The primary research subjects of Nuclear Instrumentation and Control Laboratory are the development and evaluation of nuclear I&C systems. Our research activities are related to the systems which receive thousands of plant field signals and process them to control the plants in normal and abnormal conditions. Since the whole systems include massive signals and electronic devices, and human operators, this research field involves not only nuclear engineering but also electrical engineering, computer science, industrial engineering, and cognitive science. Our research has a great potential to impact other research areas because we deal with such extreme conditions where ultra-high safety and reliability are requiredand massive information should be processed simultaneously. The representative research activities of our laboratory are the reliability estimation and development methodologies of digital systems including human performance, efficient evaluation of man-machine interface systems, and studies of cognitive engineering.
Compact Nuclear Simulator (CNS)
The reference plant of this simulator is Kori 3 Nuclear Power Unit in Korea which is a Westinghouse 3 Loop PWR plant. The Simulator capabilities includenormal plant operation evolution, malfunctions and abnormal plant conditions over the whole operating range.
Eye Tracking System (ETS)
Eye Tracking System detects frequency and duration of eye blinks and fractional closure of eyes during blinks, where he/she is staring at and how long. Eye movement data are used as the complementary measures for the evaluation of workload.
This system can be used not only for brain wave measurements but also for heart rate and contraction-relaxation of muscles measurements. Using the brain wave, it is possible to measure human operator’s stress and awakening.
Thermal Imaging Camera
Thermal Imaging Camera is used for facial skin temperature measurement to calculate operators’ stress or workload
Audio/Video system is used for recording human operators’ actions and communications. This system is especially useful for estimating team situation awareness (TSA).
Nuclear Environment and Waste Management group is a branch of nuclear engineering groups concerned with the application of interaction between the Nuclear Engineering and the Environment Technology. Research area of nuclear environment and waste management group includes environmental radiation monitoring, environmental impact assessment aroundnuclear facility, nuclear fuel cycle policy, spent nuclear fuel management, radioactive waste treatment/disposal technology, performance assessment of waste disposal site and etc. These researches are important in the view of protecting the public health against the potential hazards of radiation and maintaining a clean environment. In recent years, concerns for environmental preservation have increased the demand for Environmentally Safe and Sustainable Energy Development. Therefore, it is necessary to develop and apply the appropriate environmental assessment methodology covering the whole nuclear power generation system from the view point of the improvement of environmental friendliness.
Gamma-ray Spectroscopy System
- HPGe based Gamma-ray spectroscopy system for the purpose of analysis of radioactivity samples
- 40% efficiency HPGe Coaxial Detector (Pop Top) P type
- Lead shield with auto sampler
- Electrical cooling system and LN2 cooling system
- Digital spectrometer
- Data processing system
- Software regarding calibration, analysis and etc
Low Background Alpha and Beta Counter
- The system to measure low background Gross alpha/beta radio-activities of environmental samples
- With thin window gas flow detector, 50 sample capacity, 50 sample carriers and planchet inserts
- Data processing system
- Counting system control software and report editor
Liquid Scintillation Counting System
- The system to analyze low level RI like Tritium or C-14
- LSC counter
- Temperature control kit
- Alpha/Beta discrimination
Our major research interests center on mechanical and electrochemical behaviors of structural materials in nuclear power plant (NPP) environments, many of which are related to the NPP’s safety. One of the factors threatening the structural integrity of materials in NPPs is ‘stress corrosion cracking (SCC)’ phenomena which are typically caused by a combination of a corrosive environment and mechanical stresses. Our research is aiming at identifying main factors causing the SCC on austenitic stainless steels and Ni base alloys in pressurized water reactor (PWR) environments and verifying its mechanisms. Currently, the test equipment for experiments is under construction. Once the equipment construction is completed, the following experiments and associated research can be carried out for stainless steels and Ni base alloys;
- Stress corrosion cracking tests in the primary water environment;
- Electrochemical measurements in neutral, acidic, and caustic solutions at temperatures below than 90°C;
- Materials surface examination using an optical microscope.
PWSCC Test system
Autoclave & Loading system
- Loading frequency : Constant loading ~ Cyclic loading(up to 2 Hz)
- Loading wave form : Sine, triangle, trapezoid, constant
- Load range : 0 ~ 60 kN
- DCPD(Direct Current Potential Drop) system : reversed current 4A every 0.5 ~ 10s
- Water temperature & pressure : Max. 340oC, 170 atm
- Dissolved hydrogen: 0 ~ 100 cc/kg
- Dissolved oxygen: below 5 ppb
- Water conductivity: 20 ~ 25 ㎲/cm
- Sample preparation : Low speed cutter, High speed cutter, Auto-polisher
- Surface Examination : Optical Microscope with image analyzer
- Electrochemical Application : Potentiostat, Corrosion cell kit, Portable pH meter
- Box furnace, Precision balance, Stirrer, Ultrasonic cleaner
The Nuclear Safeguards and Security Group supports stakeholders in the areas of: development and characterization of measurement systems for nuclear material detection and quantification; assessment of safeguards and security measures for fresh and spent nuclear fuel; Monte Carlo modeling of radiation detection and measurement systems.
The Reactor Design and Analysis Group is focused on system development and performance analysis of various nuclear systems including the next generation nuclear reactor systems and small modular reactor (SMR) systems. Furthermore, a nuclear reactor core and a system component design technologies and safety evaluation of the designed or existing systems are the major focus of this research group. Since most of the design and safety analysis of the nuclear systems are now computerized, the research group is specialized in many computational simulations including: Computational Fluid Dynamics, Reactor Physics and Reactor Transient Analysis. Currently, the supercritical carbon dioxide power cycle is being investigated to enhance performance of both next generation reactor and SMR systems. The research group is also interested in simulating thermal striping phenomena, deteriorated turbulent heat transfer in a nuclear system, rod bundle flow field calculation and designing an advanced nuclear reactor core as well.
IBM High Performance ComputerIIHIg with Features