• Title, Summary, Keyword: Remote dismantling system

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Evaluation Methodology of Remote Dismantling Equipment for Reactor Pressure Vessel in Decommissioning Project

  • Hyun, D.J.;Choi, B.S.;Jeong, K.S.;Lee, J.H.;Kim, G.H.;Moon, J.K.
    • Journal of Nuclear Fuel Cycle and Waste Technology
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    • v.1 no.1
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    • pp.83-92
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    • 2013
  • A novel methodology to evaluate remote dismantling equipment for a reactor pressure vessel (RPV) in a decommissioning project is presented in this paper. The remote dismantling equipment, mainly composed of cutting tools and positioning equipment, is absolutely required to cut and handle highly radioactive and large components in nuclear power plants (NPPs); this equipment has a great effect on the overall success of the decommissioning project. Conventional evaluation methods have only focused on cutting technologies or positioning equipment, although remote dismantling equipment cannot achieve its goal without organic interaction between the cutting tools and the positioning equipment. In this paper, the cutting tools and the positioning equipment are evaluated by performance parameters according to their original characteristics, the relationship between the two systems, and common factors. Finally, the remote dismantling equipment used in recent decommissioning projects has been evaluated based on the proposed methodology. The results of this paper are expected to be useful for future decommissioning projects.

Interactive graphic simulation of research nuclear reactor dismantling process (연구용원자로 원격해체공정의 그래픽 전산모사)

  • 박영수;윤지섭;오원진;홍순혁
    • 제어로봇시스템학회:학술대회논문집
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    • pp.848-851
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    • 1997
  • A graphic simulation program is developed to assimilate the remote dismantling process of research nuclear reactors. This program makes extensive use of a commercial robot graphic instruction program. Firstly, a realistic graphic model of research reactors are built along with various dismantling equipments. Using the graphic instruction languages provided by IGRIP, then, a graphic process simulation program is developed that operates interactively with the user. Consequently, it is made possible for a process designer to visualize an arbitrary dismantling sequence and interactively modify the process. It is expected that the developed system will be utilized as an effective operator aid in both design and execution phases of remote dismantling of research reactor.

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A Study of 3-Dimension Graphic Monitoring System for Spent Fuel Dismantling Process

  • Kim, Sung-Hyun;Song, Tae-Gil;Lee, Jong-Youl;Yoon, Ji-Sup
    • 제어로봇시스템학회:학술대회논문집
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    • pp.73.1-73
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    • 2001
  • To utilize the uranium resources contained in the spent nuclear fuel generated from the nuclear power plants, the remote handling and dismantling technology is required. The dismantling process of the sport fuel is the most common process involved in the spent fuel recycling, the rod consolidation and the disposal processes. Since the machine used in the dismantling process are located and operated in isolated space, so called a hot cell, the reliability of machines is very important. To enhance the reliability of the process, in this research, the graphical monitoring system is developed for the fuel dismantling process. The graphic model of each machine is composed of many parts and every parts of the graphic model are given their own kinematics. Using the kinematics and simulating the graphic model in the virtual environment, the validity of the conceptual design can be verified before ...

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Development of a shared remote control robot for aerial work in nuclear power plants

  • Shin, Hocheol;Jung, Seung Ho;Choi, You Rack;Kim, ChangHoi
    • Nuclear Engineering and Technology
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    • v.50 no.4
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    • pp.613-618
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    • 2018
  • We are developing a shared remote control mobile robot for aerial work in nuclear power plants (NPPs); a robot consists of a mobile platform, a telescopic mast, and a dual-arm slave with a working tool. It is used at a high location operating the manual operation mechanism of a fuel changer of a heavy water NPP. The robot system can cut/weld a pipe remotely in the case of an emergency or during the dismantling of the NPP. Owing to the challenging control mission considering limited human operator cognitive capability, some remote tasks require a shared control scheme, which demands systematic software design and integration. Therefore, we designed the architecture of the software systematically.

The Status and Prospect of Decommissioning Technology Development at KAERI (한국원자력연구원의 해체기술 개발 현황 및 향후 전망)

  • Moon, Jeikwon;Kim, Seonbyung;Choi, Wangkyu;Choi, Byungseon;Chung, Dongyong;Seo, Bumkyoung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.2
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    • pp.139-165
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    • 2019
  • The current status and prospect of decommissioning technology development at KAERI are reviewed here. Specifically, this review focuses on four key technologies: decontamination, remote dismantling, decommissioning waste treatments, and site remediation. The decontamination technologies described are component decontamination and system decontamination. A cutting method and a remote handling method together with a decommissioning simulation are described as remote dismantling technologies. Although there are various types of radioactive waste generated by decommissioning activities, this review focuses on the major types of waste, such as metal waste, concrete waste, and soil waste together with certain special types, such as high-level and high-salt liquid waste, organic mixed waste, and uranium complex waste, which are known to be difficult to treat. Finally, in a site remediation technology review, a measurement and safety evaluation related to site reuse and a site remediation technique are described.

Experiment on Cutting the SUS and Zircaloy Tubes by Cutter Blade (Cutter blade에 의한 SUS 및 지르칼로이 튜브 절단 실험)

  • 정재후;윤지섭;홍동희;김영환;박기용
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • pp.651-654
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    • 2001
  • In the dismantling process of nuclear spent fuels, the spent fuel rod cutting process, followed immediately by the decladding process, performs the cutting the spent fuel rods to a proper length for fast decladding operation. In this paper, we analyzed the chemical compositions, mechanical properties, and physical characteristics for SUS and zircaloy tubes in order to identify the feasibility of cutter-blade type in cutting SUS and zircaloy tubes. It is considered that material, shape and angle, and heat treatment for fabricating the highly durable cutter blade and also it is investigated that the round-shape sustenance of cross-section, amount of debris production, and fire occurrence for measuring the cutting performance on SUS and zircaloy tubes, spent fuel rod cutting device is designed to be operated automatically through the remote control system for use in Hot Cell(radioactive) area and the electro-driven mechanical parts are modularized for easy maintenance. Results from various experiments confirm the efficiency of this device.

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