A5101716804- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Radioactive element chemistry and processing
- Nuclear materials and radiation effects
- Fusion materials and technologies
- High Temperature Alloys and Creep
- Nuclear and radioactivity studies
- Advanced ceramic materials synthesis
- Advanced materials and composites
- Nuclear Engineering Thermal-Hydraulics
- Ferroelectric and Piezoelectric Materials
- Multiferroics and related materials
- Magnetic and transport properties of perovskites and related materials
- Engineering Applied Research
- Heat transfer and supercritical fluids
- Metallurgical Processes and Thermodynamics
- Educational Robotics and Engineering
- Advanced Condensed Matter Physics
- Transportation Planning and Optimization
- High-Temperature Coating Behaviors
- Advanced Cellulose Research Studies
- Induction Heating and Inverter Technology
- Iron and Steelmaking Processes
- Microwave-Assisted Synthesis and Applications
- Solid-state spectroscopy and crystallography
Korea Atomic Energy Research Institute
2015-2024
Catholic University of America
2000
Korea Advanced Institute of Science and Technology
1993-1999
Chungbuk National University
1988
Abstract A microcell UO2 pellet, as an accident-tolerant fuel pellet, is being developed to enhance the accident tolerance of nuclear fuels under conditions well performance normal operation conditions. Improved capture-ability for highly radioactive and corrosive fission product (Cs I) is distinct feature a ceramic enhanced pellet thermal conductivity that metallic pellet. The temperature can be effectively decreased by conductivity. In this study, material concepts pellets were designed,...
The high-temperature phase of Pb(Mg 1/2 W )O 3 , Pb(Co and Pb(Yb Nb belongs to the space group Fm m with unit cell size 2 a c ×2 where is lattice parameter cubic perovskite cell. All these complex perovskites undergo transition into low-temperature orthorhombic structures shrunken along -axis approximate √2 parameters 0 - b -axes, which are, respectively, parallel prototype [110] [11̄0] directions. symmetry most prominently distinguished from that in structure modulated direction. For...
Techniques to fabricate thorium-uranium dioxide fuel [(Th,U)O2] have been developed, and the thermal conductivity of (Th,U)O2 pellets has measured. Mixtures thorium (ThO2) uranium (UO2) powders were successfully wet-milled, compacted, sintered at 1700°C pellets. The wet-milling process results in a density 96 98% theoretical uniform distribution pellet. laser flash method was used measure diffusivity ThO2 pellets, conductivities (Th0.655U0.345)O2 (Th0.355U0.645)O2 found be lower than that or...
Heat generation of uranium dioxide (UO 2 ) powder and its pressureless rapid sintering behaviors have been studied using a high‐frequency induction heating apparatus. The porous graphite housing has used to prevent heat loss preheat the oxides, simultaneously. At an elevated temperature, UO generated extra by itself. synergism individual between could effectively temperature 1700°C. Using this process, densification behavior cylindrical disk‐type green pellets according rate grain structure...
The effect of the oxidation temperature UO2 pellets on powder properties oxidized U3O8 powders has been investigated. morphology, crystalline size, and BET surface area recycled could be modified by controlling pellets. Recycled with a high small particle size obtained lowering temperature. It was also found that this low-temperature-oxidized sinter-active is effective in mitigating density drop when added. Moreover, acted as grain-size-enlarging promoter
Abstract The fabrication and high-temperature deformation strain of MnO-Al2O3-doped UO2 pelletswere studied. effects additive composition amount on the microstructure evolution a pellet were investigated. compressive creep behaviors pellets examined. results indicated that MnO-Al2O3 binary can effectively promote grain growth pellets. In addition, be improved significantly with 1,000 ppm 95MnO-5Al2O3 (mol%). developed MnO-Al2O3-additive-containing potential candidate for high-burn-up fuel...
The challenges associated with conventional boron carbide (B4C) control rod materials, including helium gas accumulation and susceptibility to oxidation corrosion in various environments, have been thoroughly explored. To address these issues, a comprehensive investigation into the potential of oxide-based neutron absorber compounds for rods has undertaken. Thermodynamic equilibrium state calculations conducted assess reactions materials (Gd, Hf, Sm, Er, Eu, Dy-based oxide), B4C,...
Powder morphology evolution of recycled U3O8 according to the thermal treatments has been studied. The defective UO2 pellets are oxidized powders at a conventional temperature 350 or 450°C in air. Those pressed into green and then sintered 1,500 1,730°C H2 gas flow. Final reoxidized powers obtained by reoxidizing those This paper shows that powder BET surface areas greatly dependent on density before reoxidation. Reoxidized added virgin fabricate effect such addition pellet properties is...
The room-temperature structure of the B-site-ordered complex perovskite dicalcium magnesium tungstate, Ca(2)MgWO(6), has been determined by simultaneous Rietveld refinement neutron and X-ray powder diffraction patterns. Ca(2)MgWO(6) is characterized B-site ordering an a(-)a(-)c(+)-type BO(6) octahedral tilt mechanism.