[보고서]고방사능 시설 운영 및 해체 폐기물 처리기술 개발

보고서 정보

주관연구기관

한국원자력연구원
Korea Atomic Energy Research Institute

보고서유형

2단계보고서

발행국가

대한민국

언어

한국어

발행년월

2012-02

과제시작연도

2011

주관부처

교육과학기술부
Ministry of Education and Science Technology(MEST)

등록번호

TRKO201300013488

과제고유번호

1345156916

사업명

원자력기술개발

DB 구축일자

2013-08-26

키워드

콘크리트폐기물.HEPA 필터 폐기물.유기 혼성폐기물.저준위화.감용.수증기개질.Concrete waste.HEPA filter waste.Organic mixed waste.Down grading.Volume reduction.Steam reforming.

DOI

https://doi.org/10.23000/TRKO201300013488

표 Jaw crusher.
표 Kind of crusher and characteristics
표 Gyratory crusher.
표 Cone crusher.
표 Impact crusher.
표 Roll crusher.
표 Ball mill.
표 Road mill
표 Heating and crushing process.
표 Moving shape of ball in rotating mill.
표 Schematic for application of microwave.
표 DECO process of KEMA.
표 Plant of KEMA test.
표 Separated gravel and contaminated fine powder.
표 Test-runs
표 Modified mechanical grinding system in NUPEC.
표 Air-heating and grinding process.
표 Transformation of aggregate by heating.
표 Floor shaver.
표 Automatic wall shaver.
표 Isotron electro-sorb process.
표 AWD-CON process.
표 ROVCO2 surface decontamination equipment.
표 Soda blasting equipment.
표 Flow sheet of steel scrap.
표 Specification of shielding block.
표 Deep and shallow disposal facility.
표 (a) Decision tree (Part A).
표 (b) Decision tree (Part B).
표 Flow sheet of Scenario 1.
표 Flow sheet of Scenario 2.
표 Flow sheet of Scenario 3.
표 Flow sheet of Scenario 4.
표 Flow sheet of Scenario 5.
표 Flow sheet of Scenario 6.
표 Average scenario costs for facilities.
표 Scenario costs for a medium building.
표 Example of overseas limited recycling of dismantled concrete waste.
표 Disposal canister and packing drum of radioactive waste.
표 Schematic diagram of waste drums in concrete box in the VLJ-Repository
표 XRD patterns of the heavy and the light weight concrete wastes.
표 Effect of the heating temperature on the separation of aggregate from the heavy concrete.
표 Effect of the heating temperature on the separation of aggregate from the light concrete
표 Effects of the heating temperature on the separation of aggregates and the distribution of cobalt.
표 Effects of the heating temperature on the separation of aggregates and the distribution of cobalt
표 Effect of washing with water on the specific activity of Co-60 in the aggregates separated from the light concrete
표 Effect of washing with water on the specific activity of Co-60 in the aggregates separated from the heavy concrete.
표 Effect of the number of ball milling on the specific activity of Co-60 in the aggregates separated from the light concrete
표 Effect of the number of ball milling on the specific activity of Co-60 in the aggregates separated from the heavy concrete
표 The specific activity of aggregates separated from the light concrete waste after completing second milling
표 The distribution characteristics of aggregates separated from the light concrete waste after completing second milling.
표 The distribution characteristics of aggregates separated from the heavy concrete waste after completing second milling
표 The specific activity of aggregates separated from the heavy concrete waste after completing second milling
표 High temperature slagging for the fine powder produced from the light and the heavy concrete
표 Volume reduction of the fine powder by high temperature slagging in an arc furnace
표 Comparison of compressive strength by heating time.
표 Relation of stress-transformation by heating time.
표 Comparison elasticity by heating time.
표 Comparison of compressive strength with elasticity coefficient.
표 Relation of stress and transformation by heating time.
표 Poission' s ratio by heating time.
표 Crushing model of binary system.
표 Locking Index(LI) concept and schematic.
표 Air flow pattern and dominant particle streams in a Zig-Zag Moving Bed process
표 Schematic representation of the particles classification, in which the previous history of the particle trajectory is taken into account
표 Dominant particle flow rates in four complementary regions.
표 Particle flow rates between the stage of a Zig-Zag moving bed for completely absorbing product exits
표 Illustration of the connection between U0(i) for consecutive values of i.
표 Experimental apparatus.
표 The geometry of the stage in a Zig-Zag Type Moving Bed.
표 Details of sampling port from the Moving Bed.
