• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.363.2-363
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• 2001

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.621-626
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• 2003

A DUPIC nuclear fuel is a newly developed fuel for CANDU reactors based on the concept of refabrication of spent PWR fuel by a dry process. Because a spent PWR fuel, a highly radioactive material, is used as a starting material, the experimental verification of DUPIC nuclear fuel fabrication requires an appropriate facility which should satisfy engineering requirements and guarantees safe operation. DUPIC nuclear fuel development team modified M6 hot-cell in IMEF to construct the dedicated facility(DFDF) for tile experiment. The experiment with spent PWR fuel have been conducted since January of 2000. Environmental effects of DFDF normal operation have been investigated when DUPIC nuclear fuel is fabricated with the maximum capacity of 50kg U/yr. The analysis results of the radiological safety of DFDF facility have shown that both national regulation limit and IMEF design criteria are satisfied.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.168-171
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• 2003

The IMEF(Irradiated Materials Examination Facility), located in KAERI site, is a hot cell facility to test and evaluate the irradiation defects or embrittlement through post-irradiation examination(PIEs) of irradiated nuclear fuels and structural materials which are come from HANARO research reactor and commercial nuclear power plants. Therefore, to carry out its own function, the high level solid radioactive wastes, produced through PIEs, are periodically carried out and managed from hot cell to monolith. So far, approximately 30 drums which contains 50 liters are transported to monolith, and it is shown that the quantity is slowly increasing, In this paper, the procedures and work contents of the high level solid radwaste carrying out and management for IMEF are described in detail.

• Proceedings of the Korea Concrete Institute Conference
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• 2003.05a
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• pp.985-990
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• 2003

In order to demonstrate Advanced Spent Fuel Conditioning Process (ACP), shielding facilities such as hot cell suitable to handling radionuclides and process property will be necessary. But the construction of new facilities needs much money, man-power and time, it is now scheduled to remodel the hot cell, which has already been installed and maintained at Irradiated Material Experiment Facility (IMEF) in the Korea Atomic Energy Research Institute (KAERI). The basic structure and concrete shield wall of hot cell partly have been constructed on the base floor in IMEF building in current status. And hot cell after remodeling will be used for carrying out the lab-scale experiment of ACP. The hot cell was built in accordance with 35 curies of fe-59(1.2 MeV) as design criteria of radiation dose limit. But the radioactive source of ACP is expected to be much higher than design criteria of IMEF, shielding ability of the hot cell in the current status is unsatisfactory to the hot test of ACP. Therefore shield wall shall be reinforced with heavy concrete, steel or lead. In this paper, dose rates are calculated according to ACP source, shielding materials, etc., and reinforcement structures are determined considering the current situation of hot cells, installation of shield windows and the easiness of work.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.3
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• pp.155-164
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• 2004

Advanced spent fuel Conditioning Process(ACP) project which is under development for efficient spent fuel management has finished process feasibility study and is preparing $\alpha$-${\gamma}$ type hot cell construction for process experimentation. Radiation dose evaluation for the radioactive nuclides were preliminarily performed for normal operation and accident case with the basic concept design report, the meteorological data and the recent site specific data. According to the production and release rate of nuclides, dose evaluations for residents around facility were performed. The evaluation result shows a safe margin for regulation limits and SAR(Safety Analysis Report) limit of IMEF(Irradiated Material Examination Facility) where this facility will be constructed.

• Proceedings of the Korean Society of Precision Engineering Conference
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• 2003.06a
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• pp.1438-1441
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• 2003

The project for "Development of Advanced Spent Fuel Management Technology" has a plan of a demonstration for the Advanced Management Process in the hot cell of IMEF. The Advanced Management Process are being developed for efficient and safe management of spent fuels. For the demonstration, several devices which are used to safely transport and handle nuclear materials without scattering have been derived by analyzing the Advanced Management Process, object nuclear material and modules of process equipment and performing graphical simulation of transportation/handling by computers. For verification, powder transportation vessel and handling device have been designed and manufactured. And several tests such as transporting, grappling, rotating the vessel have been performed. Also, the design requirements of transportation/handling equipment have been analyzed based on test results and process studies. The developed design requirements in this research will be used as the design data for the Advanced Management Process.

• Proceedings of the Korean Nuclear Society Conference
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• 2002.10a
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• pp.297.2-297
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• 2002

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.1355-1356
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• 2004

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 1990.10a
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• pp.125-128
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• 1990

조사후 시험시설(Post Irradiated Examination Facility, PIEF)은 내진범주 1 급 구조물로서 현재 각종 실험 및 연구가 진행중인 원자력 안전관련시설물 이다. 한편 이 건물로부터 30m - 120m 정도 떨어져 있는 다목적연구로 (Korea Multipurpose Research Reactor, KMRR) 및 조사재시험시설 (Irradiation Material Examination Facility, IMEF)의 건조사업을 위하여 기 초암반의 굴착작업을 수행할 경우 발파작업에 따른 그 진동 및 폭풍압영향 이 염려되어, 그 안전성 평가를 위하여 시험발파를 수행해야 할 필요가 제기 되었다. 우선 운전중인 원자력안전 시설물에서의 발파에 따른 진동허용 기준 을 설정하고, 둘째로 거리에 따른 폭발량을 경험식에 따라 잠정 결정한 후, 세째로 시험발파에 의한 진동 측정을 수행하여 그 영향을 평가하고, 끝으로 이에 따라 거리별 제한 폭발량을 결정한후 실제 본발파에 적용하고자 한다. 이로써 운전중인 원자력 안전관련시설물인 PIEF의 안전 운전을 도모하고 KMRR및 IMEF 시설의 건조를 원만하게 이룰 수 있을 것이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.411-420
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• 2003

An advanced spent fuel conditioning process (ACP) is developing for the safe and effective management of spent fuels which arising from the domestic nuclear power plants. And its demonstration facility is under design. This facility will be prepared by modifying IMEF's reserve hot cell facility which reserved for future usage by considering the characteristics of ACP. This study presents a basic structural architecture design and analysis results of ACP hot cell including modification of the IMEF. The results of this study will be used for the detail design of ACP demonstration facility, and utilized as basic data for the licensing of the ACP facility.