• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.24-31
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• 2004

In order to decommission safely nuclear power plant, it is necessary for the procedure of residual radioactivity investigation in site to provide detailed guidance for planning, implementing, and evaluating environmental and facility radiological surveys conducted to demonstrate compliance with a dose or risk-based regulation. This study presents the procedure of residual radioactivity investigation in decommissioning site - Historical Site Assessment, Scoping Survey, characterization Survey, Remedial Action Support Survey, Final Status Survey - on the basis of MARSSIM(Multi-Agency Radiation Survey and Site Investigation Manual) and investigation cases of decommissioned or decommissioning nuclear power plant.

• Annual Conference of KIPS
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• 2010.11a
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• pp.28-30
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• 2010

원자력시설의 해체 계획을 수립하는데 해체 대상 시설의 성격을 조사하고 파악하는 것은 매우 중요하다. 해체 대상 원자력시설의 특성자료 조사 결과는 해체 페기물의 양을 예측하고, 해체 사업의 비용 산정에 크게 활용이 된다. 이를 목적으로 해체사업 대상 시설의 특성 자료를 관리하는 컴퓨터 시스템인 해체시설 특성 관리시스템, DEFACS (${\underline{DE}}commissioning$ ${\underline{FA}}cility$ ${\underline{C}}haracterization$ DB ${\underline{S}}ystem$)를 개발하였다.

• Journal of Software Engineering Society
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• v.25 no.1
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• pp.11-18
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• 2012

Characteristic of decommissioning target facility investigate and understand is very important. because radioactive materials occurs in the decommissioning and dismantling, so it is difficult to use a general dismantling method. Decommissioning nuclear facilities, the characteristics of the target of research to predict the amount of decommissioning waste, decommission projects costing is largely utilized. For this purpose, we developed DEFACS(Decommissioning Facility Characterization DB System) that manage characteristic of decommissioning target facility. But nuclear facility decommissioning takes long time. so we inevitably developed system during decommissioning works, it occurs many system changes. For this reason, it is difficult to apply general development process, so we take CBD process that divide CD(Component Development) and CBSD(Component Based Software Development) for handling change of requirement. it make Component of the overall system for changes to minimize changes by strengthening the independence of components and processes due to changes in requirements were to minimize stopping of the process.

• Proceedings of the Korean Nuclear Society Conference
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• 1998.05b
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• pp.503-508
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• 1998

연구용원자로인 하나로(HANARO)에서 중성자 조사된 캡슐 및 핵연료다발을 절단 및 해체하기 위한 장비인 캡슐절단기를 개발하여 조사재시험시설(IMEF)의 M2 핫셀(hot cell)에 설치하였다. 재료 및 핵연료의 개발을 위해 하나로에서 조사되는 캡슐 및 핵연료다발의 절단 및 해체는 핵연료봉 및 캡슐내부에 내장되어 있는 시편에 손상 및 결함이 발생하지 않도록 하는 것이 매우 중요하며, 이러한 장비는 핫셀의 작업구역에서 원격조작기를 사용하여 원격으로 조작이 용이하도록 설계 및 제작되어야 한다. 이에 조사재시험시설에서 개발한 캡슐절단기는 가공물이 회전 및 좌우이송, 절단용 철이 회전 및 전후이송이 각각 되도록 하였고, 핫셀내에 설치하기 전에 가공에 필요한 최적의 조건을 설정하였다. 그리고 핫셀내 설치후 중성자에 조사되지 않은 하나로용 핵연료다발과 조사된 무계장캡슐을 건식상태로 절단 및 해체하여 장비 성능을 확인하였다.

• Journal of the Society of Disaster Information
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• v.17 no.3
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• pp.579-588
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• 2021

Purpose: The purpose of this study is to analyze how the participating companies related to asbestos dismantling affect the safety of residents near asbestos dismantling worksites, and to present important criteria for selecting asbestos dismantling related companies based on the analysis results. Method: In this study, based on the Occupational Safety and Health Act and the Asbestos Safety Management Act, important items about participating companies related to asbestos dismantling and the safety of residents near the asbestos dismantling workshop were derived, and then questionnaire items were determined through FGI. Multiple regression analysis was performed to analyze the influence relationship. Result: In order to secure the safety around the asbestos dismantling site, it was confirmed that the ability of asbestos dismantling supervisors among the participating companies (dismantling companies, investigation agencies, and supervisors) had the greatest influence. Conclusion: It showed that it is essential to select an excellent asbestos dismantling supervisor and an excellent asbestos dismantling and removal company in order to ensure the safety of residents near the asbestos dismantling site.

