• 한국정밀공학회지
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• 제16권6호
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• pp.133-140
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• 1999

In this study, a monitoring method to detect chip disposal state in drilling system based on neural network was proposed and its performance was evaluated. If chip flow is bad during drilling, not only the static component but also the fluctuation of dynamic component of drilling. Drilling torque is indirectly measured by sensing spindle motor power through a AC spindle motor drive system. Spindle motor power being measured drilling, four quantities such as variance/mean, mean absolute deviation, gradient, event count were calculated as feature vectors and then presented to the neural network to make a decision on chip disposal state. The selected features are sensitive to the change of chip disposal state but comparatively insensitive to the change of drilling condition. The 3 layerd neural network with error back propagation algorithm has been used. Experimental results show that the proposed monitoring system can successfully recognize the chip disposal state over a wide range of drilling condition even though it is trained under a certain drilling condition.

• Journal of Nuclear Fuel Cycle and Waste Technology
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• 제1권1호
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• pp.37-47
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• 2013

This paper describes basic plans for the development of a radioactive waste disposal facility with the introduction of Nuclear Power Plants (NPPs) for Kenya. The specific objective of this study was to estimate the total projected waste volumes of low- and intermediate-level radioactive waste (LILW) expected to be generated from the Kenyan nuclear power programme. The facility is expected to accommodate LILW to be generated from operation and decommissioning of nuclear power plants for a period of 50 years. An on-site storage capacity of 700 $m^3$ at nuclear power plant sites and a final disposal repository facility of more than 7,000 $m^3$ capacity were derived by considering Korean nuclear power programme radioactive waste generation data, including Kori, Hanbit, and APR 1400 nuclear reactor data. The repository program is best suited to be introduced roughly 10 years after reactor operation. This study is important as an initial implementation of a national LILW disposal program for Kenya and other newcomer countries interested in nuclear power technology.

• 대한산업공학회지
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• 제33권3호
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• pp.312-321
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• 2007

We address a disposal issue of returned products in a product recovery system where a single product is stocked in order to meet a demand from customers who may return products after usage. Product returns occur randomly and can be accepted for remanufacturing or disposed of depending on the state of the system. We examine the structure of the optimal disposal policy for returned product that utilizes the information of the inventory of both serviceable and remanufacturable products. Numerical study indicates that it can be characterized by a monotonic threshold type of the curve. A disposal is allowed only when the remanufacturable inventory level exceeds a threshold which is the function of the inventory level of serviceable product and it is decreasing as the serviceable inventory level increases. Sensitivity analysis also indicates that the optimal disposal policy and the optimal profit have monotonic properties with respect to system parameters.

• Environmental Engineering Research
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• 제24권2호
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• pp.191-201
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• 2019

Petroleum industry produces one of the popular hazardous waste known as Petroleum Sludge. The treatment and disposal of petroleum sludge has created a major challenge in recent years. This review provides insights into various approaches involved in the treatment, and disposal of petroleum sludge. Various methods used in the treatment and disposal of petroleum sludge such as incineration, stabilization/solidification, oxidation, and bio-degradation are explained fully and other techniques utilized in oil recovery from petroleum sludge such as solvent extraction, centrifugation, surfactant EOR, freeze/thaw, pyrolysis, microwave irradiation, electro-kinetic method, ultrasonic irradiation and froth flotation were discussed. The pros and cons of these methods were critically considered and a recommendation for economically useful alternatives to disposal of this unfriendly material was presented.

• Nuclear Engineering and Technology
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• 제53권3호
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• pp.1041-1048
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• 2021

An engineered barrier system (EBS) for the disposal of high-level radioactive waste (HLW) is composed of a disposal canister with spent fuel, a buffer material, a gap-filling material, and a backfill material. As the buffer is located in the empty space between the disposal canisters and the surrounding rock mass, it prevents the inflow of groundwater and retards the spill of radionuclides from the disposal canister. Due to the fact that the buffer gradually becomes saturated over a long time period, it is especially important to investigate its thermal-hydro-mechanical-chemical (THMC) properties considering variations of saturated condition. Therefore, this paper suggests a new method of measuring thermal conductivity and water suction for single compacted bentonite at various levels of saturation. This paper also highlights a convenient method of saturating compacted bentonite. The proposed method was verified with a previous method by comparing thermal conductivity and water suction with respect to water content. The relative error between the thermal conductivity and water suction values obtained through the proposed method and the previous method was determined as within 5% for compacted bentonite with a given water content.

• 방사성폐기물학회지
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• 제20권1호
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• pp.13-22
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• 2022

The decommissioning of a nuclear power plant generates large amounts of radioactive waste, which is of several types. Radioactive concrete powder is classified as low-level waste, which can be disposed of in a landfill. However, its safe disposal in a landfill requires that it be immobilized by solidification using cement. Herein, a safety assessment on the disposal of solidified radioactive concrete powder waste in a conceptual landfill site is performed using RESRAD. Furthermore, sensitivity analyses of certain selected input parameters are conducted to investigate their impact on exposure doses. The exposure doses are estimated, and the relative impact of each pathway on them during the disposal of this waste is assessed. The results of this study can be used to obtain information for designing a landfill site for the safe disposal of low-level radioactive waste generated from the decommissioning of a nuclear power plant.

