A5078344083- Nuclear Materials and Properties
- Hydrogen embrittlement and corrosion behaviors in metals
- Fatigue and fracture mechanics
- Nuclear reactor physics and engineering
- Fusion materials and technologies
- High Temperature Alloys and Creep
- Material Properties and Failure Mechanisms
- Non-Destructive Testing Techniques
- Nuclear and radioactivity studies
- Welding Techniques and Residual Stresses
- Nuclear Engineering Thermal-Hydraulics
- Intermetallics and Advanced Alloy Properties
- Engineering Structural Analysis Methods
- Metal Alloys Wear and Properties
- High-Temperature Coating Behaviors
- Corrosion Behavior and Inhibition
- Engineering Applied Research
- High-Velocity Impact and Material Behavior
- Material Properties and Applications
- Mechanical Failure Analysis and Simulation
- Metal and Thin Film Mechanics
- Advanced Welding Techniques Analysis
- Microstructure and Mechanical Properties of Steels
Korea Atomic Energy Research Institute
2016-2023
Korea Advanced Institute of Science and Technology
2010-2015
After the Fukushima accident, there has been motivation to develop accident tolerant fuel (ATF) cladding encouraged meet increased need for safety under conditions. Many countries have focused on surface-modified Zr such as Cr or Cr-Al alloy coated Zr-alloy a near-term application. In case of cladding, is no currently mechanical properties data measured by traditional tensile test describe characteristics layer directly due its thin thickness. this regard, we introduce small scale...
Low-cycle fatigue (LCF) tests were performed for Alloy 690 and 316 SS in a simulated pressurized water reactor (PWR) environment. showed about twice longer LCF life than at the test condition of 0.4% amplitude strain rate 0.004%/s. Observation oxide layers formed on crack surface that Cr Ni rich was 690, while Fe as an inner layer. Electrochemical analysis revealed had higher impedance less defect density those SS, which resulted PWR
In addition to oxidation resistance, an improvement of corrosion resistance is another important issue in the accident tolerant fuel development emerged after Fukushima accident. Crud deposited on assembly induces undesired problems such as power shift, accelerated corroion claddings which can ultimately results failure. this study, uncoated Zircaloy-4 cladding and a CrAl-coated are tested simulated PWR water. crud adhesion significantly reduced, along with reduction thickness. Morphology...
In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (KIH) was performed. However, there were few limitations in analysis cladding properties, such as oxide thickness and mechanical properties. this those models modified to include test data for irradiated materials, creep model introduced improve reliability DHC assessment. susceptibility PWR depending on axial elevation...
In operating PWRs (Pressurized Water Reactors), incidents of Alloy 82/182 cracking increased the concern for structural integrity butt weld locations recently, because high residual stresses. Studies on PWSCC (Primary Stress Corrosion Cracking) have been mainly performed using deterministic approaches by controlling parameters, but a quantitative evaluation is difficult large uncertainties in each parameter and test results. The purposes this paper are to provide probabilistic fracture...
As an accident tolerant fuel (ATF) concept, oxide dispersion strengthened Zircaloy-4 (ODS Zry-4) cladding has been developed to enhance the mechanical properties of using laser processing technology. In this study, a simulation technique was established investigate and effects Y2O3 particles for ODS Zry-4. A 3D representative volume element (RVE) model considering parameters size, shape, distribution fraction (VF) particles. From RVE model, Young's modulus, coefficient thermal expansion...
One of the limiting mechanisms pressurized water reactor spent fuel cladding is creep owing to high temperature and rod internal pressure. Based on extensive studies, many countries have tentatively concluded that rupture hard occur under dry storage conditions cannot severely degrade integrity if it meets 400°C limitation a self-limiting property. However, changes in mechanical properties after deformation are not well understood due limited amount relevant tests analyses. In this regard,...
Alloy 82/182 weld metals had been extensively used in joining the components of PWR primary system. Unfortunately, there have a number incidents cracking caused by PWSCC welds during operation worldwide. To mitigate PWSCC, optimization water-chemistry conditions, especially dissolved hydrogen (DH) and Zn contents, is considered as most promising effective remedial method. In this study, behaviours 182 were investigated simulated environments with various DH content. Both in-situ ex-situ...