• Title/Summary/Keyword: Waste-to-Energy

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A Study of Hydroxyapatite Production from Waste Oyster Used Mechanochemical Treatment

  • Kim, Sun-Tae;Oh, Chi-Jung;Kim, Wan-Tae;Kim, Young-Sig;Kim, Myong-Jun
    • Proceedings of the IEEK Conference
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    • 2001.10a
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    • pp.469-471
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    • 2001
  • Dry grinding of a mixture of CaCO$_3$ and Ca(H$_2$PO$_4$)$_2$.$H_2O$ was conducted using a planetary ball mill in order to investigate solid state reaction for a synthesis of hydroxyapatite(Ca$_{10}$(PO$_4$)$_{6}$(OH)$_2$, HAp) through mechanochemical treatment method. The raw materials, which are composed of waste oyster and calcium biphosphate Ca(H$_2$PO$_4$)$_2$.$H_2O$, were mixed and then treated mechanochemically. The synthesis of hydroxyapatite(Ca$_{10}$(PO$_4$)$_{6}$(OH)$_2$, HAp) from the mixture was almost completed by about 60 minute grinding. The formation of HAp monophase in the ground mixture was characterized through X-ray diffraction (XRD) analysis. Moreover, the formation of HAp monophase depending on the grinding time was improved by increasing the grinding time.ime.ime.

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Fabrication of Nanowire by Electrospinning Process Using Nickel Oxide Particle Recovered from MLCC (MLCC에서 회수된 산화니켈 분말의 전기방사공정을 통한 나노와이어 제조)

  • Haein Shin;Jongwon Bae;Minsu Kang;Kun-Jae Lee
    • Journal of Powder Materials
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    • v.30 no.6
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    • pp.502-508
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    • 2023
  • With the increasing demand for electronic products, the amount of multilayer ceramic capacitor (MLCC) waste has also increased. Recycling technology has recently gained attention because it can simultaneously address raw material supply and waste disposal issues. However, research on recovering valuable metals from MLCCs and converting the recovered metals into high-value-added materials remains insufficient. Herein, we describe an electrospinning (E-spinning) process to recover nickel from MLCCs and modulate the morphology of the recovered nickel oxide particles. The nickel oxalate powder was recovered using organic acid leaching and precipitation. Nickel oxide nanoparticles were prepared via heat treatment and ultrasonic milling. A mixture of nickel oxide particles and polyvinylpyrrolidone (PVP) was used as the E-spinning solution. A PVP/NiO nanowire composite was fabricated via E-spinning, and a nickel oxide nanowire with a network structure was manufactured through calcination. The nanowire diameters and morphologies are discussed based on the nickel oxide content in the E-spinning solution.

Preliminary Analyses of the Deep Geoenvironmental Characteristics for the Deep Borehole Disposal of High-level Radioactive Waste in Korea (고준위 방사성폐기물 심부시추공 처분을 위한 국내 심부지질 환경특성 예비분석)

  • LEE, Jongyoul;LEE, Minsoo;CHOI, Heuijoo;KIM, Geonyoung;KIM, Kyungsu
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.14 no.2
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    • pp.179-188
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    • 2016
  • Spent fuels from nuclear power plants, as well as high-level radioactive waste from the recycling of spent fuels, should be safely isolated from human environment for an extremely long time. Recently, meaningful studies on the development of deep borehole radioactive waste disposal system in 3-5 km depth have been carried out in USA and some countries in Europe, due to great advance in deep borehole drilling technology. In this paper, domestic deep geoenvironmental characteristics are preliminarily investigated to analyze the applicability of deep borehole disposal technology in Korea. To do this, state-of-the art technologies in USA and some countries in Europe are reviewed, and geological and geothermal data from the deep boreholes for geothermal usage are analyzed. Based on the results on the crystalline rock depth, the geothermal gradient and the spent fuel types generated in Korea, a preliminary deep borehole concept including disposal canister and sealing system, is suggested.

