• 한국건설순환자원학회논문집
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• 제4권4호
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• pp.371-378
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• 2016

본 연구에서는 건설폐기물의 실질적인 재활용율을 높이고자 건설폐기물의 발생단계인 해체공사 현장에서 사용할 수 있는 소형의 이동식 분리 선별 장치를 개발하고 이에 대한 선별 효율성능을 평가하였다. 개발한 장치는 상당수의 해체현장이 도심지에 소재한다는 점을 고려하여 협소한 현장여건과 해체현장에서 수행되는 다양한 공정을 고려하여 $15m^2$ 면적 이내에서 1개의 암롤박스를 하루에 처리할 수 있는 16ton의 용량의 이동식 소형 분리 선별 장치를 개발하였다. 개발한 장치의 효율성능을 평가하기 위하여 트롬멜 회전속도 RPM 2~3, 4~6, 7~8에 대하여 10회씩 분리 선별을 실시하였고 그 결과 RPM 6~7에서 가장 높은 약 90%의 효율로 투입폐기물을 성상별로 분리하였다.

• 방사성폐기물학회지
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• 제7권3호
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• pp.143-151
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• 2009

최근 미-북간 관계 개선 등으로 인하여 북핵 문제가 핵 검증단계로 진전될 것이라는 예상이 나오고 있다. 이제부터 우리 정부는 북핵 프로그램의 성공적 검증 폐기를 위해, 북한의 신고 후 전개될 상황에 대비하여 철저히 준비해야 한다. 본 논문에서는 구 소련과 이라크의 대량살상무기 검증 폐기 사례로부터 두 나라의 대량살상무기 검증 폐기 과정에서 발생한 문제점을 조사 분석하여, 북핵 검증 폐기 과정 시 발생할 수 있는 문제점을 파악하고 이를 방지하기 위한 정책적 고려사항을 도출하는데 목적을 두었다.

• 방사성폐기물학회지
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• 제22권1호
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• pp.37-44
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• 2024

In 2017, a decision was made to permanently shut down Kori Unit 1, and preparations began to be made for its decontamination and decommissioning. The dismantling of the biological shields concrete, reactor vessel (RV), and reactor vessel internals (RVI) is crucial to the nuclear decommissioning process. These components were radiologically activated by the neutron activation reaction occurring in the reactor during its operational period. Because of the radioactivity of the RV and RVI of Kori Unit 1, remotely controlled systems were developed for cutting within the cavity to reduce radiation exposure. Specialized equipment was developed for underwater cutting operations. This paper focuses on modeling related to RVI operations using the MAVRIC code and the dose calculation for a diver entering the cavity. The upper and lower parts of the RVI are classified as low-level radioactive waste, while the sides that came into contact with the fuel are classified as intermediate-level radioactive waste. Therefore, the modeling presented in this paper only considers the RVI sides because the upper and lower parts have a minimal impact on the radiation exposure. These research findings are anticipated to contribute to enhancing the efficiency and safety of nuclear reactor decommissioning operations.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.2019-2024
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• 2021

For evaluating the radiological safety of dismantled concrete, the process of disposal and recycling of the radioactive concrete generated during the dismantling of Kori Unit 1 is analyzed. Four scenarios are derived based on the analysis of the concrete recycling and disposal process, and the potential exposure to the workers and public during this process are calculated. VISIPLAN and RESRAD code are used for evaluating the dosages received by the workers and public in the following four scenarios: concrete inspection, transport of concrete by the truck driver, driving on a recycled concrete road, and public living near the landfilled concrete waste. Two worker exposure scenarios in the processing of concrete and two public exposure scenarios in recycling and disposal are considered; in all the scenarios, the exposure dose does not exceed the annual dose limit for each representative.

• 건축역사연구
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• 제28권2호
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• pp.31-40
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• 2019

Considering the situation in the early 20th century when the existing urban system centered on urban areas began to change, the biggest factors causing urban structural changes in urban areas are construction of railroad and urban dismantling. The change process of Eupseong, in the microscopic viewpoint, can be understood as a process of change in the course of dismantlement of town's demarcation, improvement of accessibility and urban expansion due to the construction of railroads, process of urban expansion following the crumbling boundaries and structural changes. This study aimed to look at the transformation process of the Eupseong in the early 20th century, focusing on the demolition of the castle and the railway construction from a microscopic point of view of city.