• Journal of the Korean Recycled Construction Resources Institute
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• v.4 no.1
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• pp.101-109
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• 2009

This CW(Construction wastes) are increasing as construction industry is growing, so many countries make efforts to recycle CW. Korea also made a stipulation for recycling CW. But the main content of this stipulation is for using recycled aggregates. Advanced countries try to increase reuse rate of not only recycled aggregate but also other kinds of wastes. So they are adopting SDM(separating dismantlement) method and we are also planning to make the system for SDM. This study is about SDM analysis through construction field investigation and difference analysis between SDM and UDM comparing predictive amount by UDM with real generated amount by SDM. First, the generated amount of construction wastes by SDM is more than estimated amount by UDM, and mixed waste was specially reduced more than UDM. The warehouse is easier than the office building to applicate SDM. But still there is no manual for SDM in the site, so establishment of SDM is demanded.

• Proceedings of the Korean Society of Disaster Information Conference
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• 2022.10a
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• pp.309-310
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• 2022

본 논문은 3차원 ELS 모델과 건설 프로젝트 관리 프로그램을 이용한 해체 공정을 기계식공법으로 해체하는 구조물에 적용한 사례이다. 해체 공정 설계를 위한 3차원 ELS 모델은 도면 및 현장 조사 통해 부재별 크기와 배근 정보를 확인하여 모델링하였다. 완성된 3차원 모델을 건설 프로젝트 관리 프로그램인 Bexel manager에 적용하여 부재 별 해체 공정을 설계하였다. 설계된 해체 공정은 기계식공법으로 해체하는 구조물에 적용하였고, 해체결과 작업 별 작업동선을 효과적으로 관리할 수 있었으며, 안전하게 해체를 완료하였다.

• KSCE Journal of Civil and Environmental Engineering Research
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• v.30 no.2D
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• pp.143-151
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• 2010

Currently, one of the most interested things at home and abroad country will be an eco-friendly construction. Among these, one of the most important elements will be the recycle and reuse of construction and demolition waste. Because construction waste is generated the most at the demolition phase, it is important to minimize the quantity of the demolition waste at the phase. And it is also important to develop a system to manage rightly the generated demolition waste. But in the domestic country, a research for this has hardly been carried out. In recent, the government has realized its importance and is making a research to improve demolition technique and is preparing a research to make a raw for deconstruction. Therefore, this study examined its application situation and importance by analyzing the trend of demolition technique used in the domestic industry. Also this study carried out a survey for situation analysis of the demolition industry. This study suggested items needed for the development of demolition technique, demolition design and reduction of C&D waste through a survey results and a situation analysis.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.14 no.3
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• pp.267-277
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• 2016

For the decommissioning of a nuclear power plant, a site characterization and final status survey require a site-specific suite of radionuclides that could potentially still be present in the site during or after the decontamination processes. The United States Nuclear Regulatory Commission (U.S. NRC) requires a Decommissioning Technical Base Document (DTBD) along with a Site Characterization and Historical Site Assessment (HSA) from the utility for decommissioning to proceed. Both the DTBD and HSA are preliminary components of the Radiological Site Survey investigation process and should be included in the final License Termination Plan (LTP) for site release and reuse consideration from the U.S. NRC and the utility company. This study reviews the United States Nuclear Power Plants (U.S. NPPs) decommissioning cases and is especially focused on the methodologies used for determining a site-specific suite of radionuclides before and during the site characterization and final status surveys. In 2017, Kori-1 will be ready for decommissioning and related preparations are ongoing, this review will help Korea to prepare regulatory guidelines and give technical background for the safe and successful decommissioning of NPPs.

• Annual Conference of KIPS
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• 2006.11a
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• pp.299-302
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• 2006

연구로 및 원자력 시설의 해체 공정 절차 수립과 해체 시나리오 선정에 기초 자료를 제공하고자 컴퓨터 그래픽스를 응용한 방사화 분포 가시화 연구가 수행되었다. 해체 전 시료 채취와 핵종 분석을 통해 방사능 자료가 확보된 연구로 2 호기 조사실(Exposure Room)과 조사실 주변의 콘크리트 차폐체(Concrete Shielding)를 대상으로 방사화 분포 가시화 실험이 이루어졌다. $^{60}Co$에 오염된 조사실의 벽면과 콘크리트 차폐체의 깊이 별로 조사된 방사능 농도 값을 기초로하여 이들 구조물을 3 차원으로 모델링 한 후 Contour mapping을 수행하여 방사화 분포 가시화를 완료하였다. 방사능 정도를 가시화 한 결과와 콘크리트 차폐체 깊이에 따라 지수 함수적으로 감소하고 있었던 결과가 잘 일치하고 있음을 확인할 수 있었다. 연구 결과 자료는 향후 해체 활동 중 방사선에 노출되는 작업자의 피폭선량 평가 모델에 중요한 역할을 수행할 것이다.