• Title/Summary/Keyword: 환경폐기물

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Analysis on Heat Transfer Coefficient of The Fluidized - Bed Combustion for Management of Sludge (슬러지 처리를 위한 유동층 연소로의 열전달률 해석)

  • Kim, Seong-Jung;Lee, Je-Hak
    • Journal of the Korea Organic Resources Recycling Association
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    • v.20 no.3
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    • pp.27-33
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    • 2012
  • According to the statistics of the Ministry of Environment, the emission of sewage sludge is increased by 7~9% yearly. In the future, it will be increased continuously because of extension of sewage disposal plants, high class treatment for removing nitrogen and phosphorus. Until now, we have depended on reclamation for lots of quantity and some part has been treated by ocean emission. But, direct reclamation of organic waste will be prohibited and even ocean emission will be prohibited now, so the treatment of sludge is put on emergency alert. Bio-gas can be produced by applying anaerobic digestion method for the recycling or refuse derived fuel can be conducted by applying carbonization method. However, the process is difficult, causes bad smell and makes it the second waste, so it cannot be practical method in fact. This study applied a fluidized bed combustor for sewage sludge treatment technologies that can actually take advantage of key technologies in order to verify its purpose is to demonstrate selected. If applying the fluidized bed combustor, it can be easily utilized as the replaced resource of energy(fuel) in the countries whose energy resources are insufficient, like our country. Especially, if applying only original strengths of the fluidized bed combustor sufficiently, the sewage sludge can be treated simply, eco-friendly, sanitarily and economically. Particularly, it is verified as the energy technology suitable for government's green growth policy.

Membrane Characteristics for Removing Particulates in PFC Wastes (PFC제염폐액 내의 미립자 제거를 위한 여과막의 특성 연구)

  • Kim Gye-Nam;Lee Sung-Yeol;Won Hui-Jun;Jung Chong-Hun;Oh Won-Zin;Park Jin-Ho
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.3 no.2
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    • pp.149-157
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    • 2005
  • PFC(Perfluorocarbon) decontamination process is one of best methods to remove hot particulate adhered at inside surface of hot cell and surface of equipment in hot cell. It was necessary to develop a particulate filtration equipment to reuse PFC solution used on PFC decontamination due to its high cost and to minimize the volume of second wastewater. Contamination characteristics of hot particulate were investigated and then a filtration process was presented to remove hot particulate in PFC solution generated through PFC decontamination process. The removal efficiency of PVDF(Poly vinylidene fluoride), PP(Polypropylene), Ceramic(Al$_{2}$O$_{3}$ filter showed more than 95$\%$. The removal efficiency of PVDF filter was a little lower than those of other kiters at same pressure(3psi). A ceramic filter showed a higher removal efficiency with other filters, while a little lower flux rate than other filters. Due to inorganic composition, a ceramic filter was highly stable against radio nuclides in comparison with PVDF and PP membrane, which generate H$_{2}$ gas in e-radioactivity atmosphere. Therefore, the adoption of ceramic filter is estimated to be suitable for the real nitration process.

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Structural Analysis of the Canister for PWR Spent Fuels under the Korean Reference Disposal Conditions (한국형 기준 처분 환경에서의 PWR 사용후핵연료 처분용기의 구조적 안전성 해석)

  • Choi Heui-Joo;Lee Yang;Choi Jong-Won;Kwon Young-Joo
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.4 no.3
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    • pp.301-309
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    • 2006
  • KDC-1 canister for PWR spent fuels which will be used for the Korean Reference Disposal System was developed. The structural analysis of the canister was carried out as a part of the safety analysis. Two conditions, disposal condition and handling condition, were considered for the structural analysis. Three kinds of load cases, normal, abnormal and rock movement, were considered for the disposal condition. The results of the calculation showed that the safety factors from the structural analysis were greater than the design requirements. Two accident scenarios, gripper failure accident and canister drop accident, were analyzed for the handling condition. According to the gripper failure scenario analysis, the handling machine with grippers could be used even in the cases that one or two grippers failed. The maximum von Mises stress from the canister drop accident scenario was 0.762 MPa, which was negligible compared with the yield stress of nodular cast iron. The proposed KDC-1 canister for PWR spent fuels proves to be safe under the repository condition that is based upon the Korean reference disposal system according to the structural analysis for disposal condition and handling condition.

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Migration and Retardation Properties of Uranium through a Rock Fracture in a Reducing Environment (환원환경에서 암반 균열을 통한 우라늄 이동 및 지연 특성)

  • Baik, Min-Hoon;Park, Chung-Kyun;Cho, Won-Jin
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.2
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    • pp.113-122
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    • 2007
  • In this study, uranium migration experiments have been performed using a natural groundwater and a granite core with natural fractures in a glove-box constructed to simulate an appropriate subsurface environment. Groundwater flow experiments using the non-sorbing anionic tracer Br were carried out to analyze the flow properties of groundwater through the fracture of the granite core. The result of the uranium migration experiment showed a breakthrough curve similar to that of the non-sorting Br. This result may imply that uranium migrates as anionic complexes through the rock fracture since uranium can form carbonate complexes at a given groundwater condition. The distribution coefficient $K_d$ of the uranium between the groundwater and the fracture filling material was obtained as low as 2.7 mL/g from a batch sorption experiment. This result agrees well with the result from the migration experiment, showing a faster elution of the uranium through the rock fracture. In order to analyze retardation properties of the uranium through the rock fracture, the retardation factor $R_d({\sim}16.2)$ was obtained by using the $K_d$ obtained from the batch sorption experiment and it was compared with the $R_d({\sim}14.3)$ obtained by using the result from the uranium migration experiment. The values obtained from the both experiments were very similar to each other. This reveals that the retardation of the uranium is mainly occurred by the fracture filling material when the uranium migrates through the fracture of a granite core.

