• Title/Summary/Keyword: 해체성

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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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Suggestion of Risk Assessment Methodology for Decommissioning of Nuclear Power Plant (원자력발전소 해체 위험도 평가 방법론 개발)

  • Park, ByeongIk;Kim, JuYoul;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.17 no.1
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    • pp.95-106
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    • 2019
  • The decommissioning of nuclear power plants should be prepared by quantitative and qualitative risk assessment. Radiological and non-radiological hazards arising during decommissioning activities must be assessed to ensure the safety of decommissioning workers and the public. Decommissioning experiences by U.S. operators have mainly focused on deterministic risk assessment, which is standardized by the U.S. Nuclear Regulatory commission (NRC) and focuses only on the consequences of risk. However, the International Atomic Energy Agency (IAEA) has suggested an alternative to the deterministic approach, called the risk matrix technique. The risk matrix technique considers both the consequence and likelihood of risk. In this study, decommissioning stages, processes, and activities are organized under a work breakdown structure. Potential accidents in the decommissioning process of NPPs are analyzed using the composite risk matrix to assess both radiological and non-radiological hazards. The levels of risk for all potential accidents considered by U.S. NPP operators who have performed decommissioning were estimated based on their consequences and likelihood of events.

PWR 16×16 사용후핵연료 집합체 해체장치 개념설계

  • Kim, Yeong-Hwan;Lee, Jae-Won;Lee, Han-Su;Park, Geun-Il;Lee, Jeong-Won;Jo, Gwang-Hun
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2012.10a
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    • pp.83-84
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    • 2012
  • SF 집합체 해체장치 개념설계요건 설정을 위해서 PWR $16{\times}16$ SF집합체 제원을 분석하였다. 또한 집합체 해체장치 주요요건을 도출하여 핵심메커니즘을 도출하였다. 주요요건은 다음과 같다. 집합체의 최대 clamping 힘은 각 grid의 경우: 240 kg, 하부노즐의 경우: 900 kg이다. 3 축 방향에서 절단을 위한 정확한 위치공자는 ${\pm}0.25mm$이다. 또한 처분을 위해 cuttings, fines 및 다양한 hardware를 수거하는 기능을 제공해야 한다. SF 집합체 해체를 위하여 드릴링 방식을 채택하였다. PWR SF의 종류에 따라 드릴링 위치가 다르기 때문에 위치제어와 해제장치 하단과 중간에 있는 X, Y, Z 제어를 할 수 있는 구조로 고안 하였다. SF 집합체 해체장치는 국내에서 가동되는 모든 PWR SF 집합체를 해체할 수 있는 구조로서 범용성을 가지고 있다. 원격 유지보수성을 향상하기 위하여 Solid Works 프로그램 툴(tool)을 이용하여 8개의 주요 모듈을 구성하였고, SF 집합체 해제장치 개념을 3D로 설계하였다.

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Technique to Evaluate Safety and Loaded Heavy Equipment Grade in RC Building during Demolition Work (RC건축물 해체공사의 안전성 평가기법 및 탑재장비 등급 제안)

  • Park, Seong-Sik;Lee, Bum-Sik;Kim, Hyo-Jin;Sohn, Chang-Hak
    • Land and Housing Review
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    • v.2 no.2
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    • pp.195-204
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    • 2011
  • During mechanical demolition of RC structures, weights of dismantling equipment and demolition waste of building are applied to unexpected load which did not be considered during the design of structural member. Nevertheless, the loading of dismantling equipment and dismantling process are mainly dependent on field managers' field workers' or experiences without considering safety of structural member by a structural engineer. It is urgently required that reflecting actual circumstance of mechanical demolition, safety evaluation method to evaluate the safety and the guideline for appropriate capacity of structural member to support dismantling equipment weight, be provided. Through site investigation and questionnaire on field workers, this paper proposed demolition waste load, load factor, strength reduction factor, and so on. These are essential to safe evaluation of a building, ready to demolition. Considering actual circumstance of mechanical demolition, safety evaluation method of building and design method of slab and beam was suggested to a dilapidated building. An capability to loading of dismantling equipment was proposed, applied to RC slab and RC beam. Therefore, the suggested safety evaluation method and the guideline for an capability to loading of dismantling equipment weight can reasonably evaluate the capacity of structural member in demolition and use effectively as increasing efficiency and improving safety of demolition through proper management of dismantling equipments.

