• 한국재난정보학회 논문집
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• 제17권3호
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• pp.579-588
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• 2021

연구목적: 석면해체 참여업체가 작업장 인근 주민 안전에 어떠한 영향을 미치는지 분석하고, 분석결과를 바탕으로 석면해체 참여업체의 선정에 있어서 중요 기준을 제시하는 데 목적이 있다. 연구방법: 본 연구에서는 산업안전보건법과 석면안전관리법을 토대로 석면해체 관련 참여업체와 석면해체 작업장 인근 주민 안전에 관한 중요항목을 도출한 후 FGI를 통하여 설문항목을 결정하였고, 영향관계 분석을 위해 다중회귀분석을 실시하였다. 연구결과: 안전한 석면해체 작업장 주변을 조성하기 위해서는 석면해체 관련 참여업체(석면해체·제거업자, 석면조사기관, 석면해체작업감리인) 중 석면해체작업감리인의 역량이 영향관계가 가장 큰 것으로 확인되었다. 결론:석면해체 작업장 인근 주민의 안전을 확보하기 위해서는 우수한 석면해체작업감리인과 우수한 석면해체·제거업자의 선정이 필수적임을 보여 주었다.

• Ocean Systems Engineering
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• 제13권1호
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• pp.79-95
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• 2023

An onshore dismantling yard is an important part in the supply chain of the offshore oil and gas decommissioning industry. However, despite having more than 500 offshore structures to be decommissioned in the Southeast Asia region, there are a very limited number of well-equipped dismantling yards to fully execute the onshore dismantling. Recent investigations discovered that shipbuilding and offshore structure fabrication yards are still potential options for upgrades to include dismantling. Despite the huge potential opportunities from upgrading to dismantling, research studies on this area are relatively scarce, and most past studies mainly focused on the North Sea region. To date, the potential opportunities of Southeast Asia and Malaysia yards to develop onshore dismantling capability are still unclear. The aim of this study is to identify the criteria to develop a technical preparedness checklist to evaluate an onshore dismantling yard; consequently, this will assist with assessing and bridging the gaps and identify the opportunity of developing an onshore dismantling yard in Southeast Asia region. Requirements for onshore dismantling and related rules and regulations have been investigated and summarized in the form of checklist. Findings from this study can help local oil and gas operators to pursue more local solutions and resilient supply chain performance.

• 도시과학
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• 제10권1호
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• pp.29-37
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• 2021

The number of old buildings older than 30 years in Korea continues to increase from 29.9% in 2005 to 38.8% in 2020. Considering the growing urban regeneration projects, urban maintenance projects, the suppression of urban expansion, and the lack of idle land in the city, the dismantling of old buildings is expected to increase further in the future. As major accidents at building dismantling sites continue to occur, related agencies are also strengthening safety management of building dismantling works. While physical safety management such as collapse and fall is strengthened, there is a relative lack of interest in the health of workers at dismantling sites due to environmental hazards. Since relevant laws stipulate that construction waste should be separated and discharged, old buildings need to be considered for environmental hazards such as fine dust, floating bacteria, and floating molds when dismantling. In this study, we intend to find important safety management elements in the management of building dismantling sites, measure environmental factors harmful to dismantling workers, and present basic data for the management of dismantling sites in the future. "Safety management" was the highest priority, followed by "dust," "vibration," "noise," "bacteria," and "smell." The perception of the importance of "physical damage prevention" with workers working on dismantling and managers managing the site came out similar, but the perception of "work efficiency" and "health disorder prevention" through environmental hazard management showed different priorities. In the process of dismantling, floating bacteria and floating mold were collected, cultured, and measured the concentration in the indoor air. The measurement was measured by dividing it into pre-dismantling and during dismantling.

• 방사성폐기물학회지
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• 제19권2호
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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.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2021년도 봄 학술논문 발표대회
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• pp.313-314
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• 2021

An old building over 30 years old continue to increase. Therefore, there will be more dismantling of old buildings in the future. Safety management of dismantling works is being strengthened. However, no consideration has been given to the effects of dismantling workers and their residents due to environmental hazards arising from the demolition process. Only spray and dust prevention measures are subject to inspection to minimize dust generation considering civil complaints around the site of dismantling work. In this paper, residential buildings, which account for the largest proportion of old buildings, were collected and identify total airborne bacteria and floating fungi among environmental hazards caused by non-structural dismantling work. Measurement results showed that workers during dismantling work are working in places with 4.8 times more total airborne bacteria than indoor air quality maintenance standards. Related research is needed for the health of dismantling workers.

• Nuclear Engineering and Technology
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• 제55권1호
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• pp.45-51
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• 2023

During the operation of a nuclear power plant (NPP), the waste reactor vessel closure head (RVCH) that is replaced owing to design or manufacturing defects is buried in a designated area or temporarily stored in a radiation shielding facility within the NPP. In such cases, storing it for extended periods proves a challenge owing to space constraints in the power plant and a safety risk associated with radiation exposure; therefore, dismantling it quickly and safely is crucial. However, not much research has been done on the dismantling of the RVCH in an operational power plant. This study proposes a dismantling process based on the radioactive contamination level measured for the Kori #1 RVCH, which is currently being discarded and stored, and examines the decontamination and cutting according to this process. In addition, the amount of secondary waste and dismantling cost are evaluated, and the dismantling effect of the reactor closure head is analyzed.

• 제어로봇시스템학회:학술대회논문집
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• 제어로봇시스템학회 1997년도 한국자동제어학술회의논문집; 한국전력공사 서울연수원; 17-18 Oct. 1997
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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.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.114-129
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• 2004

The 3D simulations for the Rotary Specimen Rack (RSR), the shielding concret, and the reactor core dismantling processes in the Korea Research Reactor-1&2(KRR-1&2) were carried out in the present work. The four main dismantling items, which are the RSR, reactor core, beam tube, and the thermal column and the shield concrete, were selected among the many components in the KRR-2 by consideration of the activation, worker training, difficulty of the work and so on. On the basis of these, we built 3D CAD models, selected the proper dismantling technologies, and reviewed their dismantling processes. In this study, the 3D simulation results of the shielding concrete, and the reactor core dismantling processes are also presented and discussed.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2003년도 춘계학술대회 논문집
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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.

• 자원리싸이클링
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• 제30권2호
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• pp.24-30
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• 2021

폐인쇄회로기판으로부터 부품을 분리하기 위하여 4가 주석이온 (Sn4+)을 포함한 염산용액을 이용하여 탈착실험을 진행하고, 부품탈착에 대한 교반속도, 반응온도, 4가 주석이온농도, 염산용액농도의 영향을 조사하였다. 100 rpm~300 rpm의 교반속도에서 PCB로부터 부품의 탈착속도는 큰 차이가 없었으며, 반응온도, 4가 주석이온농도, 그리고 염산용액농도를 증가시킴에 따라 탈착속도도 증가하였다. 모든 부품 탈착실험에서 탈착율이 100%에 도달하였을 때 기판에서 솔더는 관찰되지 않았으며 주석농도는 약 1,500 mg/L였다. 10,000 mg/L의 4가 주석이온을 포함한 1 mol/L의 염산용액에 폐하드디스크 PCB 1개를 투입하고, 교반속도와 반응온도를 각각 200 rpm과 90 ℃로 조정한 탈착실험에서 PCB로부터 부품의 탈착은 2시간만에 100% 완료되었다.