• Proceedings of the Korean Institute of Building Construction Conference
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• 2021.05a
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• pp.309-310
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• 2021

In order to respond to environmental problems and to efficiently recycle resources, it is important to evaluate the amount of construction waste generated. In particular, the estimation of the amount of waste generated in the demolition work was performed based on the basic unit of waste generated per floor area. This study proposes a method using drones as a method for evaluating the amount of demolition waste in a wide area. In the simulated application, the field measurement results and the proposed method were compared, and the effectiveness of the building volume calculation using drones was confirmed. It was confirmed that the building volume can be calculated quickly in the additional pilot application.

• Proceedings of the Korean Institute Of Construction Engineering and Management
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• 2004.11a
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• pp.500-503
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• 2004

In this country, now redevelopment and rebuild is becoming largely because it is improving welfare and life condition with high growth of economy. Also, the scale of construction project is trend to increase to adjust the changing social situation. Accordingly, C&D waste is rising largely because of the increased demolition works in city. The right management of C&D waste is becoming one of very important things, but little research has been conducted to estimate correctly C&D waste. This study suggests standard units of C&D waste which can estimate demolition quantity of apartment. These units can estimate easily and correctly C&D waste in demolition works and also can make it possible to use very important material to carry out policy of national waste management.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.242-242
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• 2004

원자력발전소의 운전과정에서 계획적 혹은 비계획적으로 방출되는 미량의 입자상 방사성 물질들은 대부분 원전 부지내 토양에 침적되게 된다. 이러한 과정 속에서 오염토양이 발생하게 되면 수거되어 단순 격리관리하고 있는 실정이지만 앞으로 원전의 해체과정 등으로 인한 오염토양이 상당량 발생할 것으로 예상되기 때문에 적절한 제염을 통하여 폐기물량을 최소화시킬 필요가 있다. 이를 위해 오염토양 제염공정으로 물을 이용한 토양세척법을 선정하여 제염장치를 제작하였으며 실증시험을 수행하였다.(중략)

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.2
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• pp.153-164
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• 2014

Currently, there are many programs which are now being developed or already developed to predict radionuclide and corrosion product at the stage of designing NPP. However, since there are not many developments in evaluating quantity of activation corrosion products occurring when disassembling a nuclear power plant there exist some difficulties in calculating accurately. In order to evaluate activation products inventory for the research of effect of neutron activation in the reactor vessel, component of nuclear reactor and adjacent structures, it should be evaluated by using operation history of nuclear reactor, material composition of structure and average neutron flux in every field representing fixed structure of nuclear reactor. In this study, CORA, PACTOLE, CRUDSIM, CREAT and ACE codes are analyzed to predict the quantity of radionuclide and corrosion product of primary reactor which is used at the stage of designing. As a future study, the accuracy in calculating the quantity of product corrosion can be increase by finding out the possibility of use and improvement for evaluation of the decontamination.

• Proceedings of the Korean Institute Of Construction Engineering and Management
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• 2008.11a
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• pp.388-391
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• 2008

The Domestic housing Industry has to give consequence to the redevelopment and rebuilding of existing housings rather than the supply by developing a new building site, and now those tendencies are rapidly spreading out. Also, because apartment buildings occupies 50% over of the existing housing, its maintenance, repair, remodeling and reconstruction got to be necessary area for the slumming prevention of a residential area and the disaster prevention occurred by durability lowering of the building. It is increasing the interest for reusing and recycling of C&D waste. The government is doing efforts to diminish amount of C&D waste. But there couldn't find any efforts for developing Integrated system to manage and to estimate lightly generated amounts of C&D waste. So, this study presents a integrated computer system that can estimate easily quantity of C&D waste by using CAD draw and 3D Object.

• Journal of Energy Engineering
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• v.29 no.1
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• pp.63-74
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• 2020

The Kori-Unit 1 nuclear power plant, which is scheduled for decommissioning after permanent shutdown, is expected to generate a large amount of various types of radioactive waste during decommissioning process. For concrete radioactive waste, which is expected to occupy the most amount, it is important to analyze the current waste disposal status and legal limitations and to prepare an appropriate and efficient disposal method. Concrete radioactive waste is waste of various levels, of which the clearance level is bioshield concrete. In this paper, clearance radioactive waste safety evaluation was performed using the RESRAD code, which is a safety evaluation code, based on the activation evaluation results for the wastes with the clearance level. The clearance scenario of the target radioactive waste was selected and the individual's exposure dose was calculated at the time of clearance to determine whether the clearance criteria limit prescribed by the Nuclear Safety Act was satisfied. As a result of the evaluation, the results showed significantly lower results and satisfied the criteria value. Based on the results of this clearance safety assessment, the appropriate disposal method for bioshield concrete, which are the clearance wastes of subject of deregulation, was suggested.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.16 no.4
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• pp.473-478
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• 2018

