[보고서]해체폐기물 고도감용 기술 개발

이근영

보고서 정보

주관연구기관

한국원자력연구원
Korea Atomic Energy Research Institute

연구책임자

이근영

참여연구자

김광욱 , 양희철 , 김익수 , 정동용 , 은희철 , 김형주 , 서범경 , 문제권 , 최종원 , 안병길 , 민병연 , 양인환 , 리차드 인 포스터 , 손성준 , 최윤정 , 권수민 , 김민정 , 김지민 , 이시영 , 오맹교 , 손우정 , 성현희 , 김성준 , 양다솜 , 조승연 , 김원석 , 강석태 , 배윤상

보고서유형

1단계보고서

발행국가

대한민국

언어

한국어

발행년월

2019-12

과제시작연도

2019

주관부처

과학기술정보통신부
Ministry of Science and ICT

등록번호

TRKO202100002080

과제고유번호

1711082258

사업명

원자력기술개발사업(R&D)

DB 구축일자

2021-06-12

키워드

해체.방사성폐기물.부피감용.안정화.공정개발.Decommissioning.Radioactive waste.Volume reduction.Stabilizatoin.Process development.

표 Schematic diagram of radioactive concrete waste
표 Conceptual diagram of cement, paste and mortar
표 Chemical analysis of concrete waste powder by EDS, XRF, ICP
표 Particle size distribution of concrete waste powder
표 Particle size distribution of concrete waste before and after dissolution
표 True density of concrete waste powder
표 Dissolution yield of (A) aggregate and (B) cement with different conditions
표 SEM-EDS results of concrete particles, above 1mm, after pulverization with heat-treatment. (A) before dissolution, (B) after dissolution using HCl solution
표 Variation of existing concrete composition above 1 mm particle size depending on milling time (using small size milling ball)
표 Variation of existing concrete composition above 1 mm sized particles depending on heating temperature
표 Results of (A) distribution rate(%) and (B) existing concrete composition above 1 mm sized particles, using optimized milling time and heating temperature with different heating time
표 Results of (A) distribution rate(%) and (B) existing concrete composition above 1mm sized particles with different milling ball size
표 Variation of existing concrete composition above 1 mm sized particles with different milling time using middle size milling ball
표 Variation of existing concrete composition above 1 mm sized particles with different milling time using big size milling ball
표 Variation of existing concrete composition above 1 mm sized particles with different heating time
표 Variation of weight(%) of concrete with increasing temperature
표 Distribution of (A) cement and (B) aggregate in the particles separated by different heating temperatures
표 Distribution of (A) cement and (B) aggregate in the particles separated by different heating time
표 (A) Distribution of aggregate and fine power and (B) residual cement in the particles above 1 mm separated by rotary mill with different amount
표 Distribution of (A) cement and (B) aggregate in the particles separated by rotary mill with different amount
표 (A) Distribution of aggregate and fine power and (B) residual cement in the particles above 1 mm separated by rotary mill with different milling time
표 Distribution of (A) cement and (B) aggregate in the particles separated by rotary mill with different milling time
표 (A) Distribution of aggregate and fine power and (B) residual cement in the particles above 1 mm separated by different treatment methods
표 Conceptual process diagram of case 1 for treatment of radioactive concrete waste with release of aggregate phase to environment
표 Conceptual process diagram of case 2 for treatment of radioactive concrete waste with release of aggregate phase and cement phase without radionuclide to environment
표 Conceptual process diagram of case 3 for treatment of radioactive concrete waste with release of aggregate phase and cement phase to environment without radionuclide
표 Conceptual process flow diagram of case 3 for treatment of radioactive concrete waste with release of aggregate phase and cement phase to environment without radionuclide
표 Experimental procedure for concrete dissolution