표 Characteristics of gas distribution and inlet section.
$Effects of sand size in the feed material on the fraction of sand in the overhead products$ 표 Effects of sand size in the feed material on the fraction of sand in the overhead products
$Effects of sand size in the feed material on the fraction of sand in the bottom products$ 표 Effects of sand size in the feed material on the fraction of sand in the bottom products
$Effects of feed rate(RF) on the fraction of overhead products$ 표 Effects of feed rate(RF) on the fraction of overhead products
$Effects of feed rate(RF) on the fraction of bottom products$ 표 Effects of feed rate(RF) on the fraction of bottom products
$Effects of gas velocity(UG) on the fraction of overhead products$ 표 Effects of gas velocity(UG) on the fraction of overhead products
$Effects of gas velocity(UG) on the fraction of bottom products$ 표 Effects of gas velocity(UG) on the fraction of bottom products
$Effects of mixing ratio of powder(RF) on the fraction of overhead products$ 표 Effects of mixing ratio of powder(RF) on the fraction of overhead products
$Effects of mixing ratio of powder(RF) on the fraction of overhead products$ 표 Effects of mixing ratio of powder(RF) on the fraction of overhead products
표 Effects of feed material on gas velocity(UG) efficiency(Etot) in the zig-zag moving bed
표 Effects of gas velocity(UG) on the total separation efficiency(Etot) in the zig-zag moving bed
표 Effects of feed rate(RF) of feed material on the total separation efficiency(Etot) in the zig- zag moving bed
표 Effects of mixing ratio(RM) in the feed material on the total separation efficiency (Etot) in the zig-zag moving bed
표 Effects of mixing ratio(RM) in the feed material on the total separation efficiency (Etot) in the zig-zag moving bed
표 Effects of sand size in the feed material on the grade efficiency(G(x)) of sand in the Zig-Zag moving bed
표 Process concept for a volume reduction and self-disposal of dismantled concrete waste
표 Test for a volume reduction of dismantled concrete waste.
표 Change of specific activity after sieving of the activated heavy weight concrete waste
표 Change of specific activity after crushing and heating of the activated heavy weight concrete waste.
표 Distribution of the aggregates after heating and milling of the activated heavy concrete.
표 Overall distribution of the aggregates after heating and milling of the activated heavy weight concrete
표 Distribution of the specific activity for the aggregate size form of uranium contaminated light weight concrete waste
표 Specific activity and distribution of aggregate after a heating and milling of the contaminated uranium concrete waste.
표 Specific activity and distribution of aggregate after a heating and milling of the contaminated mortar concrete waste
표 Absorption ratio of aggregated after heating and crushing.
표 Dry density of separated aggregates
표 60 Temperature change of aggregate surface into the heating chamber
표 Maximum temperature of the concrete w.r.t time.
표 Minimum temperature of the concrete w.r.t time.
표 Integrated thermal and mechanical treatment.
표 Process equipment for milling and crushing.
표 Lab-scale demonstration of thermal and mechanical treatment.
표 Distribution of aggregate by bench-scale demonstration.
표 Absorption radio of separated aggregates by lab scale demonstration
표 Specific activity of the aggregates separated from activated concrete waste
표 Distribution of the aggregates separated from activated concrete waste.
표 Specific activity of the aggregates separated from UCP concrete waste.
표 Distribution of the aggregates separated from concrete waste.
표 Bench-scale demonstration equipment for the treatment of concrete waste
표 Sequence of the demonstration test.
표 Distribution of the aggregates separated from activated concrete waste after demonstration test
표 Specific activity of the aggregates separated from activated concrete waste after demonstration test
표 Distribution of the aggregates separated from UCP concrete waste after demonstration test.
표 Specific activity of the aggregates separated from UCP concrete waste after demonstration test
표 Schematic of pilot plant.
표 Distribution of concrete fine powder below 1mm.
표 Specific activity of light weight concrete fine powder
표 Removal efficiency of radionuclide form in various leaching solution