• 방사성폐기물학회지
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• 제21권3호
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• pp.329-345
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• 2023

This paper described a method for analyzing the structural performance of a metal container used for disposing radioactive waste generated during the decommissioning of a nuclear power plant, and numerical analysis results of a method for reinforcing the container. The containers to be analyzed were those that can be used in near-surface and landfill disposal facilities scheduled to be operated at the Gyeongju radioactive waste disposal facility. Structural reinforcement of the container was performed by lattice reinforcement, column reinforcement, and bottom plate reinforcement. Accordingly, a total of 14 reinforcement cases were modeled. The external force causing damage to the container was set equivalent to the impact of a 9-m fall, accounting for the height of the vault at the near-surface disposal facility. The reinforcement methods with a high contribution to the structural performance of the container were concluded to be lattice and column reinforcements.

• 방사성폐기물학회지
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• 제9권3호
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• pp.169-179
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• 2011

우리나라에서 운영하는 원자력발전소는 PWR형과 CANDU형 2종류가 있으며, 원자력발전에 의한 지속적인 에너지 공급을 위하여 이들로부터 발생하는 사용후핵연료에 대한 안전관리는 매우 중요한 인자이다. 사용후핵연료 처분을 위한 연구는 1997년부터 시작하여 한국형 사용후핵연료 처분시스템을 개발하였으며, 현재는 개발된 기술에 대한 실증 및 처분시스템의 효율향상을 위한 연구를 진행하고 있다. 또한, PWR형 사용후핵 연료의 경우 사용후핵연료 재활용 공정을 거쳐 원료물질로 다시 사용하는 연구가 진행 중이므로, 이들 공정으로부터 발생하는 고준위폐기물을 처분하는 방안을 강구하고 있다. 이에 따라 본 논문에서는 PWR형과 CANDU형 사용후핵연료 모두를 직접 처분하는 개념으로 개발한 한국형 사용후핵연료 처분시스템을 바탕으로 CANDU형 사용후핵연료 처분 시스템의 처분효율을 향상시키는 방안을 도출하고자 하였다. 이를 위하여, 한국형 사용후핵연료 처분시스템의 CANDU 사용후핵연료 처분용기를 개선하여 현재 원자력발전소에서 사용하고 있는 사용후핵연료 60 다발(Bundle) 용량의 저장바스켓을 포장 활용하는 개념을 도출하고, 열해석을 통하여 처분시스템 완충재의 온도가 $100^{\circ}C$를 넘지 않도록 하는 요건을 만족하는 처분터널 및 처분공 간격을 정하여 이들에 대한 처분시스템 개념을 도출하였다. 이렇게 설정된 개념들을 단위면적당 열효율, 우라늄밀도(U-density), 처분면적, 굴착량, 완충재 및 폐쇄 물질량 측면에서 분석하여 처분효율이 가장 높은 방안을 제안하였다. 본 연구의 결과는 추후 실제 부지특성자료와 연계하여 PWR 사용후핵연료 재활용공정으로부터 발생한 고준위폐기물 처분시스템과 함께 복합 처분장 설계에 활용될 것이다.

• Journal of Preventive Medicine and Public Health
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• 제49권5호
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• pp.323-328
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• 2016

Objectives: A clean India is the responsibility of all Indians. One of the objectives of the Swachh Bharat Abhiyan (Clean India Initiative) is to bring about behavioural changes regarding healthy sanitation practices. While large-scale programs in India have increased latrine coverage, they have to some extent failed to bring behavioural changes ensuring optimal latrine use, including the safe disposal of child faeces, which is a significant source of exposure to faecal pathogens. Hence, this study was done to explore child faeces disposal practices in rural West Bengal and to elicit the determinants of unhygienic faeces disposal. Methods: Data collection was done using an interview method among the mothers of 502 under-5 children, following a pre-designed, semi-structured schedule during house-to-house visits in a set of villages in the Hooghly district of West Bengal. Results: The prevalence of unsafe disposal of child faeces was 72.4%, and maternal education, per capita income, and water source were found to be significantly associated with unsafe child faeces disposal. Conclusions: This study draws attention to the unsafe disposal of child faeces in this area of India and raises questions about the efficiency of sanitation campaigns in rural India that focus on expanding coverage rather than emphasizing behavioural changes, which are crucial to ensure the safe disposal of child faeces. Thus, it is urgently necessary to strengthen efforts focusing on behavioural changes regarding the safe disposal of child faeces in order to minimise adverse health outcomes.

• 방사성폐기물학회지
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• 제15권1호
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• pp.65-82
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• 2017

방사성폐기물 발생기관의 가용데이터를 기반으로 산출된 핵종재고량을 적용하여 예비안전성평가를 수행한 결과 처분안전성과 운영측면에서 많은 어려움이 예상됨을 확인하였다. 본 논문에서는 전체처분시설 예비안전성평가를 수행하였으며, 평가결과 성능목표치 초과핵종에 대해 방사능량이 큰 비중을 차지하는 단위포장물을 선별하고, 높은 표면선량률의 포장물을 처분대상에서 제외하는 방식으로 처분시설의 처분방사능량제한을 도입하였다. 처분방사능량제한은 안전기준 만족을 위한 처분시설별 인수기준과 처분기준 설정에 기초자료로 활용할 것이며, 경주 처분시설의 안전한 종합개발계획수립 및 처분시설의 안전성 최적화를 위한 Safety Case 구축에 기여할 것으로 판단된다.