$Dissolved weight fraction(%) of cement, mortar, and concrete waste in (A) HCl, (B) HNO3$ 표 Dissolved weight fraction(%) of cement, mortar, and concrete waste in (A) HCl, (B) HNO3
표 Chemical composition of dissolved solution (A) HCl, (B) HNO3
표 Dissolution yield(%) of concrete waste powder with acid concentration
표 Colors of dissolved solution of concrete waste powder
표 Dissolution yield(%) of concrete waste powder as a function of dissolution time
표 Dissolution yield(%) of concrete waste powder as a function of temperature
표 Dissolution yield(%) of concrete waste as a function of acid volume
표 Dissolution yield(%) of concrete waste powder as a function of particle size
표 Dissolution yield(%) of concrete waste powder as a function of acid concentration
표 Experimental procedure for contaminated concrete dissolution
표 Dissolution yield(%) of contaminated concrete powder and residual radioactivity of Co in undissolved powder. (T=298 K, Dissolution time= 1 hr)
표 Dissolution yield(%) of contaminated concrete powder and residual radioactivity of Co and Eu in undissolved powder. (T=298 K, Dissolution time=1 hr)
표 Dissolution yield(%) of contaminated concrete powder and residual radioactivity of Co, Cs and Sr in undissolved powder. (T=298 K, Dissolution time=1hr)
표 Picture of concrete waste powder solution dissolved by (A) HNO3, and (B) HCl
표 Residual radioactivity(%) of Co, Cs and Sr with dissolution time in undissolved contaminated concrete powder. (T=298 K, 4 M HNO3)
표 Residual radioactivity(%) of undissolved contaminated concrete powder after 2nd dissolution. (T=298 K, 4 M HNO3, 4M HCl)
표 Residual radioactivity(%) of Co, Cs and Sr in undissolved contaminated concrete powder with dissolution time at 2nd dissolution. (T=298 K, 4 M HNO3)
표 Residual radioactivity(%) of Co, Cs and Sr in undissolved contaminated concrete powder with dissolution temperature at 2nd dissolution. (T=298K, 4 M HNO3. Dissolution time=1 hr)
표 Color of concrete waste powder solution after 2nd heating dissolution. (Dissolution time=1 hr, 4 M HCl)
표 Residual radioactivity(%) of Co, Cs and Sr in undissolved contaminated concrete powder with dissolution time after 2nd dissolution at high temperature. (T=333 K, 4 M HNO3)
표 Residual radioactivity(%) of Co, Cs and Sr after 1st dissolution and 2nd heating dissolution. (Dissolution time=1 hr, 4 M HNO3)
표 (A) SEM image and (B) EDS mapping of the particles above 1 mm separated by heating and grinding treatment
표 (A) SEM image and (B) EDS mapping of the particles above 1 mm after dissolution treatment
표 Residual cement(%) in the particles above 1 mm separated by different treatment methods
표 Atomic percent(%) of major elements in the particles above 1mm after each treatment step.
표 Concentration(ppm) of major elements in the solutions after each dissolution step
표 Radioactivity(Bq/g) of aggregate separated by each treatment step for the concrete waste with (A) high and (B) low contamination
표 Radioactivity(Bq/g) of fine powder before and after treatment for the concrete waste
표 Concentrations of elements in solution after dissolution of non-radioactive concrete waste in 2M HCl
표 Concentrations of elements in target concrete wastewater generated from the process of concrete volume reduction designed in this work
표 Distribution of hydrolysis products and solubility of Al(III) in water system
표 Distribution of hydrolysis products and solubility of Fe(III) in water system
표 Distribution of hydrolysis products and solubility of Si(IV) in water system
표 Distribution of hydrolysis products and solubility of Mg(II) in water system
표 Distribution of hydrolysis products and solubility of Co(II) in water system
표 Distribution of hydrolysis products and solubility of Eu(III) in water system
표 Distribution of hydrolysis products and solubility of Ca(II) in water system