표 Removal efficiency of radionuclide by electrochemical leaching
표 Picture of electrochemical leaching test.
표 Removal efficiency of uranium according to the kind of leachant.
표 Removal efficiency of uranium according to the concentration of HNO3
표 Removal efficiency of uranium according to the scrubbing time
표 Removal efficiency of uranium according to the size of concrete fine powder
표 Removal efficiency of uranium according to the number of scrubbing cycle
표 Change of the radionuclide concentration for activated concrete fine powder by electrochemical leaching
표 Process diagram of chemical leaching for concrete fine powder.
표 Demonstration scale (15L) of chemical leaching equipment.
표 Design concept for chemical leaching system.
표 Removal efficiency of radionuclide by scrubbing cycle
표 TG-DTA analysis of the light weight concrete fine powder.
표 TG-DTA analysis of the heavy weight concrete fine powder.
표 XRD pattern of the light weight concrete fine powder.
표 XRD pattern of the heavy weight concrete fine powder.
표 Compressive strength of cemented waste form using light weight concrete fine powder
표 Compressive strength of cemented waste form using heavy weight concrete. fine powder
표 Compressive strength of cemented waste form using light concrete fine powder with sodium silicate
표 Compressive strength of cemented waste form using heavy concrete fine powder with sodium silicate
표 Compressive strength of cemented waste form using heavy concrete fine powder with MgO
표 Compressive strength of cemented waste form using light concrete fine powder with MgO
표 Leachability index of Cs-137 and Co-60 performed by ANS 16.1.
표 Activity of leached solution of cement waste with sodium silicate
표 Leachability index of cemented waste form with MgO.
표 Leachability index of cemented waste form with sodium silicate.
표 Picture of slagged concrete waste form and measurement of compressive strength
표 Compressive strength of slagged waste form.
표 Leach rate of radionuclides from the slagged sample by slagging
표 SEM images of slagged samples
표 Leached rate of radioactive slagged sample (PCT Leach Test, 7days)
표 HEPA Filter leaching System in INEEL.
표 A schematic diagram of the apparatus used for packed column leaching.
표 Proposed chemical flowsheet for recovery of actinides from filters.
표 Algorism of 4 step process in WINCO.
표 Schematic diagram for Pilot-scale waste Filter dissolution process.
표 Separated type HEPA filter
표 V-plate type HEPA filter
표 The distribution of radionuclides in HEPA filter media.
표 SEM image after capturing particles.
표 A schematic diagram of electrochemical leaching.
표 Radioactive concentration during leaching by 4.0M HNO3-0.1M Ce(IV) solution
표 Mixing of glass fibers with NaOH solution for leaching
표 Radioactive concentration during leaching by 5 wt% NaOH solution
표 Pressure filtration after 2.0 M HNO3 solution leaching
표 Radioactive concentration during repetition leaching by 2.0 M HNO3 solution
표 Radioactive concentration during repetition leaching by 4.0 M HNO3 solution
표 Results of precipitation-filtration treatment for reuse of 4.0 M HNO3 waste-solution contaminated with cobalt and cesium
표 Radioactive concentration of metal in 4.0 M HNO3 waste-solution before and after precipitation and filtration
표 Radioactive concentration during leaching by 4.0 M HNO3-0.1M Ce(IV)solution
표 Radioactive concentration during leaching by 0.5 M H2O2-1.0M Na2CO3 solution
표 Radioactive concentration during leaching by 4.0M HNO3 solution.
표 Radioactive concentration during repetition leaching by 4.0M HNO3 solution
표 Results of precipitation-filtration treatment for reuse of 4.0 M HNO3 waste-solution contaminated with uranium
표 Radioactive concentration of metal in 4.0 M HNO3 waste-solution before and after precipitation and filtration
표 TGA analysis for HEPA filter media
표 TGA analysis for sealant.
표 Thermal treated HEPA filter meida at 800℃.
표 Thermal treated HEPA filter meida at 900℃.
표 Diagram for thermal treatment of HEPA filter waste.
표 Volatility test for low concentration of heavy metals.
표 Volatility test for high (10 wt.%) concentration of heavy metals.
표 Leachability test for heavy metals and surrogate nuclides.
표 XRD data for (a) thermal treated HEPA filter media, HEPA filter media reacted with (b) ZnO, (c) PbO, and (d) SrO by thermal treatment
