• Title/Summary/Keyword: Dismantling System

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Simulation Based Conceptual Design of ELV Dismantling System (시뮬레이션 기반 폐자동차 해체시스템의 개념설계)

  • 손영태;표정호;박면웅
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 2003.06a
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    • pp.890-894
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    • 2003
  • This paper discuss basic functional construction and plant layout of a ELV dismantling system that can maximize the reusability of tarts and the recoverability of materials by dismantling ELV rationally and efficiently. "Island" type was selected for the system configuration considering processing amount, economical efficiency, and effectiveness. The system is supported by the information system, and composed of dismantling stations and handling equipments. The layout of the stations was determined after simulation and optimization using commercial software package, Arena and OptQuest. The objective of the optimization was maximum profit while the system capacity is considered as constraint. The environmental load of ELV can be minimized when the composition and function of each station are embodied in detail and the system is interfaced with shredding operation.

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The Actual State of Demolition and Pilot Dismantling in Apartment Building (해체공사의 수행실태 및 공동주택 분별해체 시험시공)

  • Kim, Hyo-Jin;Sohn, Jeong-Rak;Park, Seong-Sik;Yoon, Yung-Sang
    • Proceedings of the Korean Institute of Building Construction Conference
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    • 2007.04a
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    • pp.113-118
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    • 2007
  • Now a performance process of Demolition works is 'Before-Removal & After-Classification' method in Korea. This method is short of demolition time, but construction wastes contained substances lower recycling rate of construction, raise expenses of reclamation & treatment. Then the government has decided upon a positive 'Before-Classification & After-Removal' method, and substantially raise a recycling rate of construction wastes. Therefore, this study makes an investigation into state of internal and external demolition field through evaluating technological level, we make a proposal of dismantling method from there. Also, we put dismantling to the test in an apartment by proposed work process. As the result, it made a term of works increased for removing interior material. To solve this problem, we need to develop tools and methods of construction that can remove efficiently. From now on, we continuously need to study a breakdown system of dismantling, analysis of dismantling process and general system by inspecting entire demolition process. And we have to study details for making a specific thesis of method of removing interior material which was based on developing a suitable partial demolition machine and dismantling works.

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A Development of Simulation Model for End-of-Life Vehicle Dismantling System (폐자동차 해체시스템을 위한 시뮬레이션 모형 개발)

  • Sohn, Young-Tae;Lim, Seok-Jin;Park, Myon-Woong
    • Journal of the Korea Safety Management & Science
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    • v.12 no.3
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    • pp.327-332
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    • 2010
  • It is necessary that End-of-life Vehicle (ELV) should be recycled from the point of view of environmental preservation and resource recycling. This paper deals with two issues. The first one is the basic functional construction and plant layout of the ELV dismantling system that can maximize the reusability of parts and the recyclability of materials. The second issue is the development of a simulation model which can be used to estimate the performance of the layout design. The simulator has been interfaced with an interactive layout design system, and used to effectively determine an optimal layout design of the ELV dismantling system.

A Study on Estimation of Radiation Exposure Dose During Dismantling of RCS Piping in Decommissioning Nuclear Power Plant

  • Lee, Taewoong;Jo, Seongmin;Park, Sunkyu;Kim, Nakjeom;Kim, Kichul;Park, Seongjun;Yoon, Changyeon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.19 no.2
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    • pp.243-253
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    • 2021
  • In the dismantling process of a reactor coolant system (RCS) piping, a radiation protection plan should be established to minimize the radiation exposure doses of dismantling workers. Hence, it is necessary to estimate the individual effective dose in the RCS piping dismantling process when decommissioning a nuclear power plant. In this study, the radiation exposure doses of the dismantling workers at different positions was estimated using the MicroShield dose assessment program based on the NUREG/CR-1595 report. The individual effective dose, which is the sum of the effective dose to each tissue considering the working time, was used to estimate the radiation exposure dose. The estimations of the simulation results for all RCS piping dismantling tasks satisfied the dose limits prescribed by the ICRP-60 report. In dismantling the RCS piping of the Kori-1 or Wolsong-1 units in South Korea, the estimation and reduction method for the radiation exposure dose, and the simulated results of this study can be used to implement the radiation safety for optimal dismantling by providing information on the radiation exposure doses of the dismantling workers.