표 Solubilities of all the element considered in this study in water system open to air
표 Concentration of each element in single element system after the solution pH-adjustment
표 Solubility of Ca(II) in water system with and without opening to air with a change of pH
표 Concentration of each element in supernatant of simulated multi-components system after the solution pH-adjustment
표 Concentration of each element in supernatant of real concrete wastewater after the solution pH-adjustment
표 Concentration behaviors of Eu, Co, and Ca in supernatant of real concrete wastewater after the solution pH-adjustment
표 Concept of co-precipitation mechanism with coagulation-flocculation
표 Schematic diagram of co-precipitation mechanism of Co and Eu in wastewater via hydrolysis product of Al and Fe in solution
표 Concentration of Eu in the systems of Eu only, Eu-Al, Eu-Fe and Eu-Al-Fe after the solution pH-adjustment
표 Concentration of Eu in the systems of Co only, Co-Al, Co-Fe and Co-Al-Fe after the solution pH-adjustment
표 Cs-137 radioactivity of supernatant solutions after different precipitation treatments
표 Sr-90 radioactivity of supernatant solutions after the treatments with different time
표 Sr-90 radioactivity of supernatant solutions after different precipitation treatments
표 Experimental scheme highlighting the points at which samples were analyzed for residual radionuclides
표 Aged dissolved concrete liquor which shows clear signs of silicon precipitation
표 Description of procedural test conditions for experiment using radionuclide
표 Summary of results obtained from the precipitation of dissolved concrete liquors spiked with selected radionuclides
표 Molecular structures of extractants
표 Extraction percentage of Co with initial pH of solution. (O/A ratio=1)
표 Extraction percentage of Co with initial pH of solution. (D2EHPA=0.1 M)
표 Extraction percentage of Co with initial pH of solution. (D2EHPA=0.5 M)
표 Extraction percentage of Co with equilibrium pH of solution. (D2EHPA=0.5 M)
표 Extraction percentage of Eu with initial pH of solution. (O/A ratio=1.0)
표 Extraction percentage of Eu with initial pH of solution. (D2EHPA=0.1 M)
표 Extraction percentage of Eu with initial pH of solution. (D2EHPA=0.5 M)
표 Extraction percentage of Eu with equilibrium pH of solution. (D2EHPA=0.5 M)
표 Extraction percentage of Ca with initial pH of solution. (O/A ratio=1.0)
표 Initial pH vs. equilibrium pH in solvent extraction of Ca
표 Extraction percentage of Co with initial pH of solution in 2-components system. (O/A ratio=1.0)
표 Extraction percentage of cobalt with initial pH of solution in 2-components system. (D2EHPA=0.1 M)
표 Extraction percentage of Eu with initial pH of solution in 2-components system. (O/A ratio=1.0)
표 Extraction percentage of Eu with initial pH of solution in 2-components system. (D2EHPA=0.1 M)
표 Extraction percentage of Co with initial pH of solution in 3-components system. (O/A ratio=1.0)
표 Extraction percentage of Eu with initial pH of solution in 3-components system. (O/A ratio=1.0)
표 Extraction percentage of Ca with initial pH of solution in 3-components system. (O/A ratio=1.0)
표 Effect of saponification degree in extraction of Ca
표 Effect of saponification degree in extraction of Co
표 Effect of saponification degree in extraction of Eu
표 Comparison of extractants in extraction of Co
표 Initial pH vs. equilibrium pH in extraction of Co
표 Comparison of extractants in extraction of Eu
표 Initial pH vs. equilibrium pH in extraction of Eu
표 Extraction percentage of Co with initial pH of solution with various extractants. (2-components system)
표 Extraction percentage of Eu with initial pH of solution with various extractants. (2-components system)
표 Effect of initial pH of solution on the separation factor between Co and Eu with various extractants