표 XRD data for HEPA filter media reacted with CrO3, Co(NO3)2·6H2O and CsNO3 by thermal treatment
표 XRD data for the effect of temperature for HEPA filter media reacted with ZnO by thermal treatment
표 Development for the treatment flowsheet of low level radioactivity HEPA filter waste
표 Development for the treatment flowsheet of high-level radioactivity HEPA filter waste
표 Laboratory-size HEPA glass fiber leaching equipment image
표 Contaminated glass fiber sampled from HEPA filter waste
표 Leaching experiment by HEPA glass fiber leaching equipment.
표 Filtrate and glass filter after leaching.
표 Uranium concentration during repetition leaching by 4.0 M HNO3 solution
표 Results after leaching experiment for HEPA glass fiber contaminated with uranium
표 Cobalt and cesium concentrations during repetition leaching by 4.0 M HNO3 solution
표 Results after leaching experiment for HEPA glass fiber contaminated with cobalt and cesium
표 Demonstration-size HEPA filter leaching equipment process diagram
표 Demonstration -size HEPA filter leaching equipment design drawing
표 Demonstration-size HEPA glass fiber leaching equipment specification
표 Demonstration-size HEPA glass fiber leaching equipment image
표 Manufactured demonstration-size HEPA filter leaching equipment
표 Preparation for Cold HEPA filter leaching experiment.
표 Improvement items of demonstration-size HEPA glass fiber leaching equipment
표 In the course of cold HEPA filter leaching experiment.
표 After cold HEPA filter leaching experiment.
표 Establishment in leaching equipment of hot HEPA filter
표 Leaching experiment of hot HEPA filter.
표 Results of demonstration-size HEPA glass fiber leaching experiment
표 After leaching experiment completion of hot HEPA filter
표 Filter frame after leaching experiment completion of hot HEPA filter
표 Results of precipitation-filtration of waste-solution.
표 Pictures before and after precipitation of leaching waste-solution
표 Residual radioactivity of main element in waste-solution after precipitation-filtration
표 Leaching experiment sequence for separator
표 HEPA filter separator.
표 Leaching experiment results for separator
표 Leaching experiment results for separator.
표 Leaching experiment sequence for sealant
표 Leaching experiment results for sealant
표 Leaching experiment results for sealant.
표 Volume reduction of HEPA filter media by thermal treatment.
표 Separation test for HEPA filter media and aluminum separator.
표 Compressive strength and microhardness for thermal treated sample.
표 The detail drawing of graphite crucible
표 The volume reduction in non-contaminated HEPA filter media by thermal treatment
표 The volume reduction and volatility test in radioactive HEPA filter media by thermal treatment
표 Volatility test for radioactivity HEPA filter media.
표 Process flow diagram for the Direct Chemical Oxidation rocess
표 Waste Steam Reforming Plant Developed by Thermochem
표 Thermodynamic Equilibrium Data for Selected Steam Reforming
표 Process flow diagram of gas-phase reduction process
표 Gas-Phase Reduction of Hazardous Organics Constituents
표 Weight reduction pattern of two uranium-bearing TBP-dodecane waste and pure TBP at elevated temperatures under N2 atmosphere
표 Morphology of pyrolysis residue of uranium-bearing TBP/dodecane organic liquid and its further oxidation residue
표 Results of elemental analysis of pyrolysis residue of uranium-bearing TBP/dodecane organic liquid and its further oxidation residue
표 Powdered XRD patterns of pyrolysis residue (a) and combustion
표 Overall reaction pathway of pyrolysis and gasification of uranium-bearing TBP
표 A schematic diagram of lab-scale (0.2 kg-TBP/h) steam reforming process for the treatment of alpha-bearing mixed waste
표 Installed lab-scale (0.2 kg-TBP/h) steam reforming process for the treatment of alpha-bearing mixed waste.
표 Samples of two Uranium -bearing TBP-dodecane waste solvents and pure TBP for the analysis of their pyrolysis gas at different temperatures.
표 Analysis of pyrolysis gas composition of two uranium-bearing TBP/dodecane waste at 320°C, based on the pyrolysis-GC/MS analysis
표 Analysis of pyrolysis gas composition of two uranium-bearing TBP/dodecane waste at 600°C, based on the pyrolysis-GC/MS analysis
표 Analysis of pyrolysis gas composition of two uranium-bearing TBP/dodecane waste at 750°C, based on the pyrolysis-GC/MS analysis