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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    • 2001.10a
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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 AND EVALUATION OF A TEMPORARY PLACEMENT AND CONVEYANCE OPERATION SIMULATION SYSTEM USING AUGMENTED REALITY

  • Yan, Weida;Aoyama, Shuhei;Ishii, Hirotake;Shimoda, Hiroshi;Sang, Tran T.;Inge, Solhaug Lars;Lygren, Toppe Aleksander;Terje, Johnsen;Izumi, Masanori
    • Nuclear Engineering and Technology
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    • v.44 no.5
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    • pp.507-522
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    • 2012
  • When decommissioning a nuclear power plant, it is difficult to make an appropriate plan to ensure sufficient space for temporary placement and conveyance operations of dismantling targets. This paper describes a system to support temporary placement and conveyance operations using augmented reality (AR). The system employs a laser range scanner to measure the three-dimensional (3D) information of the environment and a dismantling target to produce 3D surface polygon models. Then, the operator simulates temporary placement and conveyance operations using the system by manipulating the obtained 3D model of the dismantling target in the work field. Referring to the obtained 3D model of the environment, a possible collision between the dismantling target and the environment is detectable. Using AR, the collision position is presented intuitively. After field workers evaluated this system, the authors concluded that the system is feasible and acceptable to verify whether spaces for passage and temporary storage are sufficient for temporary placement and conveyance operations. For practical use in the future, some new functions must be added to improve the system. For example, it must be possible for multiple workers to use the system simultaneously by sharing the view of dismantling work.

Analysis of Collapse Accidents in Demolition Work using AcciMap and STAMP (AcciMap과 STAMP를 활용한 해체공사 붕괴사고 분석)

  • Hyeon-Ji Jeong;Jeong-Hun Won
    • Journal of the Korean Society of Safety
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    • v.38 no.3
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    • pp.51-60
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    • 2023
  • Investigation of the cause of the relatively recent building collapse accident in Gwangju revealed a lack of awareness about the safety of the dismantling construction system among stakeholders, in the form of issues such as illegal subcontracting, unauthorized design changes, and insufficient safety supervision. This study was conducted to analyze the safety interactions between the building dismantling construction system and the involved stakeholders and to propose ways to prevent accidents in related institutions and workplaces. AcciMap and STAMP-CAST analysis methods were used to evaluate safety interactions among the various stakeholders participating in building demolition work. Analysis results revealed that the collapse accident during the dismantling work was caused not only by structural causes occurring in the construction stage, but also by various causes throughout the system, such as the dismantling plan preparation stage and the construction permit stage. The results also revealed the need for proper implementation of safety control measures by various stakeholders to prevent collapse accidents during dismantling construction.

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

  • 박영수;윤지섭;오원진;홍순혁
    • 제어로봇시스템학회:학술대회논문집
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    • 1997.10a
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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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Development of an information reference system using reconstruction models of nuclear power plants

  • Harazono, Yuki;Kimura, Taro;Ishii, Hirotake;Shimoda, Hiroshi;Kouda, Yuya
    • Nuclear Engineering and Technology
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    • v.50 no.4
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    • pp.606-612
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    • 2018
  • Many nuclear power plants in Japan are approaching the end of their planned operational life spans. They must be decommissioned safely in the near future. Using augmented reality (AR), workers can intuitively understand information related to decommissioning work. Three-dimensional (work-site) reconstruction models of dismantling fields are useful for workers to observe the conditions of dismantling field situations without visiting the actual fields. This study, based on AR and work-site reconstruction models, developed and evaluated an information reference system. The evaluation consists of questionnaires and interview surveys administered to six nuclear power plant workers who used this system, along with a scenario. Results highlight the possibility of reducing time and mitigating mistakes in dismantling fields. Results also show the ease of referring to information in dismantling fields. Nevertheless, it is apparently difficult for workers to build reconstruction models of dismantling fields independently.

Implementation of an Architecture for the Dismantling Digital Mock-up System (해체 디지털목업시스템 아키텍쳐 구현)

  • Park Hee-Seoung;Kim Sung-Kyun;Lee Kune-Woo;Oh Won-Jin
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.3
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    • pp.237-247
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    • 2005
  • It is necessary to forecast the various dismantling activities prior to dismantling nuclear facilities by using various software instead of a physical mock-up system because the dismantling in a contaminated with radioactivity cause the results of an unexpected situation. The component that needs to develop a dismantling mock-up system was examined. There are many component systems such as a decommissioning database system,3D dosimetric mapping that represents a distribution of a radionuclide contamination, a component of modeling for nuclear facility and devices include the decontamination and decommissioning. The research of software architecture about these components was carried out because these component systems that have been independently doesn't describe not only to visual an activities of Decontamination and Decommissioning(D&D) but also to evaluate it. The result was established an architecture that consist of an visualization module which could be visualized an D&D activities and a simulation module which can be evaluated a dismantling schedule and decommissioning cost.

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