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Simulation of Rare Earth Elements Removal Behavior in TRU Product Using HSC Chemistry Code (HSC Chemistry 코드를 이용한 TRU 생성물 중의 희토류 원소 제거 거동 모사)

  • Paek, Seungwoo;Lee, Chang Hwa;Yoon, Dalsung;Lee, Sung-Jai
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.18 no.2
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    • pp.207-215
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    • 2020
  • The feasibility of rare earth (RE) removal process via oxidation reactions with UCl3 was investigated using the HSC Chemistry code to reduce the concentrations of RE in transuranic (TRU) products. The composition and thermodynamic data of TRU and RE elements contained in the reference spent fuel were examined. The reactivity was evaluated by calculating equilibrium data considering oxidation reactions with UCl3. Both RE removal rate and TRU recovery rate were evaluated for the two cases, wherein TRU products with different RE concentrations were used. When TRU products were reacted with UCl3, selective oxidation was driven by the difference in the Gibbs free energy of each element. The calculation results imply that the TRU/RE ratio of the final product can be increased by removing RE elements while maintaining the maximum recovery rate of TRU, which is accomplished by controlling the amount of UCl3 injected. Since the results of this study are based on thermodynamic equilibrium data, there are many limitations to apply to the actual process. However, it is expected to be used as an important data for the process design to supply the TRU product of pyroprocessing to SFR's fuel demanding low RE concentrations.

Ocean Circulation Model ing of East Sea for Aquatic Dispersion of Liquid Radioactive Effluents from Nuclear Power Plants (원전 액체 방사성 유출물 해양확산 평가를 위한 동해 해수순환 모델링)

  • Chung Yang-Geun;Lee Gab-Bock;Bang Sun-Young;Lee Ung-Gwon;Lee Yong-Sun
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.321-331
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    • 2005
  • Recently. three-dimensional models have been used for aquatic dispersion of radioactive effluents in relation to nuclear power plant siting based on the Notice No. 2003-12 'Guideline for investigating and assessing hydrological and aquatic characteristics of nuclear facility site' of the Ministry of Science and Technology (MOST) in Korea. Several nuclear power plants have been under construction or planed. which are Shin-Korl Unit 1 and 2, Shin-Wolsong Unit 1 and 2, and Shln-Ulchin Unit 1 and 2. For assessing the aquatic dispersion of radionuclides released from the above nuclear power plants, it is necessary to know the coastal currents around sites which are affected by circulation of East Sea. In this study, a three dimensional hydrodynamic model for the circulation of the East Sea of Korea has been developed as the first Phase, which Is based on the RIAMOM. The model uses the primitive equation with hydrostatic approximation, and uses Arakawa-B grid system horizontally and Z-coordinate vertically. Model domain is $126.5^{\circ}E\;to\;142.5^{\circ}E$ of east longitude and $33^{\circ}N\;and\;52^{\circ}N$ of the north latitude. The space of the horizontal grid was $1/12^{\circ}$ to longitude and latitude direction and vortical level was divided to 20. This model uses Generalized Arakawa Scheme. Slant Advection, and Mode-Splitting Method. The input data were from JODC, KNFRDI, and ECMWF. The model ing results are in fairly good agreement with schematic patterns of the surface circulation in the East Sea The local current model and aquatic dispersion model of the coastal region will be developed as the second phase. The oceanic dispersion experiments will be also tarried out by using ARGO Drifter around a nuclear pelter plant site.

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Characters of Fracture-filling Minerals in the KURT and Their Significance (한국원자력 연구원 지하처분연구시설(KURT)의 단열충전광물 특성과 그 의미)

  • Lee, Seung-Yeop;Baik, Min-Hoon
    • Journal of the Mineralogical Society of Korea
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    • v.20 no.3
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    • pp.165-173
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    • 2007
  • The KAERI Underground Research Tunnel (KURT) located in KAERI (Korea Atomic Energy Research Institute) was recently constructed following the site investigation in 2003. Its dimension is 180 m in length, 6 m in width, and 6 m in height, and it has a horseshoe-like cross-sec-lion and is located in the ground to the depth of 90 m. When the tunnel was dug into the ground with 100 m in length, fresh rocks, weathered rocks and fracture-filling materials were taken and examined by mineralogical and chemical analyses. There are phyllosilicate minerals such as illite, smectite and chlorite including calcite, which are filling some faults and cracks of the KURT rock. The illite and smectite usually coexist in the fracture, where their content ratio is different according to which mineral is predominant. There are high concentrations of U and Th in the rocks coated with iron-oxides and filled with secondary materials as compared with those in the fresh rocks. It seems that the radionuclides, which are slowly leached from the parent rocks or exist as a dissolved form in the groundwater and hydrothermal solution, may have been migrated along the fractures and thereafter selectively sorbed and coprecipitated on the iron-oxides and the fracture-filling materials. These results will be very useful far the evaluation of environmental factors affecting the nuclides migration and retardation when long-term safety is considered to the geological disposal of high-level radioactive wastes in the future.