표 A schematic diagram of MEO process for NOx removal
표 Lab-scale MEO process equipment for the removal of acid gases
표 Parametric study of steam reformer for gaseous mixtures from the pyrolysis of waste TBP solution
표 Gas residence time in steam reforming PFR at different steam feed rates, as a function of temperature and reactor length
표 Generation and decomposition of butadiene at different steam feed rates, as a function of temperature and reactor length
표 Decomposition of butadiene at different steam feed rates, as a function of temperature and reactor length
$Mole fraction of incompletely oxidized species at the outlet of steam reforming PFR at different steam feed rates, as a function of temperature and reactor length$ 표 Mole fraction of incompletely oxidized species at the outlet of steam reforming PFR at different steam feed rates, as a function of temperature and reactor length
표 Influence of gas volumetric flow rate of 16,000-98,000 SCCM (GHSV of 10000-60000) on the oxidation efficiency of total UHCs (top figures) and emission concentrations of each UHC species (bottom figures) at three different temperatures: a) 500°C, b) 525°C and c) 550°C
$Temperature effect on the reactor performance at φ = 0.2 and GHSV = 20000h-1: (a)oxidation efficiency(η), (b) outlet mole fraction of feed UHCs, and (c) outlet mole fraction of newly generated UHCs$ 표 Temperature effect on the reactor performance at φ = 0.2 and GHSV = 20000h-1: (a)oxidation efficiency(η), (b) outlet mole fraction of feed UHCs, and (c) outlet mole fraction of newly generated UHCs
표 Changes in NO concentration with respect to time as a function of current density
표 Changes in NO2 concentration during the removal of NO with respect to time as a function of current density
표 Changes in NO concentration and NO removal efficiency by scrubbing liquid with and without Ag(II) accumulation before commencing the gas removal experiment, as a function of time
표 Effect of accumulation time of Ag(Ⅱ) before commencing the gas removal experiment on NO concentration
표 Effect of AgNO3 concentration on NO removal efficiency
표 Effect of HNO3 concentration at anodic solution for the removal of NO2
표 Effect of HNO3 concentration at anodic solution for the removal of NO
표 Effect of scrubbing liquid flow rate on NO removal efficiency
표 Effect of gas flow rate on NO removal efficiency
표 Effect of HNO3 concentrations on NO2 removal efficiency in gas scrubber II
표 Effect of sodium sulfite concentration for the removal of NO2
표 Effect of sodium sulfide concentration for the removal of NO2.
표 Changes in NO, NO2, and NOX concentrations with respect to time and the removal efficiencies of NOX through gas scrubber Ⅰ,Ⅱ
표 TGA results of (U(PO3)4) with a heating rate of 1 °C/min under inert atmosphere
표 TGA results of (U(PO3)4) with a heating rate of 2 °C/min under inert atmosphere
표 Fig. 3.35. TGA results of (U(PO3)4) with a heating rate of 3 °C/min under inert atmosphere
표 TGA results of (U(PO3)4) with a heating rate of 4 °C/min under inert atmosphere
표 Plots of ln(B/T1.894661) versus 1/T for determination of activation energy, E.
표 Activation energy of the conversion of uranium metaphosphate (U(PO3)4) into uranium pyrophosphate (UP2O7), as function of conversion, α
표 Master plots of theoretical g(a)/g(0.5) against a for various reaction models (solid lines, as enumerated in Table 3.6) and experimental values of p(y)/p(0.5) for different O2 conditions
표 Determination of Z(=k0) values by plotting g(a) against (E/BR)p(y) for different O2 condtitions
표 Reaction progress of U(PO3)4 into UP2O7 at given temperatures, as afunction of time

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고방사능 시설 운영 및 해체 폐기물 처리기술 개발
Development of Technology for Treatment of Wastes from High Radioactive Facilities in Operation or under Decommissioning 원문보기

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고방사능 시설 운영 및 해체 폐기물 처리기술 개발 Development of Technology for Treatment of Wastes from High Radioactive Facilities in Operation or under Decommissioning 원문보기

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고방사능 시설 운영 및 해체 폐기물 처리기술 개발
Development of Technology for Treatment of Wastes from High Radioactive Facilities in Operation or under Decommissioning 원문보기

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