Theoretical Analysis of Heat Transport Limitation in a Screen Mesh Wick Heat Pipe

  • Lee, Ki-Woo;Park, Ki-Ho;Lee, Wook-Hyun;Rhi, Seok-Ho
    • International Journal of Air-Conditioning and Refrigeration
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    • v.12 no.1
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    • pp.1-9
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    • 2004
  • The purpose of the present study is to examine the heat transport limitations in a screen mesh heat pipe for electronic cooling by theoretical analysis. Diameter of pipe was 6mm, and mesh numbers were 50, 100, 150, 200 and 250, and water was investigated as working fluid. According to the change of mesh number, wick layer, inclination and saturation temperature, the maximum heat transport limitations by capillary, entraintment, sonic and boiling were analyzed by a theoretical design method of heat pipe, including capillary pressure, pumping pressure, liquid friction coefficient in wick, vapor friction coefficient, etc. Based on the results, the capillary limitation in a small diameter of heat pipe is largely affected by mesh number and wick layer. Mesh number of 250 is desirable not to be used in pipe diameter of 6 mm, because capillary heat transport limitation decreases by the abrupt increase of liquid friction pressure due to the small liquid flow area. For the heat transport of 15 watt in 6mm diameter pipe, mesh number of 100 and one layer is an optimum wick condition, which thermal resistance is the smallest.

UK Civil Nuclear Decommissioning, a Blueprint for Korea's Nuclear Decommissioning Future?: Part II - UK's Progress and Implications for Korea

  • Foster, Richard I.;Park, June Kyung;Lee, Keunyoung;Seo, Bum-Kyoung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.1
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    • pp.65-98
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    • 2022
  • The nuclear legacy that remains in the United Kingdom (UK) is complex and diverse. Consisting of legacy ponds and silos, redundant reprocessing plants, research facilities, and non-standard or one-off reactor designs, the clean-up of this legacy is under the stewardship of the Nuclear Decommissioning Authority (NDA). Through a mix of prompt and delayed decommissioning strategies, the NDA has made great strides in dealing with the UK's nuclear legacy. Fuel debris and sludge removal from the legacy ponds and silos situated at Sellafield, as part of a prompt decommissioning strategy for the site, has enabled intolerable risks to be brought under control. Reactor defueling and waste retrievals across the Magnox fleet is enabling their transition to a period of care and maintenance; accelerated through the adopted 'Lead and Learn' approach. Bespoke decommissioning methods implemented by the NDA have also enabled the relevant site licence companies to tackle non-standard reactor designs and one-off wastes. Such approaches have potential to influence and shape nuclear decommissioning decision making activities globally, including in Korea.

Ignition and flame propagation in hydrogen-air layers from a geological nuclear waste repository: A preliminary study

  • Ryu, Je Ir;Woo, Seung Min;Lee, Manseok;Yoon, Hyun Chul
    • Nuclear Engineering and Technology
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    • v.54 no.1
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    • pp.130-137
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    • 2022
  • In the geological repository of radioactive nuclear waste, anaerobic corrosion can generate hydrogen, and may conservatively lead to the production of hydrogen-air layer. The accumulated hydrogen may cause a hazardous flame propagation resulting from any potential ignition sources. This study numerically investigates the processes of ignition and flame propagation in the layered mixture. Simple geometry was chosen to represent the geological repository, and reactive flow simulations were performed with different ignition power, energy, and locations. The simulation results revealed the effects of power and energy of ignition source, which were also analyzed theoretically. The mechanism of layered flame propagation was suggested, which includes three stages: propagation into the hydrogen area, downward propagation due to the product gas, and horizontal propagation along the top wall. To investigate the effect of the ignition source location, simulations with eight different positions were performed, and the boundary of hazardous ignition area was identified. The simulation results were also explained through scaling analysis. This study evaluates the potential risk of the accumulated hydrogen in geological repository, and illustrates the layered flame propagation in related ignition scenarios.

