 3050 NO-2를 접착제로 사용 시 Si시편/ 유리기판, Si시편/LTCC기판에서 hermetic 특성의 고찰이 목적이다. Si시편/유리기판과 Si시편/LTCC기판의 접합 계면에 접착제로 negative PR을 토출하고 활성화 공정조건을 행한 시편들에서 hermetic이 얻어졌다. Si시편/유리기판의 leak rate는 $5.9{\times}10^{-8}mbar-1/sec$로 접합방법에 따른 영향은 없었으며, Si시편/LTCC 기판에서 leak rate는 $4.9{\times}10^{-8}mbar-1/sec$로 Si시편/유리기판과 비슷하였다. 향후 He leak rate를 개선하기 위해서는 LTCC 기판을 가공하여 PR 흐름방지 턱을 만들고, UV expose 에너지를 높이고 ($400mj/cm^2$ 조사), 시린지/기판의 gap 조절을 자동화 할 수 있는 vision system이 부착된 장비를 사용하면, 보다 낮은 leak rate 값을 얻을 수 있어 우수한 hermetic이 유지된다.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.145-155
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• 2001

This simulation first allows us to define a transition zone from a bubble to jet mode of the argon out-flow and hereinafter to define a similar area for water-steam leak in the KALIMER SG (Korea Advanced Liquid Metal Reactor Steam Generator) using a water mock-up system, taking into account the KALIMER leak classification and tube bundle design, as a simulation of a real water-steam into sodium leak. in accordance with leak conditions in the KALIMER SG, the transition from bubbling to jetting is studied by means of turbulence regime simulation for argon out-flow through a very small orifice, which has the equivalent diameter of about 0.253 mm. finally the noise generation mechanism is explained from the existing experimental data. We also confirmed the possibility of micro-leak detection from the information of the bubbling mode through simulations and the experiment in this study.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.132-140
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• 2024

In the event of a severe accident in Sodium Cooled Fast Reactors (SFR), the sodium combustion aerosols along with fission product aerosols would migrate to the environment through leak paths of the Reactor Containment Building (RCB) concrete wall under positive pressure. Understanding the characteristics of sodium aerosol transport through concrete leak paths is important as it governs the environmental source term. In this context, experiments are conducted to study the influence of various parameters like pressure, initial mass concentration, leak path diameter, humidity etc., on the transport and deposition of sodium aerosols in straight leak paths of concrete. The leak paths in concrete specimens are prepared by casting and the diameter of the leak path is measured using thermography technique. Aerosol transport experiments are conducted to measure the transported and plugged aerosol mass in the leak paths and corresponding plugging times. The values of differential pressure, aerosol concentration and relative humidity taken for the study are in the ranges 10-15 kPa, 0.65-3.04 g/m³ and 30-90% respectively. These observations are numerically simulated using 1-Dimensional transport equation. The simulated values are compared with the experimental results and reasonable agreement among them is observed. From the safety assessment view of reactor, the approach presented here is conservative as it is with straight leak paths.

• Nuclear Engineering and Technology
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• 제47권6호
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• pp.712-718
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• 2015

Cast duplex stainless steels are susceptible to thermal aging during long-term service at temperatures ranging from $280^{\circ}C$ to $450^{\circ}C$. To analyze the effect of thermal aging on leak-before-break (LBB) behavior, three-dimensional finite element analysis models were built for circumferentially cracked pipes. Based on the elasticeplastic fracture mechanics theory, the detectable leakage crack length calculation and J-integral stability assessment diagram approach were carried out under different bending moments. The LBB curves and LBB assessment diagrams for unaged and thermally aged pipes were constructed. The results show that the detectable leakage crack length for thermally aged pipes increases with increasing bending moments, whereas the critical crack length decreases. The ligament instability line and critical crack length line for thermally aged pipes move downward and to the left, respectively, and unsafe LBB assessment results will be produced if thermal aging is not considered. If the applied bending moment is increased, the degree of safety decreases in the LBB assessment.