• 한국압력기기공학회 논문집
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• 제16권1호
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• pp.110-116
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• 2020

As the management plan for domestic spent nuclear fuel is delayed, the storage of the operating nuclear power plant is approaching saturation, and the Kori 1 Unit that has reached its end of operation life is preparing for the dismantling plan. The first stage of dismantling is the transfer of spent nuclear fuel stored in storage at plants. The spent fuel management process leads to temporary storage, interim storage, reprocessing and permanent disposal. In this paper, the technical issues to be considered when transporting spent fuel in this process are summarized. The spent fuels are treated as high-level radioactive waste and strictly managed according to international regulations. A series of integrity tests are performed to demonstrate that spent fuel can be safely stored for decades in a dry environment before being transferred to an intermediate storage facility. The safety of spent fuel transport container must be demonstrated under normal transport conditions and virtual accident conditions. IAEA international standards are commonly applied to the design of transport containers, licensing regulations and transport regulations worldwide. In addition, each country operates a physical protection system to reduce and respond to the threat of radioactive terrorism.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2001년도 춘계학술대회 논문집
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• pp.651-654
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• 2001

In the dismantling process of nuclear spent fuels, the spent fuel rod cutting process, followed immediately by the decladding process, performs the cutting the spent fuel rods to a proper length for fast decladding operation. In this paper, we analyzed the chemical compositions, mechanical properties, and physical characteristics for SUS and zircaloy tubes in order to identify the feasibility of cutter-blade type in cutting SUS and zircaloy tubes. It is considered that material, shape and angle, and heat treatment for fabricating the highly durable cutter blade and also it is investigated that the round-shape sustenance of cross-section, amount of debris production, and fire occurrence for measuring the cutting performance on SUS and zircaloy tubes, spent fuel rod cutting device is designed to be operated automatically through the remote control system for use in Hot Cell(radioactive) area and the electro-driven mechanical parts are modularized for easy maintenance. Results from various experiments confirm the efficiency of this device.

• 박물관보존과학
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• 제27권
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• pp.1-22
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• 2022

부여 부소산사지 출토 치미는 지난 1978년 부여박물관에서 복원하였지만, 오랜 시간이 지남에 따라 복원재료인 석고가 열화되면서 치미의 무게를 감당하지 못해 부분적으로 심하게 파손되어 있었다. 이를 보강하기 위해 응급으로 에폭시 수지를 사용하여 몸통 내부와 일부 꼬리 부분을 여러 차례 보강한 흔적이 있었다. 전시 기간에 맞춰 치미를 이동하기 위해 상태 점검을 하던 중 치미의 하부 몸통 및 날개 부분의 안정성이 매우 취약하다고 판단되어 다시 복원하기로 하였다. 재 복원하기 위해 치미를 해체하는 과정에서 당시 도공의 제작 방법을 유추해볼 수 있는 여러 제작흔적이 남아 있어 치미의 제작 방법을 연구할 수 있는 좋은 자료로 판단되어 조사하였다. 본 논문은 재 복원을 위해 해체하는 과정에서 밝혀진 부소산사지 치미의 제작기법을 정리하였다. 3차원 기술을 이용해 치미를 스캔한 후 해체 과정에서 살펴본 치미의 제작기법을 바탕으로 수직적이고 경직된 형태를 자연스러운 형태로 수정하고 복원하여 이전 재료를 교체함으로써 복원제의 내구성을 강화하였다. 모델링한 출력물을 본래 편과 접합하고 소실된 형태를 새롭게 만들어 완형으로 재 복원하였다.

• 수산해양기술연구
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• 제44권1호
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• pp.75-80
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• 2008

A scrapped fiber-reinforced plastic(FRP) fishing vessel causes many environmental problems, because technology development for recycling FRP vessel has not been adequately addressed. FRP is a main material for constructing a small coastal fishing vessel that is an object of reduction policy. Therefore, the FRP wastes derived a scrapped fishing vessel are increasing. In this study, I investigated an effective disposal process for FRP through the analysis of the actual conditions of scrapped FRP fishing vessel. The treatment processes of scrapped FRP fishing vessel are carried out with oil-removing, dismantling, intermediated processing(crushing), and then reclaiming follows burning in the final processing in Korea. However, in Japan, several recycling methods have been developed, for example, the incineration including thermal recovery, the use of cement-reclamation, and the use of asphalt concrete aggregate, because the method of reclaiming after incinerating which is generally used in Korea produces a toxic by-product such as dioxin.

• 한국안전학회지
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• 제29권4호
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• pp.184-190
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• 2014

Decommissioning process of nuclear facilities consist of a sequence of problem solving activities, because there may exist not only working environments contaminated by radiological exposure but also industrial hazards such as fire, explosions, toxic materials, and electrical and physical hazards. Therefore, not a few countries in the world have been trying to develop appropriate counter techniques in order to guarantee safety and efficiency of the process. In spite of that, there still exists neither domestic nor international standard. Unfortunately, however, there are few workers who experienced decommissioning operations a lot in the past. As a solution, it is quite necessary to utilize experts' opinions for risk assessment in decommissioning process. As for an individual hazard factor, risk assessment techniques are getting known to industrial workers with advance of safety technology, but the way how to integrate those results is not yet. This paper aimed to find out an appropriate technique to integrate individual risk assessment results from the viewpoint of experts. Thus, on one hand the whole risk assessment activity for decommissioning operations was modeled as a sequence of individual risk assessment steps which can be classified into two activities, decontamination and dismantling, and on the other, a risk assessment structure was introduced. The whole model was inferred with Fuzzy theory and techniques, and a numerical example was appended for comprehension.