해양플랜트 해체작업 통합관리용 시스템 개발 방향

  • Park, Yeong-Mo;Park, Wan-Sun
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • 2013.06a
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    • pp.551-553
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    • 2013
  • 노후 해양 플랜트 해체사장의 확대와 더불어 HLVs에 의존하고 있는 기존 해체 공법을 대체할 수 있는 새로운 통합관리 시스템의 개발이 요구되고 있다. IT 기술, ROV 운용기술, 구조물 건전성 모니터링 시스템 구축기술, 고성능 재료 개발 기술 등 국내에 확보되어 있는 기술들을 융합하여 노후 해양플랜트 해체작업을 종합적으로 관리, 진행할 수 있는 통합관리 시스템의 개발방향을 제시하였다.

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Preparation of Radiological Environmental Impact Assessment for the Decommissioning of Nuclear Power Plant in Korea (국내 원전 해체시 방사선환경영향평가 방안)

  • Lee, Sang-Ho;Seo, Hyung-Woo;Kim, Chang-Lak
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.1
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    • pp.107-122
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    • 2018
  • Kori unit 1, the oldest commercial nuclear power plant in South Korea, was permanently shut down in June 2017. There are a lot of things to consider in decommissioning nuclear power plants, and one of them is the radiological environmental impact assessment. Performed to promote the health and safety of residents around the nuclear power plant, radiological environmental impact assessment aims to confirm that off-site radiological dose from radioactive material released from the facility does not exceed the regulatory criteria. There are three main parts of environmental impact assessment: pre-decommissioning environmental monitoring, environmental monitoring during decommissioning, and impact on nearby residents. At present, although the Korea Nuclear Safety Act stipulates that radiological environmental impact assessment resulting from decommissioning should be carried out, the details have not been specified. Therefore, this paper compares and analyzes guidelines for evaluation of radiological environmental impacts of nuclear power plants overseas, and presents a draft on the assessment of radiological dose resulting from decommissioning according to the Korean situation.

Development of the draft guidelines of the decommissioning plan for a nuclear power plant in Korea (국내 원자로시설 해체계획서 세부 작성지침(안) 개발)

  • Lee, Jungmin;Moon, Joohyun
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.11 no.3
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    • pp.213-227
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    • 2013
  • It is essential to prepare the decommissioning plan for a nuclear power plant (NPP) for the safe decommissioning of the NPP, minimization of the generation of decommissioning wastes, and protection of human beings and environment. Although Kori unit 1 and Wolsong unit 1 will be destined to their decommissioning in Korea in the near future. there is no provisons about preparing the decommissioning plan. In this paper, therefore, the draft guidelines of the decommissioning plan for a NPP were developed by considering the domestic situation, based on the comparative analyses of the regulatory guidelines of the decommissioning plan in U.S., U.K. and France. The draft guidelines are expected to play an important role to modify the domestic laws and regulations on the decommissioning of the NPP, and to give a license holder in charge of decommissioning the detailed instructions for preparing it in advance.

QFD-Based Integrated Model of Dismantling Method Selection and FMEA Risk Assessment for Work Stage (QFD 기반의 해체공사 공법선정과 FMEA 위험성평가 통합 모델)

  • Lee, Hyung-Yong;Cho, Jae-Ho;Son, Bo-Sik;Chae, Myung-Jin;Kim, Hyun-Soo;Chun, Jae-Youl
    • Journal of the Korea Institute of Building Construction
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    • v.21 no.6
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    • pp.629-640
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    • 2021
  • According to statistics from the Ministry of Land, Infrastructure and Transport in 2018, approximately 37% of residential buildings in Korea need to be reconstructed. Due to the rapid growth of the demolition industry, many side effects such as environmental destruction and safety accidents are becoming a problem in the demolition of existing buildings. This study proposes a decision-making process for selecting the most suitable dismantling method for field application by comprehensively considering safety, economic feasibility, and environmental characteristics. In particular, field applicability is evaluated by evaluating risk factors for the selected method. To this end, this study proposes the TOPSIS method for the selection of the dismantling method using the QFD development concept, and the FMEA method as a continuous development process of the selected method.