• Corrosion Science and Technology
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• 제8권5호
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• pp.188-192
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• 2009

A forced outage due to a steam generator tube leak in a Korean nuclear power plant was reported.1) Primary water stress corrosion cracking has occurred in many tubes in the plant, and they were repaired using sleeves or plugs. In order to develop proper repair criteria, it is necessary to understand the leak behavior of the tubes containing stress corrosion cracks. Stress corrosion cracks were developed in 0.1 M sodium tetrathionate solution at room temperature. Steam generator(SG) tubes with short cracks were successfully fabricated with a restricted solution contact method. The leak rates of the degraded tubes were measured at room temperature. Some tubes with 100 % through wall cracks showed an increase of leak rate with time at a constant pressure.

• 한국압력기기공학회 논문집
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• 제17권1호
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• pp.8-17
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• 2021

The seat leakage test is required after the maintenance work on the valve seat. Either the test has been performed outside of the plant after cutting the valve from the pipe system or the simplified test has been performed so far. It was unable to perform the test at the plant site because it is hard to make a steady pressure on the valve inlet when it is installed in the pipe. This research aims to perform the leakage test in the nuclear power plant while it is installed in the pipe system. The mock-up test is performed by pressurizing the leak-off pipe on the valve body. The result is compared with traditional test result by pressurizing the valve inlet. Furthermore the chamber mock-up tests are performed under various conditions. The leak rate by the developed test using the leak-off pipe is found to be similar but greater than the leak rate by the existing test method. It implies that the test using the leak-off pipe is more conservative than the existing test. The methodology and the equipment which this paper suggests that on-site seat test is possible and the application of the technology could reduce the time and cost for the valve maintenance work significantly.

• 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.

• 한국소성가공학회:학술대회논문집
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• 한국소성가공학회 2005년도 춘계학술대회 논문집
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• pp.258-261
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• 2005

In this paper, experimental and numerical attempts are made fur application of powder metallurgy forming technology to making the cylinder block of a hydraulic pump of which height reaches nearly 70 mm and is ten times larger than the wall thickness. Leak tests with several compositions are carried out in order to find allowable powder composition to prevent leak under high pressure in service and CAE techniques are applied to finding proper process conditions. Through the research, the possibility of the powder formed cylinder block that is very competitive from the point of both cost and mass production has been shown, even though its thickness exceeds the recommended limit considering heterogeneous density distribution caused by the friction between a powder compact and dies.

• Composites Research
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• 제36권6호
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• pp.429-434
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• 2023

본 연구에서는 기존 배관 가스 누출 감지에 사용되던 음향방출 센서가 실시간 모니터링에 적용될 때 발생할 수 있는 문제들을 개선하기 위해, Macro-fiber composite (MFC) 트랜스듀서를 음향방출 센서로 사용하여 가스 누출 감지 시스템에 적용하였다. 적용 전 MFC의 구조를 최적화하기 위해 구조해석을 진행하여 제작하였고, 그 결과 MFC가 가지는 유연성으로 굴곡진 배관에 잘 밀착되어 AE 신호를 문제없이 수신할 수 있었다. AE 신호 분석 결과 고압 누출, 저압 누출 모두 파라미터 값 변화에 유의미한 결과를 보였으며, 특히, FFT 그래프의 파라미터에서 고압 누출의 경우 누출이 없는 경우 대비 120~626%의 변화량, 저압 누출의 경우 9~22%의 변화량을 보였다. 또한, 누출 발생 부위에서의 거리에 따라, 거리가 멀수록 이러한 파라미터 변화량이 줄어드는 경향을 보여, 추후 파라미터 변화량 감지를 통해 누출 감지가 가능할 뿐만 아니라, 변화량으로부터 누출 발생 위치를 파악할 수 있을 것으로 보인다.