표 Photograph of 2 mL measured volume of IX resin
표 Photographs of IX process showing Co2+ loading onto and elution from S940
표 Co removal by selected IX resins as a function of pH
표 Eu removal by selected IX resins as a function of pH
표 Co removal by selected IX resins as a function of NaCl concentration. (pH screen results overlaid for comparison)
표 Eu removal by selected IX resins as a function of NaCl concentration. (pH screen results overlaid for comparison)
표 Process flow diagram for volume reduction treatment of radioactive concrete waste
표 Process flow diagram for volume reduction treatment of radioactive concrete fine powder contaminated by Cs.
표 Process flow diagram for volume reduction treatment of radioactive concrete fine powder contaminated by Sr
표 Process flow diagram for volume reduction treatment of radioactive concrete fine powder contaminated by Co and Eu
표 Process flow diagram for volume reduction treatment of radioactive concrete fine powder contaminated by multiple radionuclides
표 Spent activated carbon from nuclear power plant
표 Reaction mechanism between (a) TEDA or (b) KI impregnated activated carbon and methyl iodide
표 Radioactive isotopes and their form in spent activated carbon
표 Concentration of 14C and 3H in virgin activated carbon
표 Weight loss pattern of spent activated carbon under Ar atmosphere at elevated temperatures and establishment of thermal desorption reaction steps based on DTG
표 FTIR spectrum of evolved gases during the course of TGA of spent activated carbon shown in Fig. 2.2.2.가-1
표 Changes in 14C radioactivity of stepwise treated spent activated carbons(1st VD(vacuum desorption): 1,000℃ and 5 Pa, 2nd VD: 1,200℃ and 0.5 Pa, and SO(surface oxidation at 700℃ after filling with oxygen into evacuated pores and pressurizing with O2 at 5 bar))
표 SEM images of spent GAC(granular activated carbon) (a), TVD (thermal vacuum desorption) treated spent GACs, and SO(surface oxidation) treated spent GAC
표 XPS spectrum of spent GAC, TVD-treated spent GAC and SO-treated spent GAC samples
표 Carbon-bonding peaks (C1s) in the XPS spectra of five samples (a) and an example peak separation for C1s peak of the spent GAC sample (b)
표 Oxygen-bonding peaks in the XPS spectra of five samples (a) and an example peak separation for C1s peak of the spent GAC sample (b)
표 Elemental composition (%) of spent GACs, vacuum desorption treated GACs at 600°C, 800°C and 900°C, and 5% oxidation treated GACs
표 FTIR spetrum of spent GACs, vacuum-treated GACs at different temperatures and surface oxidation treated GACs
표 Schematic diagram of thermochemical process for the treatment of spent activated carbon
표 Layout of bench-scale thermochemical process (a) and Installed bench-scale thermochemical process with a spent activated carbon treatment capacity of 5 L/batch (b)
표 Weigh loss of spent activated carbon (a) and desorption rate (b) under ultra-high vacuum TGA (2×10-2 Pa)
표 Activation energy of desorption reaction step 1&2 and desorption reaction step 3 as a function of desorption progress under ultra-high vacuum condition (2×10-2 Pa)
표 Simulated reaction progress of 3rd step desorption (a) and an example result of optimum temperature profile of the reactor for the completion of desorption reaction step (b)
표 Results of non-isothermal TGA under 2% O2 atmosphere and an example simulation of optimized condition for the 2% peeling of VD treated spent GACs
표 Results of plug flow reactor (PFR) simulation for the oxidation of methane in a 30 cm(L) and 5 cm(ID) plug flow reactor–Methane emission concentration as a function of PFR residence time and temperature
표 Methane emission concentration as a function of PFR length and temperature
표 Methane emission concentration as a function of gas velocity and mass flow rate