Properties of Light-weight Expanded Bonded Leather Using Thermal Expandable Microspheres (열 팽창성 Microsphere를 적용한 경량 발포 재생피혁 특성 분석)

  • Shin, Eun-Chul;Kim, Won-Ju;Kim, Yeong-Woo
    • Journal of Adhesion and Interface
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    • v.21 no.3
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    • pp.81-85
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    • 2020
  • Shaving dust is a collagen fiber that is the leather waste occurred for thickness adjustment during the natural leather manufacturing process, and causes problems such as an environmental contamination because of a chromium (Cr) contained when it comes to reclaiming process. Various studies applying the shaving dust are currently being conducted in many countries across the world with an initiative by the EU. Of those applications, the bonded leather is being highlighted as a substitute for natural leather. Since the bonded leather, however, uses latex as a binder, accordingly it entails a high weight and a poor ventilation, which are deemed as disadvantages due to its dense internal tissues compared to other synthetic leathers. To address such disadvantages, this study employed the thermally expandable micro sphere to improve its air permeability and light weight by alleviating the internal structure. This is a study on the manufacturing of light bonded leather using the shaving dusts. In the study, the shaving dusts were forced to foam under 100~120℃ considering the heat resistance of collagen fiber after applying the thermally expandable micro sphere, and then the tendency was analyzed. In the analysis results, the most excellent foaming rate was exhibited when the shaving dusts were treated under 120℃ for 8 minutes and the variation of internal structure according to a foaming was observed through SEM analysis for the cross-section of the bonded leather.

Influence of Characteristics of Hospital Foodservice Operation and Dietitian on Performance of HACCP Prerequisite Program (병원 급식소와 영양사의 특성이 HACCP 선행요건 수행도에 미치는 영향)

  • Song, Yoon-Ji;Bae, Hyun-Joo
    • Korean journal of food and cookery science
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    • v.32 no.1
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    • pp.107-113
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    • 2016
  • The purpose of this study was to analyze factors that influence prerequisite program (PRP) performance of hospital foodservice operation. Data was collected through surveys given to 65 dietitians working in general hospital with ${\geq}100beds$. Importance score of sanitary management for the self-operated establishments was significantly higher than that of contract-managed in the areas of working environment management (p<0.01), waste management (p<0.05), clean disinfection management (p<0.05). Performance score of hospitals with ${\leq}300beds$ was significantly lower than that of hospitals with ${\geq}300beds$ in personal hygiene management (p<0.05). Moreover, importance score of dietitians spending ${\geq}3hours$ on inspection time was significantly higher than that of dieticians spending ${\leq}3hr$ in waste management area. According to the results of Pearson correlation analysis, PRP performance score was positively related with dietitian's career (p<0.05), number of submitted beds (p<0.05), cooking process inspection time (p<0.05), dietitian's job satisfaction (p<0.01), and holding rate of utensil and equipment (p<0.05). In addition, the results of multiple regression analysis showed that dietitian's job satisfaction (p<0.001) and holding rate of utensil and equipment (p<0.05) had a significant positive effect on prerequisite program performance. In conclusion, improvement of working condition to increase dietitian's job satisfaction and securing of utensils and equipments are high priorities for improvement of PRP performance.

Properties of Concrete Panel Made by Light Weight Aggregates (인공경량골재로 제조된 콘크리트 패널의 물성)

  • 엄태호;김유택
    • Journal of the Korean Ceramic Society
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    • v.41 no.3
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    • pp.221-228
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    • 2004
  • Basic properties of artificial lightweight aggregate by using waste dusts and strength properties of LWA concrete were studied. Bulk specific gravity and water absorption of artificial lightweight aggregates varied from 1.4 to 1.7 and 13 to 16%, respectively. Crushing ratio of artificial lightweight aggregate was above 10% higher than that of crushed stone or gravel. As a result of TCLP leaching test, the leaching amount of tested heavy metal element was below the leaching standard of hazardous material. Slump, compressive strength and stress-strain properties of LWA concrete made of artificial lightweight aggregate were tested. Concrete samples derived from LWA substitution ratio of 30 vol% and W/C ratio of 45 wt% showed the best properties overall. Thermal insulation and sound insulation characteristics of light weight concrete panel with the optimum concrete proportion were tested. Average overall heat transmission of 3.293W/㎡$^{\circ}C$ was observed. It was higher by about 15% than those of normal concrete made by crushed stone. Sound transmission loss of 50.9 ㏈ in frequency of 500 ㎐ was observed. It was higher by about 13% than standard transmission loss.