• Transactions of the Korean Society of Mechanical Engineers B
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• v.35 no.8
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• pp.861-868
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• 2011

Flowmeters that measure the amount of fluid passing through conduits must kept accurate by comparison and the periodic calibration. The reference meters used are clamp-on meters that mount sensors on the outer wall of the pipe. They are called 1-path, 2-path or 4-path flowmeters depending on the number of sensors. We selected a flowmeter mainly used for K-water as test a flowmeter. We carried out experiments to find the intrinsic error of the flowmeter and errors in the downstream of a double bent pipe. The results show that there are the sensor locations that meet the tolerance. We suggested the angle of the sensor, the straight run from the downstream of the bent pipe and the number of sensors. So it is possible to improve the water treatment process and increase the accounted water rate by upgraded flow measurement technology.

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• 2001.11a
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• pp.79-80
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• 2001

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.11
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• pp.1037-1046
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• 2013

In this study, the establishment of the criteria for accurate measurement is investigated via a statistical analysis of experimental results. The magnitude of influence on measurement errors is severely affected by the number of paths, mounting angle of sensor, straight pipe length in sequence, and Reynolds number. Three-dimensional numerical analysis has been conducted to understand the flow patterns downstream of a double bent pipe. Numerical analysis shows that the results well agreed with the experimental ones in case of a sensor mounting angle of $0^{\circ}$ and L/D = 3, 5 of $45^{\circ}$, $135^{\circ}$ in a single path. As a result, when the Reynolds number is 700,000-1,400,000, the sensor error of a single-path ultrasonic flowmeter is reduced with the mounting condition of L/D = 3, $45^{\circ}$.

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 2014.11a
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• pp.193-194
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• 2014

원전은 고온기능시험 이후 2차계통 내부를 상대습도 40%이하로 관리하여 계통 재질 부식을 최소화하고 있다. 일반적으로 발전소에서는 운전 정지 후 상대습도 40%이하로 낮추는데 15일정도 소요되지만, 발전소 계통 중 일부 곡관부위는 약 60일정도 소요된다. 본 연구는 일부 계통 재료가 상대습도 제한치(<40%) 이상의 환경에서 장기간(최대 60일) 노출시 재료 건전성에 미치는 영향 평가이다. 평가를 위해 시편의 실험 전, 후 무게변화를 이용한 부식률 측정과 표면분석을 위해 광학현미경을 이용하였다. 사용 시편의 재료는 SA516 Gr.70이며 표면상태를 인위적으로 산화피막을 생성 시킨 것(2개)과 산화피막이 없는 것(6개)으로 2종류로 제작하였다. 총 시험기간은 60일이고 시험기간 중 산화피막이 없는 시편은 7일, 21일, 60일에 시편을 2개씩 꺼내어 무게를 측정하여 부식률을 계산하였다. 실험결과, 산화피막이 없는 시편은 노출되는 시간에 따라 부식률이 각각 0.35(7일), 0.21(21일), 0.67(60일) mpy이었고 산화피막이 있는 시편은 0.06(60일) mpy였다. 산화표면 분석결과, 산화피막이 없는 시편은 노출되는 시간에 관계없이 물방울이 맺힌 부분에 pitting을 확인하였다. 하지만, 산화피막이 있는 시편은 pitting의 흔적은 없었다. 산화피막이 없는 시편의 경우 시간에 따라 부식률은 높아지지만 학계에서 통용되는 뛰어난 내부식성 재료의 부식률 기준인 < 1 mpy이하기 때문에 재료 건전성에 미치는 영향은 거의 없을 것으로 판단된다. 또한, 대부분 원전의 경우 고온기능시험 또는 운전기간 동안에 2차계통 구성 재료 표면에 산화막이 생성되었기 때문에 산화피막이 있는 시편의 결과로 판단하면 상대습도 40%이상에 60일 이상 노출되어도 부식은 거의 일어나지 않았을 것으로 사료된다. 실증실험결과를 가지고 종합적으로 평가하면 상대습도 40%이상 환경에서 곡관부위가 60일이상 노출되어도 재료 건전성에 미치는 영향은 거의 없을 것으로 판단된다.

• Journal of Energy Engineering
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• v.26 no.2
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• pp.1-11
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• 2017

While they are becoming more viable, synthetic natural gas (SNG) plants, with their high temperatures and pressures, are still heavily dependent on advancements in the state-of-the-art technologies. However, most of the current work in the literature is focused on optimizing chemical processes and process variables, with little work being done on relevant mechanical damage and maintenance engineering. In this study, a combination of pipe system stress analysis and detailed local stress analysis was implemented to prioritize the inspection locations for main pipes of SNG plant in accordance to ASME B31.3. A pipe system stress analysis was conducted for pre-selecting critical locations by considering design condition and actual operating conditions such as heat-up and cool-down. Identified critical locations were further analyzed using a finite element method to locate specific high-stress points. Resultant stress values met ASME B31.3 code standards for the gasification reactor and lower transition piece (bend Y in Fig.1); however, it is recommended that the vertical displacement of bend Y be restricted more. The results presented here provide valuable information for future risk based maintenance inspection and further safe operation considerations.

• Journal of the Korean Society for Nondestructive Testing
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• v.28 no.2
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• pp.184-190
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• 2008

Various ECT techniques have been applied basically to assess the integrity of steam generator tithing in nuclear power plant. Among these techniques, the bobbin probe technique is applied generally to examine the volumetric flaws such as a crack-like defect and wear which is generally occurred on steam generator tubing, and additionally MRPC probe is used to examine closely tile top of tubesheet and bending regions due to the high possibility of cracking. Dent and bulge also may be formed on tube during installation process and operation of steam generator, but the dent and bulge indications greater than specific size criteria are recorded on examination report because these indications are not considered as flaw. These indications can be easily detected with bobbin probe and approximately sized with profile bobbin probe, but the size and shape can not be accurately verified. Accordingly, in this study, the $8{\times}1$ multi-array EC probe was designed to increase the measurement accuracy of the sectional profiling EC testing of tube. As a result, we would like to propose the application of $8{\times}1$ multi-array EC probe for the measurement of size and shape of profile change on steam generator tube in OPR-1000 nuclear power plant.