표 Results of plug flow reactor (PFR) simulation for the oxidation of methane in a 30 cm(L) and 5 cm(ID) plug flow reactor – CH4 and CO2 emission concentration as a function of PFR residence time and temperature
표 Candidates for host minerals for capturing of 14CO2-containing CO2
표 Comparison of XRD patterns of limes before (a, c) and after (b, d) calcination
표 Thermogravimetric analysis of host minerals under CO2 atmosphere at elevated temperatures
표 Mass change of shell(a) and white pebble(b) under CO2 atmosphere at elevated temperatures
표 P&ID diagram of pilot-scale (20L/batch) thermochemical treatment process for the treatment of spent activated carbons
표 Design of the vacuum outgasing and sulface oxidation treatment furnace in a pilot-scale (20 L/batch) thermochemical treatment process
표 Design of secondary furnace having a function of both oxidation of hydrocarbons and capture of CO2
표 Composition of serpentine
표 Composition of wollastonite
표 Experimental scheme for CO2 adsorption
표 Experimental scheme of thermochemical process of spent activated carbon treatment
표 XRD patterns of minerals before and after adsorption of carbon dioxide for 1 hours under room temperature and atmospheric pressure; (a) serpentinite, (b) wollastonite
표 TGA curves of minerals before and after adsorption of carbon dioxide for 1 hour under room temperature and atmospheric pressure conditions ; (a) serpentinite, (b) wollastonite
표 Composition of Sr-glass-Na2O
표 Composition of Sr-glass-K2O
표 Composition of Ca-glass-Na2O
표 Composition of Ca-glass-K2O
표 (a) XRD patterns and (b) TGA curves of Sr-glass-Na2O before and after adsorption of carbon dioxide for 1 hour
표 TGA-MS curve for Sr-glass-Na2O after carbon dioxide adsorption
표 Hypothesized CO2 adsorption mechanism for alkaline earth metal incorporated glass adsorbent
표 SEM images during TEM sample preparation using FIB. (a) Sr-glass powder-Na2O on the silicon board, (b) Pt coating with ion beam irradiation, (c) areas damaged by ion beam & sputtered by Pt, (d) Milled sample, (e) sample on grid
표 TEM image of Sr-glass-Na2O powder surface after immersing in DI-water for 1 hour
표 XRD peak analysis for (a) Sr-glass-Na2O after CO2 adsorption for 1 hour, and (b) SrCO3 powder from Aldrich
표 SEM images of Sr-glass-Na2O (a) before and (b) after adsorption of carbon dioxide for 1 hour at room temperature
표 Mechanism of CO2 capture using Sr-glass-Na2O in each stage
표 TGA curves for sieved powder (1st, 2nd, 3rd cycle) of Sr-glass-Na2O bulk after carbon dioxide adsorption for 1 hour at room temperature
표 XRD patterns for bare Sr-glass-Na2O, CO2 captured Sr-glass-Na2O, and sieved powder
표 CO2 capacity of (a) Sr-glass-Na2O, (b) Sr-glass-K2O, (c) Ca-glass-Na2O and (d) Ca-glass-K2O under room temperature conditions and atmospheric pressure with respect to time
표 Theoretical and experimental CO2 capacity for each adsorbent and efficiency of alkaline earth metal
표 Sr2+ concentration in CO2 adsorption media, DI-water, in terms of time when capturing CO2 using (a) Sr-glass-Na2O and (b) Sr-glass-K2O
표 XRD patterns of (a) heat-treated Sr-glass-Na2O, and (b) heat-treated Ca-glass-Na2O before and after adsorption of carbon dioxide for 1 hour at room temperature
표 TGA curves of (a) heat-treated Sr-glass-Na2O, and (b) heat-treated Ca-glass-Na2O before and after adsorption of carbon dioxide for 1 hour at room temperature
표 Scheme for beta ray radiation on alkaline earth metal incorporated glass adsorbent
표 (a) XRD pattern before and after adsorbing CO2 using Sr-glass-Na2O after beta ray radiation, (b) CO2 capacity of Sr-glass-Na2O after beta ray radiation
표 Schematic diagram of equipment for the accelerated CO2 mineralization
표 Schematic diagram and photo of equipment for the CO2 mineralization used in this study
