• 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.

• 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.

• Nuclear Engineering and Technology
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• v.41 no.6
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• pp.859-866
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• 2009

KAERI has worked on the development of an advanced spent fuel conditioning process (ACP) since 1997. A hot cell facility, termed the ACPF, has also been developed. The ACPF consists of two air-sealed hot cells. The results of a safety analysis as part of the license procurement process stipulated by the Korean Government showed that the facility was designed safely. After its construction, an integrated performance test was performed. The results of this test confirmed that the facility satisfies the design requirements.

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.295-296
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• 2005

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.331-336
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• 2003

The advanced spent fuel conditioning process(ACP) was proposed to reduce considerably the overall volume and radioactivity for effective management of the PWR spent fuel in respects on safety and economy. The ACP is under research and development, and have scheduled to perform hot test for demonstration of the ACP after several years. For hot test, hot cell facility of ${\alpha}{\gamma}$ type possess conservative safety is required essentially. A existing hot cell of ${\beta}{\gamma}$ type will be refurbished to minimize construction expenditures of hot cell facility. In this study, the design requirements are established, and the process detail work flow was analysed for the optimum arrangement to ensure effective process operation in hot cell. And also, the basic and detail design of hot cell facility and process and safety analysis was peformed to secure conservative safety of hot cell facility and process.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.596-600
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• 2003

The Advanced spent fuel Conditioning Process(ACP) is under development for the effective management of spent fuel which had been generated in nuclear plants. The ACP needs a hot cell where most operations will be peformed. To give priority to the environment safety, radiation doses evaluation for the radioactive nuclides were preliminarily peformed in both normal operation and accident case. The evaluation result shows a safe margin for regulation limits and SAR limit of IMEF where this facility will be constructed.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.306-315
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• 2004

A Bridge Transported Servo Manipulator (BTSM) for Advanced spent fuel Conditioning Process (ACP) has been developed to overcome the limitation of access that is a drawback of Mechanical master-slave manipulators (MSMs) for the equipment maintenance. Wire-driven mechanisms have been adopted to increase the handling capacity to weight. The main disadvantage of the wire driven mechanism is that if one link is in motion, other links can be affected because wires and links are coupled. In this paper, the relationship between pulleys and links are formiliarized to overcome this drawbacks, Derived equations are proven and analyzed through experiments.

• 제어로봇시스템학회:학술대회논문집
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• 2003.10a
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• pp.2514-2518
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• 2003

The KAERI Spent Fuel Remote Technology Development (SFRTD) Department is developing the remote maintenance and repair equipment, which is used in a hot cell in an intense radiation field, as part of a project to develop the Advanced spent fuel Conditioning Process (ACP). Although several mechanical master-slave manipulators (MSMs) is mounted on the hot cell wall, their reach will be limited and cannot access areas for all the ACP equipment maintenance. A Bridge Transported ServoManipulator (BTSM) has been designed to overcome the limitation of access areas that is a drawback of MSMs for the ACP equipment maintenance. The BTSM system consists of four components: a transporter with telescoping tubeset, a slave manipulator, a master manipulator, and a remote control system. The BTSM system has been designed by Solid Edge that is a 3D computer-aided design (CAD) software, except for the remote control system. The master manipulator and the slave manipulator are kinematically similar in design, except for the handle and the tong, respectively. The manipulators have 6 degrees of freedom (DOF) plus the jaws motion. The transporter has traveling, traverse, and hoisting motion to position the slave manipulator.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.349-349
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• 2004

차세대관리 종합공정(Advanced spent fuel Conditioning Process)은 사용후핵연료의 안전하고 효율적인 관리를 위하여 제시된 건식처리공정으로 사용후핵연료를 금속으로 전환하고, 고발열성 핵종(Cs, Sr)을 효율적으로 제거하여 사용후핵연료의 부피, 발열량 및 방사선의 세기를 최대 1/4까지 감소시키고, 처분용기의 소요량과 처분장의 소요면적을 1/2 이상으로 축소함으로서 처분 안전성과 경제성을 높일 수 있는 장점으로 인해 연구개발 중에 있으며, 이의 실증시험 수행을 위하여 ${\alpha}-{\gamma}$ type의 핫셀을 건설 중에 있다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.11b
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• pp.60-75
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• 2005

The remote operation of the Advanced Spent Fuel Conditioning Process (ACP) is analyzed by using the 3D graphic simulation tools. The ACP equipment operates in intense radiation fields as well as in a high temperature. Thus, the equipment should be designed in consideration of the remote handling and maintenance. As well as suitable remote handling and maintenance method needs to be provided. To provide such remote operation technology, we developed the graphic simulator which provides the capability of verifying the remote operability of the ACP without fabrication of the process equipment. In other words, by applying virtual reality to the remote maintenance operation, a remote operation task can be simulated in a computer, not in a real environment. In this way the graphic simulator can substantially reduce the design cost of the remote operation process and the equipment. Also it can provide new operation concept that is more reliable, easier to implement, and easier to understand.