Curriculum
| Course Number | Summary | English |
|---|---|---|
| NE7001 | Nuclear Policy | |
| Nuclear engineering is closely related to the international policies regarding the peaceful use of atomic energy. Accordingly, nuclear engineers should be equipped with knowledge of not only the technology but also the policy. The lecture deals with various elements constituting the policy such as nuclear related administration, government, organization, law, nuclear regulation, R&Ds, radioactive management etc. | ||
| NE7002 | Introduction to spent nuclear fuel management | |
| This course aims at introducing general aspects of spent nuclear fuel management comprehensively. Accordingly, this course consists of introductory lectures on spent fuel management by an assigned faculty member in Nuclear Engineering Department and a series of special lectures on various fields such as criticality, heat removal, shielding, structural analysis, nuclear fuel cycle, nuclear regulation and policy delivered by collaboration of top-level experts in other institutions and professors in Nuclear Engineering Department. | ||
| NE7003 | Special topic on spent nuclear fuel management | |
| This is an open-ended course for engineering design in which element technology regarding spent nuclear fuel can be comprehensively discussed. This course aims at building capacity in design and management technology of spent nuclear fuel by applying multiple ways of learning such as team teaching, performing team project, evaluation of students’ presentations. | ||
| NE7101 | Nuclear Reactor Analysis I | |
| This course provides the advanced contents for the Nuclear Reactor Theory 1 and 2 courses in undergraduate course. This course is one of the common courses in all the courses of the graduate school. This course is closely related to the Nuclear Reactor Analysis 2. This course addresses the neutron diffusion theory, nuclear reactor kinetics, and core analysis methods coupled with depletion calculations. Also, this course provides numerical methods for solving neutron diffusion analysis, resonance treatment methods, integral transport methods, and homogenization methods for the nuclear reactor core. However, this course can be attended by all the graduate students. | ||
| NE7102 | Nuclear Reactor Analysis Ⅱ | |
| This course is an advanced one for the graduate students who have taken the Nuclear Reactor Analysis 1. This course mainly addresses advanced numerical methods for solving the neutron and gamma transport equations. The contents of this course includes the derivation of neutron transport equation, adjoint transport equation, PN method, discrete ordinates methods (DOM), integral transport methods, and acceleration methods for DOM. | ||
| NE7104 | Advanced Numerical Analysis | |
| This course addresses the computer programming using C++ or Fortran 90 for the numerical methods that are given in the Nuclear Reactor Analysis 1 and 2. Some projects associated with the implementation of the numerical methods for solving multi-group neutron diffusion and transport equations are assigned to the students. This course also provides the theories required for the numerical methods such as the computer programming, the convergences of iteration methods and eigenvalue theory. | ||
| NE7105 | Reactor Core Design Project | |
| This course designs the realistic commercial reactor cores using commercial core design code packages. The some experts from the industrial companies or research institutes give the lectures and guide core design practices. The core design code packages can be CASMO(HELIOS) or DeCART2D/MASTER code system or KARMA-ASTRA code system depending on the affiliations of lecturers. This course which is an advanced course of the undergraduate course ‘Nuclear Reactor Core Design’ can be attended only by the students took the Nclear Reactor Analysis I course previously. | ||
| NE7107 | Nuclear Reactor Design Concept | |
| This course is to develop the insights of the students on the research and development of advanced reactors and the design concepts of several different types of reactors such as research reactors and electricity generation reactors are inter-compared and analyzed. The students are required to practice development of the reactor core design candidates with integrated consideration of material, thermal hydraulics, and reactor core physics aspects. Also, it is required to judge the realistic feasibilities of the reactor design concepts with consideration of front and back-end fuel cycles. | ||
| NE7108 | Monte Carlo Methods | |
| This course is for all the graduate student irrespective of their majorities. This course addresses the basic theories and techniques such as probability distributions, sampling methods, and variance reduction techniques. In particular, the Monte Carlo methods for particle transport are given to include the eigenvalue and fixed source problems. The computer programing will be assigned to the students to implement the Monte Carlo method for neutron or gamma transport. | ||
| NE7110 | Advanced Reactor Experiment | |
| This is an advanced course of the undergraduate course ