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

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Landfill gas-landfill degassing system and methods of using landfill gas at Sarajevo landfill

  • Dzevad Imamovic;Amra Serdarevic
    • Coupled systems mechanics
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    • v.12 no.6
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    • pp.531-537
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    • 2023
  • Municipal solid waste landfills are unpredictable bioreactors which in cases of mishandling and bad supervision presents numerous risks. The key to municipal waste landfills is to approach them from the point of prevention of the possible consequences, which means using methods of organized waste disposal, and also utilizing landfill gas, as an unavoidable consequence with disposal of municipal solid waste with a high share of biodegradable organic matter. This paper presents an overview about problems of solid municipal waste management, type and composition of waste, and an overview of waste management condition. Further, the problem of landfill and landfill gasses is described with the calculation models of landfill production, as well as the use of the SWM GHG Calculator and LandGEM software on a specific example of gas production for the central zone at Sarajevo landfill "Smiljevici". Main focus of this thesis is the analysis of potentials of greenhouse gas emission reduction measures from the waste management. Overview of the best available techniques in waste management is presented as well as the methodology used for calculations. Scenarios of greenhouse gas emission reduction in waste management were defined so that emissions were calculated using the appropriate model. In the final section of the paper, its description of the problem of collection and utilization the landfill gas at the sanitary landfill "Smiljevici", and implementation of the system for landfill gas collection and solution suggestion for the gasification and exploitation of gas. Energy, environmental and economic benefits can be accomplished by utilizing municipal solid waste as fuel in industry and energy and moreover by utilizing energy generation from landfill gas, which this thesis emphasizes.

Development of Source Dechlorination Process for Waste Vinyls (폐비닐류의 원천 탈염공정 개발)

  • Chung, Soohyun;Na, Jeonggeol;Lee, Jonghyuk;Woo, Hee Myung
    • 한국신재생에너지학회:학술대회논문집
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    • 2011.05a
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    • pp.186.1-186.1
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    • 2011
  • Most of waste plastics including waste vinyls have been recycled up to about 50% of waste production, 4.5 million ton per year in 2009. To fundamentally increase the recycled amounts of waste plastics to waste production, the energy utilization of waste plastics is inevitable. But the contents of PVC included in waste plastics can limit the use as a RPF and make the air pollutants such as HCl and dioxin when it burns in the combustion system. Accordingly the source dechlorination by using heating method can be applied to make low contents of HCl as less than 0.6%. In this study the twin screw reactor using heat medium was used for the source dechlorination. As results of study, it was considered that this system is effective for the industrilal application.

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Comparative Evaluation of Various Standard Methods in Leaching Test of Radioactive Waste Form (방사성고화체로부터의 $^{60}$ Co, $^{137}$ Cs 침출에 대한 표준시험법의 상호비교)

  • Kim, Ki-Hong;Ryu, Young-Gerl;Chung, Kyung-Ki;Hong, Kwon-Pyo;Lee, Nak-Hee;Jeong, Yi-Yeong;Koh, Duck-Joon;Kim, Heon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.1 no.1
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    • pp.93-103
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    • 2003
  • IAEA, FT-04-020, and ANS 16.1, standard leaching test methods, were evaluated comparatively with their test results. Leaching index of $^{60}$ Co and $^{137}$ Cs by ANS 16.1 method for waste forms of paraffin and cement were above 6.0. Their leaching behavior were depending on the type of matrix and leachant. Leachability of $^{60}$ Co for cement waste form was higher in simulated seawater than do-mineralized water, and was higher in de-mineralized water for paraffin waste form. leachability of $^{60}$ Co was contrary to $^{137}$ Cs. Cumulative fraction leached of $^{60}$ Co was higher in order or IAEA > ANS > FT in a cement waste form.

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EUTECTIC(LiCl-KCl) WASTE SALT TREATMENT BY SEQUENCIAL SEPARATION PROCESS

  • Cho, Yung-Zun;Lee, Tae-Kyo;Choi, Jung-Hun;Eun, Hee-Chul;Park, Hwan-Seo;Park, Geun-Il
    • Nuclear Engineering and Technology
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    • v.45 no.5
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    • pp.675-682
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    • 2013
  • The sequential separation process, composed of an oxygen sparging process for separating lanthanides and a zone freezing process for separating Group I and II fission products, was evaluated and tested with a surrogate eutectic waste salt generated from pyroprocessing of used metal nuclear fuel. During the oxygen sparging process, the used lanthanide chlorides (Y, Ce, Pr and Nd) were converted into their sat-insoluble precipitates, over 99.5% at $800^{\circ}C$; however, Group I (Cs) and II (Sr) chlorides were not converted but remained within the eutectic salt bed. In the next process, zone freezing, both precipitation of lanthanide precipitates and concentration of Group I/II elements were preformed. The separation efficiency of Cs and Sr increased with a decrease in the crucible moving speed, and there was little effect of crucible moving speed on the separation efficiency of Cs and Sr in the range of a 3.7 - 4.8 mm/hr. When assuming a 60% eutectic salt reuse rate, over 90% separation efficiency of Cs and Sr is possible, but when increasing the eutectic salt reuse rate to 80%, a separation efficiency of about 82 - 86 % for Cs and Sr was estimated.

Study on a Phosphorylation of Rare Earth Nuclide (Nd) in LiCl-KCl-NdCl3 System using Li3PO4-K3PO4 (LiCl-KCl-NdCl3계에서 Li3PO4-K3PO4를 이용한 희토류 핵종(Nd) 인산화에 관한 연구)

  • Eun, Hee-Chul;Kim, Jun-Hong;Choi, Jung-Hoon;Cho, Yung-Zun;Lee, Tae-Kyo;Park, Hwan-Seo;Park, Geun-Il
    • Journal of Advanced Engineering and Technology
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    • v.6 no.2
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    • pp.125-129
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    • 2013
  • In the pyrochemcial process of spent nuclear fuel, it is necessary to separate rare earth nuclides from LiCl-KCl eutectic waste salt for radioactive waste reduction. This paper presents the phosphorylation of neodymium chloride in LiCl-KCl-NdCl3 system using Li3PO4-K3PO4 as a phosphorylation agent in a chemical reactor with pitched blade impellers. The phosphorylation test was performed changing operation temperature, stirring rate, and amount of phosphorylation agent. Neodymium chloride was effectively converted into neodymium phosphate (NdPO4). It was confirmed that more than 99 wt% of neodymium can be separated from LiCl-KCl-NdCl3 system using a phosphorylation method l

An Experimental Study on Thermoelectric Generator Performance for Waste Coolant Recovery Systems in Vehicles (자동차 냉각수 폐열회수 열전발전 시스템의 성능에 관한 연구)

  • Lee, Dae-Woong
    • Korean Journal of Air-Conditioning and Refrigeration Engineering
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    • v.26 no.7
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    • pp.329-334
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    • 2014
  • This study indicated the possibility of energy regeneration from waste coolant heat, by using thermoelectric generation integrated with heat pipe. The internal combustion engine rejects more than 60% wasteful energy to the atmosphere by heat. The thermoelectric generator has recently been studied, to convert the energy from engine waste heat into electricity. For coolant waste heat recovery, a thermoelectric generator was investigated, to find out the possibility of vehicular application. Performance characteristics were conducted with various test conditions of coolant temperature, coolant mass flow rate, air temperature, and air velocity, with the thermoelectric generator installed either horizontally or vertically. Experimental results show that the electric power and conversion efficiency increases according to the temperature difference between the hot and cold side of the thermoelectric generator, and the coolant flow rate of the hot side heat exchanger. Performance improvement can be expected by optimizing the heat pipe design.

The structural and non-linear dynamic analysis for radioactive waste container

  • Yu-Yu Shen;Kuei-Jen Cheng;Hsoung-Wei Chou
    • Nuclear Engineering and Technology
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    • v.55 no.8
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    • pp.3010-3016
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    • 2023
  • In recent years, the development of radioactive waste containers for nuclear facility decommissioning and dismantling is a critical issue because the Taiwan domestic boiling water reactor nuclear power plant is going to be decommissioned. The main purpose of this research is to design a metal container that meets the structural requirements of related regulations. At first, the shielding analysis was performed by varying dimensions of radioactive waste to determine the storage efficiency of the container. Then, a series of structural analyses for operational and accidental conditions of the container with full load were conducted, such as lifting, stacking, and drop impact conditions. On the other hand, the field drop impact tests were carried out to ensure structural integrity. The present research demonstrates the structural safety of the developed container for decommissioned nuclear facilities in Taiwan.

Characterization of Cement Waste Form for Final Disposal of Decommissioned Concrete Waste (해체 콘크리트 폐기물 최종처분을 위한 시멘트 고화체 특성 평가)

  • Lee, Yoon Ji;Hwang, Doo Seong;Lee, Ki Won;Jeong, Gyeong Hwan;Moon, Jei Kwon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.11 no.4
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    • pp.271-280
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    • 2013
  • Since the decommissioning of nuclear plants and facilities, large quantities of slightly contaminated concrete waste have been generated. In Korea, the decontamination and decommissioning of the KRR-1, 2 at the KAERI have been under way. And concrete waste was generated about 800 drums of 200 L. The conditioning of concrete waste is needed for final disposal. The concrete waste is conditioned as follows: mortar using coarse and fine aggregates is filled void space after concrete rubble pre-placement into 200 L drum. Thus, this research has developed an optimizing mixing ratio of concrete waste, water, and cement and has evaluated characteristics of a cement waste form to meet the requirements specified in disposal site specific waste acceptance criteria. The results obtained from compressive strength test, leaching test, thermal cycling test of cement waste forms conclude that the concrete waste, water, and cement have been suggested to have 75:15:10wt% as the optimized mixing ratio. Also, the compressive strength of cement waste form was satisfied that including fine powder up to maximum 40wt% in concrete debris wastes about 75%. As a result of scale-up test, the mixture of concrete waste, water, and cement is 75:10:15wt% meet the satisfied compressive strength because the free water increased with and increased in particle size.

Environmental Load Assessment of Municipal Solid Waste using LCA (LCA를 통한 도시 고형 페기물의 환경부하평가)

  • ;Susumu Tohno;Mikio Kasshara
    • Journal of Environmental Science International
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    • v.12 no.6
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    • pp.643-650
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    • 2003
  • We analyzed the amount of environmental loads, and the amount of energy consumption through life cycle assessment from a discharge stage to the ultimate disposal to municipal solid waste in Seoul. We carried out inventory analysis of the amount of environmental loads that made the object range collection, intermediate treatment, and the final treatment, and took into consideration each stage exceptions CO$_2$ and NOx , the amount of SOx discharge, and energy consumption. We applied the data of an object model, and acquisition processed the scale of an object model suitably and applied to it to difficult data using the data of the Yokohama City incineration plant in Japan. The amount of environmental loads per Iton of municipal waste were analyzed CO$_2$ 0.4C-ton, SOx 0.4kg and NOx 0.8kg. Moreover, the amount of energy consumption which is 2.4Gcal was computed.