표 Experimental conditions for the CO2 mineralization
표 Changes in pressures of the high pressure CO2 supplier(burette) and temperatures of the mixture with Ca(OH)2 and purified water
표 XRD results of the product from the preliminary CO2 mineralization (Experimental conditions: Solid/Liquid 0.2, CO2 pressure 50 bar, Stirring rate 500~550 rpm)
표 SEM images of the product from the preliminary CO2 mineralization (experimental conditions: solid/liquid ratio 0.2, CO2 pressure 50 bar, stirring rate 500~550 rpm)
표 Composition of the product from the preliminary CO2 mineralization (experimental conditions: solid/liquid ratio 0.2, CO2 pressure 50 bar, stirring rate 500~550 rpm)
표 Temperature increases of the mixture with Ca(OH)2 and purified water according to CO2 pressures in the mineralization reactor
표 XRD patterns of products from a mineralization reaction at zero stirring rate (CO2 pressure: 50 bar, S/L ratio: 0.05)
표 A photo of products from a mineralization reaction at zero stirring rate (CO2 pressure: 50 bar, S/L ratio: 0.05)
표 Temperature increases of the mixture with Ca(OH)2 and purified water according to stirring rates
표 Temperature increases of the mixture with Ca(OH)2 and purified water according to mass ratios of Ca(OH)2 over purified water
표 Photos of the products obtained from the mineralization tests with mass ratios (0.2~0.4) of Ca(OH)2 over purified water
표 XRD results of the products obtained from a mineralization test using wollastonite
표 Thermodynamic equilibrium calculations of CaCO3 decomposition using HSC-Chemistry 9.1
표 Thermo-gravimetric analysis of CaCO3 with heating rates
표 Composition of low melting glass used in this study
표 A photo of water-quenched melt (Bi2O3-B2O3-ZnO-SiO2) after melting at 900℃ for 1h
표 Powder (200 mesh) of the water-quenched melt (Bi2O3-B2O3-ZnO-SiO2)
표 XRD patterns of the powder of the water-quenched melt (Bi2O3-B2O3-ZnO-SiO2)
표 Melting test results of the glass powder
표 A photo of solidification product of CaCO3 using the low melting glass (waste loading: 40 wt%, 500℃)
표 XRD-patterns of solidification product of CaCO3 using the low melting glass.(waste loading: 40 wt%, 500℃)
표 SEM-mapping of solidification product of CaCO3 using the low melting glass.(waste loading: 40 wt%, 500℃)
표 Mass loss after the solidification of CaCO3 using the low melting glass with waste loadings.(450℃)
표 CO2 remains after the solidification of CaCO3 using the low melting glass with sintering temperatures.(waste loading: 35 wt%)
표 Composition of sludge wastes generated from NPPs in Korea (unit=%)
표 The underground tanks at the A1 NPP in Slovakia
표 Composition of sludge wastes generated from research reactor in Korea (unit=%)
표 Composition of sludge wastes generated from NPPs sump in Korea (unit=%)
표 Sump sludge generated from SRNL
표 Concrete structure dismantling technologies with (A) wet and (B) dry cutting
표 Typical characteristics of waste immobilization technologies
표 Phases transition of cement hydration as a function of time
표 Sintering stages from a loose powder and being sintered in each of the three stages
표 Schematic illustrations of (A) ceramic wasteform with waste phases in solution, and (B) ceramic with encapsulated waste phases
표 Potential host minerals for nuclear waste ceramizataion (Ln: lanthanides, An: actinides)
표 Radionuclide activity concentration limits for low-level waste disposal
표 Radionuclide activity concentration limits for clearance level
표 Test standard for waste acceptance criteria of immobilized radioactive waste
표 SENSEI process developed for treatment of spent uranium catalysts
표 Composition of major components included in uranium-bearing waste generated from the treatment process of spent uranium catalyst
표 Adsorption yield of Cs with different m/V ratio of hybrid-II in (A) SLW based DI water, and (B) SLW based seawater
