• 대한기계학회논문집A
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• 제38권4호
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• pp.443-449
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• 2014

조사시험 도중 핵연료의 특성변화를 확인하기 위하여 원자로 수조내에 위치한 조사리그로부터 핵연료봉을 분리한 후 핫셀로 이송하여 중간검사를 진행한다. 또한 중간검사를 마친 핵연료봉은 원자로의 작업 수조로 이동시켜 조사리그에 재장착을 하게 되며, 재조립된 조사리그는 원자로 노심의 조사리그에 장착시켜 조사시험을 계속 진행한다. 그러나 중성자 조사가 진행된 핵연료봉은 높은 에너지의 방사선을 방출하기 때문에 작업자가 방사선에 피폭되지 않게 하기 위하여 핵연료봉 장탈착 공정은 원자로 작업수조수 내에서 이루어져야 한다. 특히 조사리그의 길이가 5.4 미터이고, 핵연료봉의 장탈착 작업이 이루어질 하나로 작업수조수의 깊이는 6 미터로 매우 깊어 장탈착 작업을위한 특수한 장치가 필요하다. 본 연구에서는 중간검사가 가능한 새로운 핵연료봉 조립체를 설계하고, 조사 핵연료봉 조립체의 장탈착용 툴을 개발하여 노외 성능시험을 통해 그 성능을 검증하였다.

• Nuclear Engineering and Technology
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• 제44권7호
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• pp.735-744
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• 2012

In order to quantify the flow distribution characteristics of APR+ reactor, a test was performed on a test facility, ACOP ($\underline{A}$PR+ $\underline{C}$ore Flow & $\underline{P}$ressure Test Facility), having a length scale of 1/5 referring to the prototype plant. The major parameters are core inlet flow and outlet pressure distribution and sectional pressure drops along the major flow path inside reactor vessel. To preserve the flow characteristics of prototype plant, the test facility was designed based on a preservation of major flow path geometry. An Euler number is considered as primary dimensionless parameter, which is conserved with a 1/40.9 of Reynolds number scaling ratio. ACOP simplifies each fuel assembly into a hydraulic simulator having the same axial flow resistance and lateral cross flow characteristics. In order to supply boundary condition to estimate thermal margins of the reactor, the distribution of inlet core flow and core exit pressure were measured in each of 257 fuel assembly simulators. In total, 584 points of static pressure and differential pressures were measured with a limited number of differential pressure transmitters by developing a sequential operation system of valves. In the current study, reactor flow characteristics under the balanced four-cold leg flow conditions at each of the cold legs were quantified, which is a part of the test matrix composing the APR+ flow distribution test program. The final identification of the reactor flow distribution was obtained by ensemble averaging 15 independent test data. The details of the design of the test facility, experiment, and data analysis are included in the current paper.

• Korean Chemical Engineering Research
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• 제50권5호
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• pp.778-782
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• 2012

최근까지 대부분의 PEMFC MEA (Membrane and Electrode Assembly) 열화 연구는 전극과 전해질막 각각 분리되어 연구되었다. 그런데 실재 PEMFC 운전조건에서는 전극과 막은 동시에 열화된다. 그래서 본 연구에서는 전극과 막열화가 동시에 일어나는 조건에서 열화 가속시험을 하였다. 실험결과 전극과 막 열화가 서로 상호작용함을 보였다. 막열화는 촉매의 활성면적 감소폭을 줄였고, 전극열화는 막의 수소투과 전류와 불소유출속도(FER) 증가폭을 감소시켰다.

• 항공우주시스템공학회지
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• 제14권5호
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• pp.100-106
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• 2020

액체로켓엔진용 터보펌프는 작동 조건에서 캐비테이션 불안정성에 노출되며, 이는 터보펌프의 안정성에 영향을 미친다. 이를 확인하기 위해 터보펌프 조립체 시험 중 나타난 캐비테이션 불안정성의 특징을 살펴보았다. 시험 중 산화제펌프는 대표적인 캐비테이션 불안정성인 초조화 선회 캐비테이션과 부착 비대칭 캐비테이션에 노출되었다. 캐비테이션 불안정성이 발생되지 않는 조건에서 작동했던 연료펌프에서도 산화제펌프의 초조화 선회 캐비테이션에 의한 진동이 확인되었다.

• 한국산학기술학회논문지
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• 제14권5호
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• pp.2375-2380
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• 2013

본 연구에서는 디젤 차량용 통합형 연료히터 및 성능검사 시스템을 구현한다. 센서와 히터가 분리된 연료히터를 히터내에 센서를 안착시켜 통합함으로써 일체형 통합히터를 개발하고 성능평가시험 시스템 개발을 통하여 시험한다. 디젤 차량은 겨울철 저온환경의 영향을 받아 엔진이 냉각될 경우 일정한 온도 이하로 내려가면 파라핀과 같은 반고체 상태인 왁싱(Waxing)물질을 형성하여 엔진시동이 잘 걸리지 않게 하는 원인이 된다. 이러한 저온시동성을 지원하기 위해 연료히터를 사용하며, 연료히터의 성능을 평가하는 시험챔버가 필요하다. 시험챔버에서 연료히터의 성능검사 항목으로 상온, 극저온, 극고온에서의 동작검사, 시험저항 설정에 따른 저항동작지연시간 및 전류동작지연시간, 온도변화에 따른 바이메탈 지연시간 검사, 블록히터의 전류 및 저항 검사, 히팅 운전검사 등을 수행한다. 이때 연료히터의 시험평가 및 평가 알고리즘을 제시한다.