Fuel Cycle Cost Modeling for the Generation IV SFR at the Pre-Conceptual Design Stage

  • Kim, Seong-Ho;Moon, Kee-Hwan;Kim, Young-In
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2009.11a
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    • pp.51-52
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    • 2009
  • Recently, several industrial countries using the fission energy have given attention to the Gen-IV SFR (sodium-cooled fast reactor) for achieving sustainable nuclear energy systems. In this context, an SFR is currently developed at the design concepts study stage in the Republic of Korea [Kim & Hahn 200909]. The sustainability of systems means economic, environment-friendly, proliferation-resistant, and safer systems. More specifically, this sustainability can be accomplished in terms of resource recycling and radioactive waste reduction. In the present work, the objective of fuel cycle cost modeling is to identify the impact of various conceptual options as a cost reduction measure for the Gen-IV SFR at the design concepts study stage. It facilitates the selection of several reasonable fuel cycle pathways for the future Gen-IV SFR from an economic viewpoint.

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Separation and Solidification of Rare Earth Nuclides from LiCl-KCl Based Eutectic Waste Salts using a series of Phosphorylation/Distillation/Solidification Processes (인산화/증류/고화의 일련공정을 이용한 LiCl-KCl 공융염폐기물 내 희토류 핵종 분리 및 고화)

  • Eun, Hee-Chul;Choi, Jung-Hoon;Cho, In-Hak;Park, Hwan-Seo;Park, Geun-Il
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.11 no.4
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    • pp.325-332
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    • 2013
  • Pyroporcessing of spent nuclear fuel generates a considerable amount of LiCl-KCl eutectic waste salt containing radioactive rare earth (RE) chlorides. In this study, a series of processes, which consist of a phosphorylation/distillation process and a solidification process, were performed to minimize volume of the LiCl-KCl eutectic waste salt and solidify a residual waste into a stable form at a relatively low temperature. Over 99wt% of RE chlorides in LiCl-KCl eutectic salt was converted and separated into $REPO_4$ in the phosphorylation/distillation process using a mixture of $Li_3PO_4-K_3PO_4$. The separated $REPO_4$ was solidified into a homogeneous and fine-grained form at $1,050^{\circ}C$ using LIP(Lead Iron Phosphate) as a solidification agent. The final waste volume was reduced below about 10% through the series of the processes.

Structural Stability Analysis of Medical Waste Sterilization Shredder (의료폐기물 멸균분쇄용 파쇄기의 구조적 안정성 분석)

  • Azad, Muhammad Muzammil;Kim, Dohoon;Khalid, Salman;Kim, Heung Soo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.34 no.6
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    • pp.409-415
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    • 2021
  • Medical waste management is becoming increasingly important, specifically in light of the current COVID-19 pandemic, as hospitals, clinics, quarantine centers, and medical research institutes are generating tons of medical waste every day. Previously, a traditional incineration process was utilized for managing medical waste, but the lack of landfill sites, and accompanying environmental concerns endanger public health. Consequently, an innovative sterilization shredding system was developed to resolve this problem. In this research, we focused on the design and numerical analysis of a shredding system for hazardous and infectious medical waste, to establish its operational performance. The shredding machine's components were modeled in a CAD application, and finite element analysis (FEA) was conducted using ABAQUS software. Static, fatigue, and dynamic loading conditions were used to analyze the structural stability of the cutting blade. The blade geometry proved to be effective based on the cutting force applied to shred medical waste. The dynamic stability of the structure was verified using modal analysis. Furthermore, an S-N curve was generated using a high cycle fatigue study, to predict the expected life of the cutting blade. Resultantly, an appropriate shredder system was devised to link with a sterilization unit, which could be beneficial in reducing the volume of medical waste and disposal time, thereof, thus eliminating environmental issues, and potential health hazards.

Teleoperation R&D activities in korean nuclear waste program

  • Bum, T.J.;Jung, W.T.;Lee, J.S.
    • 제어로봇시스템학회:학술대회논문집
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    • 1989.10a
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    • pp.795-798
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    • 1989
  • This paper presents some results of teleoperation R&D activities for radioactive work. Heavy power manipulator feature is integrated with vision system implementation of advanced type and tool adaptation to hand gripper. Some assodiated te datth activities of interests to the teleoperation and future directions are also presented.

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