• Explosives and Blasting
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• v.25 no.2
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• pp.47-60
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• 2007

The blast demolition technology has been used to demolish various industrial facilities and tall buildings since 1950s in the advanced countries such as USA and U.K. It is now considered as one of safe demolition methods in the above countries. In Korea, several companies have tried to introduce blast demolition technology in the early days of the 1990s. However, this technology is still at the beginning stage and not fully adopted due to situation of avoiding technology transfer by overseas technical tie-up companies, lack of objects to be demolished and low level recognition on blast demolition. This technology shall be considered as a cutting edge technology to be applicable to demolition of skyscrapers, various industrial structures and factory buildings in the near future. Blast demolition of a pier structure was carried out under the site condition where there were already the constructed 2 pier structures of up and down line which had safety problems in an expressway construction project. The pier structures need to be demolished and reconstructed for a short period of time in consideration of the construction work process to be followed.

• 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.

• Journal of the Korea Institute of Building Construction
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• v.18 no.5
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• pp.499-506
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• 2018

The number of demolition work is rapidly increasing because the middle- and high-rised buildings constructed over the rapid industrialization and urbanization have been deteriorated in social and structural aspects. However, theoretical approaches or studies related to the demolition cost prediction are still insufficient. Thus, this study derived and analyzed important factors affecting the fluctuation of the building demolition costs. 14 factors was derived through literature reviews and experts' interview, and the importance of each factor was analyzed to the each work(temporary work, structure demolition, and waste disposal) and the entire demolition work by using descriptive analysis. The survey results showed that the demolition costs was greatly influenced by environmental properties of the site. The results of this study can be used as a basis for estimating the approximate cost of the demolition work.

• Proceedings of the Korean Institute of Surface Engineering Conference
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• 2017.05a
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• pp.136-136
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• 2017

화학제염 기술은 산화제, 환원제, 금속이온, 무기산등이 혼합되어 있는 화학용액을 사용하여 원전기기 계통 내부에 생성된 고방사능 준위의 산화막과 오염물질을 제거하는 기술이다. 원전의 해체 및 유지보수에 있어 방사능 피복저감을 위한 필수적인 기술이다. 현재 원전 해체 산업은 잠재성이 높은 고부가가치 창출 산업으로 주목을 받고 있다. 원전 보유국의 경우, 기존 상용 제염기술과는 차별성 있는 제염기술을 확보하고자 노력하고 있다. 기존의 공정과 비교하여 공정비용 및 시간을 감소시킬 수 있어야 할 뿐만 아니라, 화학용액에 의한 원전 계통 금속 부품의 부식 및 손상을 최소화해야 한다. 금속 부품이 화학약품에 의한 부식손상을 받는다면 금속 부품의 수명 및 재활용 가치가 감소하기 때문에, 화학제염 기술 적용에 있어 용액에 대한 재료의 건전성 평가가 사전에 필히 이루어져야 한다. 본 연구에서는 원전 냉각재 펌프용 재료로 주로 사용되는 Stainless 304강을 시험편으로 선정하여, 화학제염 시험공정 3가지에 대한 부식손상 특성을 규명하였다. 산화공정은 과망간산($HMnO_4$) 용액을 공통으로 사용하였으며, 산화공정 종료 후 환원공정은 각 시험공정에 따라 시험공정 1은 옥살산($H_2C_2O_4$) 2000ppm, 시험공정 2는 옥살산($H_2C_2O_4$)1500ppm + 시트르산($H_8C_6O_7$)500ppm, 그리고 시험공정 3은 옥살산($H_2C_2O_4$) 3000ppm 용액을 각각 투입하여 수행하였다. 산화, 환원공정을 1Cycle로 하여, 각 시험공정 별로 총 5Cycle을 실시하였다. 각 시험공정 Cycle종료 후 시험편을 취외하여 무게감량측정, SEM(Scanning electron microscope) 분석, 3D현미경분석 그리고 타펠분극 실험을 실시하였다. 각 분석결과를 토대로 하여, Stainless 304강에 대한 화학제염 시 모델별 시험공정에 따른 부식특성을 규명하였다.

• Construction Engineering and Management
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• v.5 no.6 s.22
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• pp.42-45
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• 2004

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.389-390
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• 2016

• Journal of the Korea Academia-Industrial cooperation Society
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• v.16 no.9
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• pp.6297-6304
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• 2015

Nuclear power plant decommissioning has attracted attention according to the shutdown decision of Kori 1 which is Korea's first nuclear power plant. Nuclear power plant decommissioning is the one who never experienced ever in our country. So, its process is difficult and time-consuming. In addition, it is difficult to determine the decommissioning quantity. This study proposed the plan that can be used in quantity take-off for nuclear power plant decommissioning using BIM technology being utilized in recent construction industry. As a result, we suggested the method of BIM-based quantity take-off such as the selection decommissioning method and process, setting up of BIM modeling environment, establishment of OBS & WBS, integrated BIM modeling, the definition of quantity property. The proposed plan can be utilized usefully from when permanent stopping nuclear power plant occurs intensively. Furthermore, the overseas nuclear power plant decommissioning project order also are expected through technology securement based on this plan.

• Proceedings of the Korea Information Processing Society Conference
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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.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.10a
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• pp.147-148
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• 2016

ACPF 핫셀에 기 설치된 일체형 원격조종기의 해체 작업은 모두 완료 되었으며, 셀 내 부압 유지를 위해 월튜브 전면부는 기밀되었다. 금년 말까지 핫셀 원격조종기를 모두 분리형으로 대체하여 전해환 공정 실험의 원격작업에 활용할 계획이다.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.720-724
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• 2003

In order to develop the decontamination process for self-disposal with authorization of duct waste generated from the decommissioning of retired TRIGA research reactors, the surface characterization of duct specimen taken from TRIGA research reactor was carried out and the adequate decontamination method was selected. It can be known that the paint coated internal surface of duct is contaminated with $^{60}Co$and $^{137}Cs$, which are penetrated into the paint layer and incorporated into zinc plated surface of galvanized iron as the material of duct. Two step chemical decontamination process, in which sodium hydroxide and sulfuric acid solutions are used in turn, is quite successful to remove the surface contamination of duct waste.