• 한국지반공학회:학술대회논문집
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• 한국지반공학회 2007년 가을학술발표회
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• pp.611-622
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• 2007

In the design and construction of the coastal/offshore structures, it is very important to evaluate the geotechnical characteristics of marine soils, which support the structures. Although the offshore site investigation is much more difficult than onshore, safe and precise jobs have not been accomplished in Korea because of the insufficiency of the test equipments especially for the site with deep water depth. The main objective of this study is to develop a new type of marine cone penetration testing(CPT) system, which can be utilized to even deep sea and high depth of soil layer. The system is one of seabed types and employs the conventional cone, which shows more reliable results than miniature cone. The most important parts of the marine CPT including continuous rod system, cone penetration system with wheel drive, automatic cone rod assembly/dissembly system etc., were designed and manufactured. Some tests to verify the developed marine CPT system were performed at both onshore and offshore sites as well as mechanical test in laboratory. The test results show the consistent and promising performance of the new equipment, and thereafter the system would be applicable to various sites with practical/economical advantages.

• 항공우주시스템공학회지
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• 제10권1호
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• pp.95-102
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• 2016

There are many possible disturbance sources on such a spacecraft, but reaction wheel assembly (RWA) which is generally used for spacecraft attitude control is anticipated to be the largest. These effects on degradation of performance of spacecraft such as attitude stability. In reaction wheel, disturbance caused by imbalance and speed error. It is hard to emulate speed error disturbance because it is not coincide with wheel frequency. This paper concentrates on emulating and analyzing the speed error disturbance. Firstly, classify the causes that lead to speed error disturbance which generate RPM fluctuation. Secondly, simulated with disturbance driver module and reaction wheel assembly which are developed by Spacecraft Control Lab. Experimental investigations have been carried out to test the disturbance emulator module as a disturbance generator for RWA. Measurements and test have been conducted on various fault. Frequency analysis of test data show that speed error disturbance effects on wheel settling wheel speed or fluctuation type.

• 소음진동
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• 제5권1호
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• pp.95-106
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• 1995

Flow-induced vibration in heat exchanger (or fuel rod) in nuclar power plant can cause dynamic interactions between tubes and tube supports resulting in fretting-wear. To increase the reliability and design life of heat exchanger components, design criteria that establish acceptable limits of vibration and minimize fretting wear are necessary. The fretting-wear rate is dependent upon material combination, contact configuration, environmental conditions and tube-to tube support dynamic interaction. It is demostrated that the fretting -wear rate correlates well with tube-to-support contact force or work rate. The tube-to-support dynamic interaction, which consists of dynamic contact forces and tube motion, is used to relate single-span wear data to real heat exchanger configurations consisting of multi-span tube bundles. This paper describes the test facility to measure tube-to-support dynamic impact force and reports its dynamic characteristics through the four impact tests - a force transduces independent and external impact tests, central ring inside impact test and additional cylinder impact test. Through the tests the impact parameter change dependent upon the material difference of impacting ball is studied, and the impact parameters of Force Transducer Assembly components are measured. And also the dynamic behavior of Force Transducer Assembly is analyzed. The force measurement technique herein is shown to provide a reasonable measure of dynamic contact forces.

• 한국추진공학회지
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• 제20권6호
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• pp.91-100
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• 2016

액체로켓엔진에 적용되는 원심형 터보펌프의 효율특성을 실험적으로 고찰하였다. 펌프 단품에 대한 시험결과를 토대로 터보펌프 조립체의 성능을 예측하면서 시험매질에 따른 펌프의 효율특성에 대한 변화를 분석하였다. 펌프에 적용된 작동유체로 단품시험을 위해서는 상온 청수와 액체질소, 터보펌프 조립체 시험에서는 케로신(Jet A-1)과 액체산소(LOX)가 적용되었다. 설계점과 탈설계점 영역을 포함하는 전반적인 작동조건에 대하여 펌프의 효율특성을 파악하였고, 단품시험으로부터 실매질 환경에서 보정된 펌프효율을 구할 수 있었다.

• Nuclear Engineering and Technology
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• 제55권8호
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• pp.2905-2918
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• 2023

The valve assembly used in nuclear power plants is important safety-related equipment. In the new standard, the physical attributes are measured using a valve diagnosis test, which is used in the expansion to other non-tested valves using a quantitative test-basis methodology. With a motor-operated actuator, the state of stem's lubrication is related to physical attributes such as the stem factor and the friction coefficient. This study analyzed the numerical transient of fluid and solid lubrication with a squeeze film effect due to the loading rate on the stem and the stem nut using the experimental data. The differential equation that governs the motion mechanism of the stem and stem nut is established and analyzed. The flow rate, the fluid and the solid contact forces are calculated with the friction coefficient. Finally, we found that a change in the friction coefficient results from a change of the shear force in the solid contact mode during the interchange process between the solid contact mode and the fluid contact mode. The qualitative understanding of the squeeze film effect is expanded quantitatively for forces, thread surface distance, velocity, and acceleration, with consideration of the metal solid contact and fluid contact.