Radioactive aerosol generated in cutting and melting work during the NPP decommissioning process can cause internal exposure to body through workers' breath. Thus, it is necessary to assess worker internal exposure due to the radioactive aerosol during decommissioning. The actually measured value of the working environment is needed for accurate assessment of internal exposure, but if it is difficult to actually measure that value, the internal exposure dose can be estimated through recommended values such as the fraction of amount of intake and the size of particles suggested by the International Committee on Radiological Protection (ICRP). As for the selection of particle size, this study applied a value of $5{\mu}m$, which is the size of particles considering the worker recommended by the ICRP. As for the amount of generation, the amount of intake was estimated using data on the mass of aerosol generated in a melting facility at a site in Kozloduy, Bulgaria. In addition, using these data, this study calculated the level of radioactivity in the worker's body and stool and conducted an assessment of internal exposure using the BiDAS computer code. The internal exposure dose of Type M was 0.0341 mSv, that of Type S was 0.0909 mSv. The two types of absorption showed levels that were 0.17% and 0.45% of the domestic annual dose limit, respectively.

• Proceedings of the Korean Institute of Industrial Safety Conference
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• 1998.11a
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• pp.321-326
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• 1998

폐콘크리트양은 건설폐기물 발생량의 약 50%정도인 연간 약 500만톤 이상으로 추정하고 있다. 따라서, 건설폐기물인 폐콘크리트에 대한 적절한 기술적 처리와 재활용 시스템이 구축된다면 도로포장 및 기타 포장 하층노반재료, 재생 입도조정쇄석, 건축물의 기초재, 토목 구조물의 기초재, 공작물의 되메우기 재료 등으로 활용될 수 있어 폐기되어버릴 단순한 쓰레기가 아니라 오히려 재활용 용도를 적극 개발하여야 할 중요한 자원이라고 볼 수 있다. 본 연구의 목적은 여러가지 건설 폐기물 중에서도 재활용 가능성이 높으며 구조물 해체시 다량으로 얻어지는 폐콘크리트를 대상으로 건설공사에 재이용하기 위해 폐콘크리트 골재를 사용한 재생콘크리트의 공학적 특성을 실험을 통해 검토하고자 하는 것이다. (중략)

• Journal of the Korean Recycled Construction Resources Institute
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• v.6 no.2
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• pp.115-122
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• 2018

In this paper, the feasibility of recycling concrete waste as a method to reduce final disposal amount of wastes generated through decommissioning of nuclear power plant has been analyzed based on experimental results of existing literature. When recycled concrete waste was used as recycled aggregate, it was investigated through literature that the concrete strength decreased by 30~40% depending on the mixing ratio. It was also investigated that concrete with recycled aggregate can be used as a structural material when the quality of recycled aggregate is well managed since no significant problem was found. When recycled cement produced from concrete waste was used, the strength of concrete or mortar decreased considerably as the recycled cement content increased. Therefore, it can be concluded that concrete or mortar with recycled cement can be used as a filling material for final disposal of large radioactive waste rather than for structural use. This paper is expected to be useful for reduction on disposal volume and decommissioning cost for nuclear power plants such as Kori 1.

• Journal of Radiation Protection and Research
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• v.37 no.4
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• pp.202-207
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• 2012

The radioactivity inventory significantly affects all steps of decommissioning projects including planning, cost estimation, risk assessment, waste management and site remediation. The decommissioning project of the KRR-2 was completed in 2009 and a large amount of activated concrete waste was generated. The bioshield concrete, containing minute amount of impurity elements, was activated by neutron reaction during the operation of the reactor. A variety radionuclides was generated in the concrete, including $^3H$, $^{14}C$, $^{55}Fe$, $^{60}Co$ $^{63}Ni$, $^{134}Cs$, $^{152}Eu$ and $^{154}Eu$. In this paper, the comparison between the calculated results and previous measured results was carried out to estimate the inventory of the bioshield concrete of the KRR-2. The combined computer codes of MCNP5 and ORIGEN 2.1 for calculation of the distribution of neutron flux, cross-section and generation of radionuclides were used. The results were shown that 99.8% of the total radioactivity of $^3H$, $^{55}Fe$, $^{60}Co$ and $^{152}Eu$ in the bioshield concrete 12 years after shutdown. The effects on the variation of inventory were analysed depending on the operation periods and the cooling times in the bioshield concrete.