• Nuclear Engineering and Technology
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• 제33권2호
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• pp.175-183
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• 2001

Various welding processes are now available for end cap closure of nuclear fuel element such as TG(Tungsten Inert Gas) welding, magnetic resistance welding and laser welding. Even though the resistance and TIG welding processes are widely used for manufacturing commercial fuel elements, they can not be recommended for the remote seal welding of a fuel element at a hot cell facility due to the complexity of electrode alignment, difficulity in the replacement of parts in the remote manner and a large heat input for a thin sheath. Therefore, the Nd:YAG laser system using optical fiber transmission was selected for Zircaloy-4 end cap welding inside hot cell. The laser welding apparatus was developed using a pulsed Nd:YAG laser of 500 watt average power with optical fiber transmission. The weldability of laser welding was satisfactory with respect to the microstructures and mechanical properties comparing with TIG and resistance welding. The optimum operation processes of laser welding and the optical fiber transmission system for hot cell operation in a remote manner have been developed The effects of irradiation on the properties of the laser apparatus were also being studied.

• 설비공학논문집
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• 제23권12호
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• pp.799-804
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• 2011

Radioactivity of high concentrations have existed in the handling nuclear materials in hot cell of PIEF(Post Irradiation Examination Facility). The exhaust filtration system was enabled to process cylindrical filters by using a manipulator in the hot cell. By establishing a double filtration system with two filters, backup protection against leakage or failure of the first is provided by the second filter. Additionally, this a arrangement is arrange intended to increase the total filtration efficiency. The result of the pressure drop changing in the air flow of the cylindrical and HEPA filters is observed by a curved line. A filtering efficiency of more than 99.99% to $0.3{\mu}m$ particle appears in the upstream and downstream during the efficiency test on the HEPA filters. The V-pleats type had a lower pressure drop than the separator type. There was no damage during usage and was found to be suitable with high capacity of air volume. Therefore, by carrying out performance tests of the exhaust filtration system, efficiency and safety can be achieved.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 춘계학술발표회
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• pp.501-502
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• 2005

During the cut and dismantling process of HANARO irradiated instrumented capsule(03M-06U), a little different phenomenon like a jamming was observed and occurred. So to release jamming between outer pipe and inner thermal media, the outer pipe will be cut piece by piece by capsule cutting machine installed in M2 hot cell until the outer pipe was eliminated or reduced as we could. It is assumed that this kind of problem was occurred following reasons: 1) This capsule has probably a problem during manufacturing process at shop before irradiation. 2) The gap between outer pipe and thermal media is not enough to meet design criteria for thermal expansion during irradiation at HANARO

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 2000년도 제15차 학술회의논문집
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• pp.415-415
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• 2000

The functions of a mobile robot such as obstacle knowledge and collision avoidance for in-door cleaning are necessary features, as has been much studied in the field of industrial automatic guided vehicle or general mobile robot. A mobile robot, in order to avoid collision with obstacles, has to gather data with environment knowledge sensors and recognize environment and the shape of obstacles from the data. In the study, a wall-following algorithm was suggested as a autonomous moving algorithm in which a mobile robot can recognize obstacles in indoor like environment and do cleaning work in effect. The system suggested in the study is for cleaning of nuclear material dusts generated in the process of nuclear fuel manufacturing and decontamination of devices in disorder which is performed in M6 radioactive ray shield hot-cell in IMEF(Irradiated Material Examination Facility) in the Korea Atomic Energy Research Institute.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 학술논문집
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• pp.133-134
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• 2004

DUPIC (Direct Use of spent PWR fuel In CANDU) fuel cycle technology is being developed at Korea Atomic Energy Research Institute (KAERI). All the DUPIC fuel fabrication processes are remotely conducted in the completely shielded M6 hot-cell located in the Irradiated Material Examination Facility (IMEF) at KAERI. Undesirable products such as spent nuclear fuel powder debris and contaminated wastes are inevitably created during the DUPIC nuclear fuel fabrication processes.(omitted)

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.621-626
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• 2003

핵비확산성 건식공정 산화물핵연료는 경수로 사용후핵연료를 재가공하여 원전에서 사용할 수 있는 핵연료로 재가공하는 개념으로, 이 실험은 고방사능 물질인 사용후핵연료를 초기물질로 사용하므로 고방사능 차폐시설인 핫셀 내에서 원격으로 조작되어야 하는 기술적 특성 때문에 이 실험은 적절한 공학적 요건과 안전성을 갖춘 전용시설(DFDF: DUPIC Fuel Fabrication Facility)을 구축하여 '00년 1월부터 실제 사용후핵연료를 사용한 실험을 수행하고 있다. DFDF에서 최대 약 50 ㎏U/yr의 사용후핵연료를 사용하여 건식공정 산화물핵연료 제조시험을 수행할 때 IMEF 시설의 방사선 환경영향에 미치는 영향을 검토하였다 분석한 결과 DFDF 시설의 운영으로 인한 영향은 모두 관련법규를 만족할 뿐 아니라 IMEF 시설의 설계기준도 만족하는 것으로 분석되었다.

