Nuclear Science and Engineering (NSE)
This course deals with physical basics and engineered application of the nuclear energy and the main objective is to provide the student with general understanding and knowledge of the nuclear engineering. The fundamentals of nuclear physics and interaction of radiation with matters are studied. The basic principles of nuclear reactor are investigated and various nuclear reactor concepts are discussed. The nuclear energy conversion and radiation protection are studied as well.
This course introduces the nuclear fuel cycle which is the progression of nuclear fuel through a series of differing stages. It consists of steps in the front end, which are the preparation of the fuel, steps in the service period in which the fuel is used during reactor operation, and steps in the back end, which are necessary to safely manage, contain, and either reprocess or dispose of spent nuclear fuel. Depending on the reprocessing of the spent fuel, the specific topics include an open fuel cycle (or a once-through fuel cycle) and a closed fuel cycle considered in terms of sustainability of nuclear energy and nonproliferation. In particular, nuclear waste disposal (spent fuel) techniques will be discussed in terms of economics, safety and public acceptance.
The basic concepts and definition about radiation dosimetry are introduced and the biological effects on cells and human body organs are discussed. It also covers the generation, amplification, transfer and measurement of the electronic signal from various radiation detector based on the physics theory of the electronics signal and noise. The course also explores methods of radiation counting, timing and imaging system.
This subject introduces basic concepts and applications of materials science and engineering to nuclear energy systems, while laboratory practices are designed for experiencing property tests of the lectured materials. Lectures include the essential knowledge of materials science and engineering as well as the effects of radiation and environments on material properties. The experiments are concerned with mechanical test and data analysis, phase transformation, observation by optical and electron microscopes, corrosion tests and irradiation effects.
This course covers fundamental theory of nuclear fission reactors. Specific topics includes the followings: nuclear fission phenomenon, the chain nuclear reaction, diffusion/ moderation/absorption of neutron, multi-group neutron diffusion equations, heterogeneous reactor, reactor dynamics, reactivity and its change, perturbation theory and adjoint solutions, etc.
In this course, students will have a chance to get the practical experience in nuclear fuels and fuel cycle, and nuclear fuel cladding and structural materials. In the nuclear fuels and fuel cycle area, students will first learn the fuel, fuel design criteria, fuel performance analysis code and then have a chance to analyze the in-reactor performance of the fuel. Then they will learn how to manufacture the fuel and have a chance to actually fabricate the fuel pellet with simulated material. Then they will be asked to analyze the results. In nuclear fuel cladding and structural materials area, students will learn the basic principles for the design and analysis of fuel cladding and structural components with commercial structural analysis code. And, material properties of fuel cladding and structural components will be reviewed and the proper material design and analysis using computational thermodynamics software will be practiced.
This course focuses on the electromagnetic theories as a basis for plasma engineering, nuclear fusion, radiation and nuclear engineering. The basic concepts on electricity and magnetism are included. Specific topics will include vector algebra and calculus; electrostatics in material media for Coulomb’s Law, Gauss’s Law, and boundary-value problems; steady electric currents for Ohm’s law and Kirchhoff’s law; magnetostatics in magnetic media for Ampere’s Law, Biot-Savart law, and vector potential; time-varying electromagnetics for Faraday’s Law and Maxwell’s equation.
Design of various nuclear fission energy systems and fast reactor technology require a variety of knowledge such as reactor physics, neutron data, radiation measurement and liquid metal magnetohydrodynamics. Through this course, students will learn how to design and develop nuclear systems based on the above-mentioned knowledge. Students will participate in comprehensive design and lab activities such as 1) set up a design goal, 2) identify design parameters of the system and sketch the performance of the proposed system, 4) establish quantitative models and/or setup experimental devices that show the performance of the system, 5) identify multiple constraints in the project, and develop an optimized solution.
In this course, a variety of design constraints such as design principles, requirements, functions and technical specifications that govern the overall phases of design processes will be introduced to point out drawbacks and enhancement directions of nuclear systems. In addition, through implementations of small-scale mockups, an engineering chance realizing new ideas that are created by students would be provided.
The partial differential equations to be solved for real world nuclear engineering applications such as the nuclear reactor core design, core transient analysis, and core depletion calculations, cannot be solved analytically in most cases. Instead, computer can be utilized to obtain approximate solutions of the PDEs. This course covers techniques which can solve numerically the PDEs found in nuclear engineering, e.g., finite difference, finite element, and advanced nodal methods.
Advanced design of next-generation nuclear fission and fusion systems requires interdisciplinary knowledges between thermal-hydraulics and materials in terms of safety and economics. Through this course, students learn about how to design and develop nuclear systems based on the above-mentioned major knowledges. Students participate in a comprehensive design and lab activity based on given proposals: Read a proposal for the project; Set up a design goal; Identify design parameters of the system and sketch the performance of the proposed system; Establish quantitative models that show the performance of the system by taking charge of their own learning, and analyze the system performance quantitatively; Identify multiple design constraints in the project, and develop an optimized solution or solutions. The system design project is based on Axiomatic Design principles.
Experiments are performed for production of radioisotopes, neutron activation analysis, neutron radiography, and fuel burnup measurement utilizing Research Reactor. The reactor system is described with reference to the Kori Units 3 & 4, Westinghouse three- loop pressurized water reactors. Their Final Safety Analysis Report (FSAR) is reviewed to examine the thermal and hydraulic system behavior spanning from an abnormal condi- tion to a loss-of-coolant accident condition. The Compact Nuclear Simulator (CNS) is utilized to study the reactor dynamics involving startup and shutdown practice, to examine the thermal hydraulic behavior of the system after a component malfunction or an operator error, and to compare the results against the licensing calculation reported in the FSAR.
This course focuses on the concept for nuclear fusion. It introduces basic principles and technological issues relevant to plasma and fusion energy generations and their practical uses as a limitless large-scale electric power source in the future. Through this class, students learn plasma, principle of nuclear fusion, the kinds of nuclear fusion, plasma confinement, nuclear fusion device and current status of the nuclear fusion technology.
This course covers the basic principles and structures of various nuclear fuels and their actual applications and future fuel developments. The structure, characteristics and materials of different types of fuel wil be introduced and their general irradiation behavior will be discussed. Fuel modelling, testing, design and fabrication will be covered. General in-reactor performance and failure experiences of current generation fuels and future fuel development activities will be introduced.
This course covers basic computer and IT technology necessary for nuclear reactor physics analysis, thermal hydraulics system design, nuclear fuel performance analysis, nuclear material, radiation protection analysis, nuclear reactor safety analysis: Operating System (Windows, Linux), Computing Tools (Matlab, Mathematica, Labview), Programming Language (FORTRAN, C, JAVA), Script Language (Perl, Python, Batch File), Parallel Programming (OpenMP, MPI)