표 (A) TEM images and (B) EDS mapping result of hybrid
표 (A) TEM images and (B) EDS mapping result of hybrid-II
표 Weight of CHA(K)-Cs, PCFC-Cs and CHA-PCFC-Cs adsorbent measured by TGA with temperature
표 TGA and DSC results of (A) hybrid, (B) hybrid-II
표 Geopolymer production process flowchart
표 Conceptual model for geopolymerization
표 Monomeric units from geopolymer gel as suggested by Davidovits
표 Monomeric units from geopolymer gel suggested by Davidovits
표 Chemical composition (wt%) of the metakaolin
표 XRD patterns of metakaolin
표 Solid state magic angle spinning 27Al-NMR spectrum of kaolinte and metakaolin
표 XRD patterns of silica fume
표 Experimental scheme
표 Comparison of diffusivity leaching test methods
표 Monoliths submerged into DIW in the leaching vessel
표 Fresh paste in sample plastic moulds
표 Geopolymer samples after demoulding
표 XRD patterns of geopolymer
표 Compressive strengths of geopolymer
표 Leachability index of geopolymer without waste
표 Thermal decomposition of sodium borate decahydrate
표 Sodium borate compounds
표 Solubility of sodium borates in water and 1 M NaOH solution
표 Solubility value of sodium borates in water and 1 M NaOH solution
표 Additional amount of water required depending on waste (SBA) loading
표 XRD pattern of SBA- containing geopolymers
표 Compressive strengths and waste loading of geopolymer under different experimental conditions (SiO2/Al2O3=4, Na2O/SiO2=0.22 and H2O/Na2O=12.3)
표 Compressive strengths and waste loading of geopolymer under different conditions (SiO2/Al2O3=4, Na2O/SiO2=0.25 and H2O/Na2O=11.5)
표 Compressive strengths of geopolymer according to curing time
표 Leachability index of geopolymer containing borax wastes
표 Difference illustration of immobilization between using cement grout and molten glass and using sintering methods
표 Formation mechanism of glass structure in case of adding network modifier of Na2O in glass network former of SiO2
표 XRD pattern of initial uranium-bearing waste generated from the spent uranium catalyst treatment process
표 Schematic fabrication of green body by compaction
표 Compression test by production pressures and volume reduction from after sintering
표 Photos of (A) greed bodies and (B) their sintered bodies at 1,100℃ with a change of compaction pressure
표 Photos of (A) greed bodies of SiO2-Na2O system and (B) their sintered bodies at 1,100℃ with a change of weight ratio of SiO2 to Na2O
표 XRD patterns of SiO2-Na2O system sintered at 1,100℃ with a change of weight ratio of SiO2 to Na2O
표 Physical properties of uranium bearing waste-Na2O system sintered at 1,100℃ at 7:1 and 7:2 of ratio of Na2O to SiO2 in the system
표 SEM images of sintered bodies at 1,100℃ in the system of uranium-bearing waste and Na2O at 7:1 and 7:2 of ratio of Na2O to SiO2
표 Physical properties of SiO2-B2O3 system sintered at 1,100℃ with a change of ratio of B2O3 to SiO2
표 Photos of (A) green bodies of SiO2-B2O3 system and (B) their sintered bodies at 1,100℃ with a change of weight ratio of B2O3 to SiO2
표 XRD patterns of sintered bodies at 1,100℃ in the system of SiO2– B2O3 with a change of ratio of Na2O to SiO2
표 SEM images of sintered bodies at 1,100℃ in the system of SiO2 – B2O3 with a change of ratio of B2O3 to SiO2
표 Physical properties of uranium bearing waste-B2O3 system sintered at 1,100℃ with a change of ratio of B2O3 to SiO2
표 Photos of uranium bearing waste-B2O3 system sintered at 1,100℃ with a change of ratio of B2O3 to SiO2
표 SEM images of sintered bodies at 1,100℃ in the system of uranium bearing waste–B2O3 system with a change of ratio of B2O3 to SiO2
표 XRD pattern of sintered bodies at 1,100℃ in the system of uranium bearing waste-B2O3 with a change of ratio of B2O3 to SiO2