• Nuclear Engineering and Technology
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• 제40권3호
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• pp.175-182
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• 2008

The results of process development for the blending of waste salt from the electrorefining of spent fuel with zeolite-A are presented. This blending is a key step in the ceramic waste process being used for treatment of EBR-II spent fuel and is accomplished using a high-temperature v-blender. A labscale system was used with non-radioactive surrogate salts to determine optimal particle size distributions and time at temperature. An engineering-scale system was then installed in the Hot Fuel Examination Facility hot cell and used to demonstrate blending of actual electrorefiner salt with zeolite. In those tests, it was shown that the results are still favorable with actinide-loaded salt and that batch size of this v-blender could be increased to a level consistent with efficient production operations for EBR-II spent fuel treatment. One technical challenge that remains for this technology is to mitigate the problem of material retention in the v-blender due to formation of caked patches of salt/zeolite on the inner v-blender walls.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2005년도 춘계학술대회 논문집
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• pp.1715-1718
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• 2005

During demonstrations of a process conditioning spent nuclear fuels, it may be necessary to transport and handle Spent fuel road cuts from Post Irradiation Examination facility to Slitting device in The hot cell. It may be not easy to transport spent fuel rod cuts because rod cuts are high radioactive materials. For this purpose, we have developed a capsule for transporting and handling high radioactive materials. We have analyzed conditions of a hot cell and requirements of the device, designed and manufactured The prototype of the device, and done some performance tests. From the tests, it has been shown that transportation and handling without scattering nuclear material was smooth but the weight of capsule was heavy. These result will be reflected to a design of the improved transportation and handling device which will be used during demonstrations.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.105-108
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• 2003

방사성 물질 취급시설인 핫셀을 출입하거나 핫셀 내의 장비 반출 등으로 인하여 핫셀 뒤편에 위치한 서비스 구역은 오염이 발생할 수 있다. 오염이 발생된 서비스 구역을 법령이 정한 표면허용오염도 이하로 제염 관리하기 위해서는 많은 방사성폐기물이 발생할 뿐만 아니라 제염하기 위한 소요인력 및 시간 또한 많이 요구된다. 이러한 문제점을 해소하기 위한 습식 제염장치는 부착된 오염원을 바닥 면으로부터 분리시키는 브러시를 회전시키는 부분, 회전브러시에 제염액 또는 세제를 공급하는 부분, 바닥 면에서 분리된 오염원과 제염액 또는 세제를 흡입하는 부분 그리고 주행하는 부분으로 구성되며, 스테인리스 재질로 제작하여 내부식성 뿐만 아니라 장치 자체의 제염도 쉽게 제작하여 조사후시험시설의 서비스 구역에서 제염장치의 성능시험을 수행하였다.

• 방사성폐기물학회지
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• 제2권3호
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• pp.155-164
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• 2004

사용후핵연료의 효율적인 관리를 위하여 원자력연구소에서 개발중인 사용후핵연료 차세대관리 종합공정(ACP)은 공정타당성연구 단계를 마치고 이의 실증을 위한 $\alpha$-${\gamma}$ type핫셀 건설 단계에 이르렀다. 핫셀의 설계에 앞서 사용후핵 연료를 취급하게 되는 과정에서 발생할 수 있는 방사능에 대한 환경영향평가를 정상운전 시와 사고발생 시로 나누어 수행하였다. 평가에 필요한 자료들은 공정의 개념설계 보고서와 최근 연구소부지 기상 테이터 및 부지특성 자료를 바탕으로 하였으며 기존의 유사한 시설에 대한 평가방법을 참조하였다. 각 핵종별 발생량과 방출량을 계산하여 피폭선량을 계산하였으며 평가결과 원자력법관련 규제기준과 핫셀이 위치하게 되는 IMEF 건물의 안전성분석 기준보다 매우 안전한 결과를 얻어 시설 운영에 대한 안전성을 확보하였다.