• 한국광물학회지
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• 제15권2호
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• pp.140-144
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• 2002

한국원자력연구소의 연구용 원자로인 하나로에 설치되어 있는 4축 단결정 회절장치에서 사용할 수 있는 고온시료환경장치의 개발이 완료되었다. 이 장치를 이용하여 구조가 알려진 시료에 대해 고온실험을 수행함으로써 장치의 성능을 시험하였다. 이번 연구를 통하여 현재 개발된 고온시료환경장치가 900 K 이상의 고온에서 장시간의 실험에 안정함을 알 수 있었다. $LaTaO_3$단결정(상전이 온도 약 900 K)에 대해 상온과 913 K에서 중성자 회절실험을 수행하여 X-ray 회절실험으로는 정확한 위치를 측정하기 어려운 Li의 위치를 측정하였고 고온에서 Li 원자가 무질서 상태로 존재함을 확인하였다.

• 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.

• 비파괴검사학회지
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• 제21권5호
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• pp.561-564
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• 2001

연구로인 하나로의 핵연료봉은 제조 시 피복층에 품질 관리 절차에서 규정한 크기 이상의 결함이 없도록 와전류탐상 검사를 하도록 되어 있다. 와전류탐상검사 절차를 수립하기 위하여 외삽 차동형 와전류탐촉자 및 표준시험편을 제작하였다. 임피던스 분석기를 사용하여 제작된 탐촉자에 대한 임피던스값을 측정하여 검사주파수 영역에서 최대감도를 얻도록 제작되었는지를 조사하였고, 이 탐촉자 및 MIZ-40A 와전류탐상기를 사용하여, 요구되는 결함 크기를 검출할 수 있는가를 조사하였다. 그 결과 이 탐촉자를 사용하여 길이 2mm 피복 두께 대비 깊이 10%인 인공 노치를 검출할 수 있었으며, 연구로용 핵연료봉의 제조 시 피복층에 존재하는 결함을 성공적으로 검사할 수 있었다.

• Nuclear Engineering and Technology
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• 제40권5호
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• pp.409-418
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• 2008

Because the interaction layers that form between U-Mo particles and the Al matrix degrade the thermal properties of U-Mo/Al dispersion fuel, an investigation was undertaken of the undesirable feedback effect between an interaction layer growth and a centerline temperature increase for dispersion fuel. The radial temperature distribution due to interaction layer growth during irradiation was calculated iteratively in relation to changes in the volume fractions, the thermal conductivities of the constituents, and the oxide thickness with the burnup. The interaction layer growth, which is estimated on the basis of the temperature calculations, showed a reasonable agreement with the post-irradiation examination results of the U-Mo/Al dispersion fuel rods irradiated at the HANARO reactor. The U-Mo particle size was found to be a dominant factor that determined the fuel temperature during irradiation. Dispersion fuel with larger U-Mo particles revealed lower levels of both the interaction layer formation and the fuel temperature increase. The results confirm that the use of large U-Mo particles appears to be an effective way of mitigating the thermal degradation of U-Mo/Al dispersion fuel.

• 한국유체기계학회 논문집
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• 제5권4호
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• pp.26-31
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• 2002

The heat produced by the fission in the fuel of HANARO, 30 MW of research reactor, was transferred from the primary cooling water to the secondary cooling water through heat exchangers. The secondary cooling water absorbing the heat was circulated by secondary cooling pumps and cooled through 33 MW of cooling tower. Each capacity of the three secondary cooling pumps was fifty percent ($50\%$) of full load. The two pumps were normally operated and the other pump was standby. One of the secondary cooling pumps has often made troubles by high vibration. To release these troubles the pump shaft has been re-aligned, the pump bearing has been replaced with new one, the shaft sleeve has been replaced with new one, the shaft and the impeller have been re-balanced representatively and/or the vibration of motor has been tested by disconnecting the shaft of pump. But the high vibration of pump cannot be cleared. We find out the weight balance trouble of the assembly in which the impeller is installed in the shaft. After clearing the trouble, the high vibration is relieved and the pump is operated smoothly. In this paper, the trouble solution shooting method of secondary cooling pump is described including the reason of high vibration

• 유체기계공업학회:학술대회논문집
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• 유체기계공업학회 2001년도 유체기계 연구개발 발표회 논문집
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• pp.197-202
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• 2001

The heat produced by the fission in the fuel of HANARO, 30 MW of research reactor, was transferred from the primary cooling water to the secondary cooling water through heat exchangers. The secondary cooling water absorbed the heat was circulated by secondary cooling pumps and cooled through 33 MW of cooling tower. Each capacity of the three secondary cooling pumps was fifty percent ($50\%$) of full load. The two pumps were normally operated and the other pump was standby. One of the secondary cooling pumps has often get troubles by high vibration. To release these troubles the pump shaft has been re-aligned, the pump bearing has been replaced with new one, the shaft sleeve has been replaced with new one, the shaft and the impeller have been re-weight balanced representatively or the vibration of motor has been tested by disconnecting the shaft of pump. But the high vibration of pump cannot be cleared. We find out the weight balance trouble of the assembly that the impeller is installed in the shaft. After clearing the trouble, the high vibration is released and the pump is operated with smooth. In this paper the trouble solution of secondary cooling pump is described including the reason of high vibration.

• 한국의학물리학회:학술대회논문집
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• 한국의학물리학회 2006년도 제33회 추계학술대회 발표논문집
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• pp.131-131
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• 2006

• Nuclear Engineering and Technology
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• 제30권4호
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• pp.328-341
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• 1998

This paper presents in detail the hydraulic characteristic measurements using LDV(Laser Doppler Velocimetry) in subchannels of a HANARO, KAERI research reactor, fuel bundle. The fuel bundle consists of 18 axially finned rods with 3 spacer grids and has a cylindrical configuration. Axial velocity and turbulent intensity were measured. The effects of the spacer grids on the turbulent flow were investigated using the experimental results. Pressure drops for each component of the fuel bundle were measured, and the friction factors of the fuel bundle and the loss coefficients for the spacer grids were estimated from the measured pressure drops. The turbulent thermal mixing phenomena were discussed.

• 대한약학회:학술대회논문집
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• 대한약학회 2003년도 Proceedings of the Convention of the Pharmaceutical Society of Korea Vol.2-2
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• pp.105.1-105.1
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• 2003

The purpose of this study is to investigate the biological effects in black mouse by neutron irradiation at HANARO reactor in KAERI. Neutrons readily penetrate the charged field of an atomic nucleus because they are electrically neural. And so it can fight cancer with the radiation released when an atom of the element boron absorbs a neutron. The main patient in BNCT facility is brain cancer and sometimes skin cancer in foreign countries until now. Therefore, mice were laid flat and so irradiated at the direction of the front. (omitted)

• International Journal of Korean Welding Society
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• 제5권1호
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• pp.1-9
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• 2005

Multipass welds of 316L stainless steel have been widely employed to the pipes of Liquid Metal Reactors. Owing to localized heating and a subsequent rapid cooling by the welding process, residual stress arises in the weld of the pipe. In this study, the residual stresses in the 316L stainless steel pipe welds were calculated by the finite element method using the ANSYS code. Also, the residual stresses both on the surface and in the interior of the thickness were measured by the HRPD(High Resolution Powder Diffractometer) instrumented in the HANARO Reactor. The experimental data and the calculated results were compared and the characteristics of the distribution of the residual stress were discussed.