표 PCT leaching rate of uranium bearing waste-B2O3 system sintered at 1,100℃ with a change of ratio of B2O3 to SiO2
표 Photos of sintered uranium bearing waste-B2O3 system with a ratio of B2O3 to SiO2 of 7:2 with a change of sintering temperature
표 XRD pattern of sintered uranium bearing waste-B2O3 system with a ratio of B2O3 to SiO2 of 7:2 with a change of sintering temperature
표 Physical properties of uranium bearing waste-B2O3 system sintered at a ratio of SiO2 to B2O3 of 7:2 with a change of sintering temperature
표 PCT leaching rate of uranium bearing waste-B2O3 system sintered at a ratio of SiO2 to B2O3 of 7:2 with a change of sintering temperature
표 TGA curves of single Sb2O3 and Sb2O5
표 XRD pattern of sintered bodies prepared at 1,100 ℃ with and without addition of B2O3 with a ratio of B2O3 to SiO2 of 7:2 in the target uranium waste
표 SEM image and EDS map of element distribution (a) in the green body to be sintered, (b) in the sintered body at 1,100℃ with addition of B2O3 with a ratio of B2O3 to SiO2 of 7:2 in the target uranium waste
표 TG and DSC curves of target uranium-bearing waste according to added B2O3 wt% in the target uranium waste
표 DSC curves and its secondary derivative curves of in the cases without and with addition of 1.9 wt% B2O3 in the uranium-bearing waste
표 TG and DSC curves of 50 wt% Sb2O3-50 wt% Fe2O3 system
표 XRD pattern of material obtained after DSC measurement of Sb2O3-Fe2O3 system in Fig. 2.3.5.나-22
표 TG, DSC and second derivative of the DSC of 45 wt% SiO2 + 45wt% Sb2O3 + 10 wt% B2O3 system
표 TG and DSC curves of U3O8
표 Typical composition of Portland cement constituents
표 Typical composition of Portland cement constituents by weight
표 Photos of cement cured for 28 days
표 Photo of leaching experiment of cement by ANS 16.1 method
표 Evaluation of cement immobilization characteristics with a change of ratio of cement to target waste
표 Change of leachability index of cement waste form bearing spent uranium catalyst with leaching time at a ratio of cement to target waste of 2
표 Leaching characteristics of U and Sb in cement waste form with a change of ratio of cement to target waste, and their comparisons with those in glass-ceramics waste form
표 XRD spectra of (A) salt-free CHA-PCFC-Cs, and (B) high-salt CHA-PCFC-Cs with temperature
표 XRD spectra of CHA-PCFC with different PCFC impregnation ratio at 1,000℃
표 XRD spectra of CHA-PCFC-Cs with Cs adsorption amount at 1,100℃
표 Cs volatility and leaching of calcined CHA-PCFC with temperature. CHA-PCFC was synthesized according to (A) hybrid, (B) hybrid-II and reacted with a salt-free solution (DI water) or high-salt solution (seawater)
표 Cs volatility and leaching of calcined CHA-PCFC with isothermal time at 800℃. CHA-PCFC was synthesized according to (A) hybrid, (B) hybrid-II and reacted with a salt-free solution (DI water) or high-salt solution (seawater)
표 Cs volatility and leaching of calcined CHA-PCFC with isothermal time at 850℃. CHA-PCFC was synthesized according to (A) hybrid, (B) hybrid-II and reacted with a salt-free solution (DI water) or high-salt solution (seawater)
표 XRD spectra of (A) salt-free CHA-PCFC-Cs, and (B) high-salt CHA-PCFC-Cs with isothermal time at 850℃
표 SEM images of high-salt CHA-PCFC-Cs with isothermal time at 850℃
표 Cs volatility and leaching of calcined CHA-PCFC with calcination time to encapsulate at 900℃. CHA-PCFC was synthesized according to (A) hybrid, (B) hybrid-II and reacted with a salt-free solution (DI water) or high-salt solution (seawater)
표 Cs volatility and leaching of calcined CHA-PCFC with calcination time to encapsulate at 950℃. CHA-PCFC was synthesized according to (A) hybrid, (B) hybrid-II and reacted with a salt-free solution (DI water) or high-salt solution (seawater)

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