• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.05a
• /
• pp.249.1-249
• /
• 2002

• Journal of the Korean Society for Nondestructive Testing
• /
• v.21 no.5
• /
• pp.561-564
• /
• 2001

The cladding area of HANARO Research Reactor fuel rods should be checked not to have any defects larger than the size required at QA documents by using eddy torrent testing method doting fabrication process. To apply eddy current testing inspection to the fuel rods, encircling differential probes and standard specimen were designed and fabricated. The impedance of the fabricated probes was measured with impedance analyzer in order to cheek that the probe has a suitable impedance for the inspection frequency, and with this probe and MIZ-40A eddy current equipment, the detectability of this probes was investigated. The developed probes could detect artificial notch with 2mm length 10% depth of cladding thickness in cladding area. In addition, the probe was successfully applied to detect the defects in cladding area doting fabrication of the research reactor rods.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.503-508
• /
• 1998

연구용원자로인 하나로(HANARO)에서 중성자 조사된 캡슐 및 핵연료다발을 절단 및 해체하기 위한 장비인 캡슐절단기를 개발하여 조사재시험시설(IMEF)의 M2 핫셀(hot cell)에 설치하였다. 재료 및 핵연료의 개발을 위해 하나로에서 조사되는 캡슐 및 핵연료다발의 절단 및 해체는 핵연료봉 및 캡슐내부에 내장되어 있는 시편에 손상 및 결함이 발생하지 않도록 하는 것이 매우 중요하며, 이러한 장비는 핫셀의 작업구역에서 원격조작기를 사용하여 원격으로 조작이 용이하도록 설계 및 제작되어야 한다. 이에 조사재시험시설에서 개발한 캡슐절단기는 가공물이 회전 및 좌우이송, 절단용 철이 회전 및 전후이송이 각각 되도록 하였고, 핫셀내에 설치하기 전에 가공에 필요한 최적의 조건을 설정하였다. 그리고 핫셀내 설치후 중성자에 조사되지 않은 하나로용 핵연료다발과 조사된 무계장캡슐을 건식상태로 절단 및 해체하여 장비 성능을 확인하였다.

• Nuclear Engineering and Technology
• /
• v.24 no.1
• /
• pp.40-51
• /
• 1992

One of the important irradiation performance characteristics of the silicide dispersion fuel element in research reactors is the diameteral increase resulting from fuel swelling. This paper, will attempt to develop a physical model for the fuel swelling, DFSWELL, by analyzing the basic irradiation behaviours and some experimental evidences. From the experimental evidences, it was shown that the volume changes in irradiated U$_3$Si-Al were strongly dependent on temperature and fission rate. The quantitative-amount of swelling for silicide fuel is estimated by considering temperature, fission rate, solid fission product build-up and gas bubble behavior. The swelling for the silicide fuel is comprised of three major components : i ) a volume change due to the formation of an interfacial layer between the fuel particle and matrix. ii ) a volume change due to the accumulation of gas bubble nucleation iii ) a volume change due to the accumulation of solid fission products The DFSWELL model which takes into account the above three major physical components predicts well the absolute magnitude of silicide fuel swelling in accordance with the power histories in comparison with the experimental data.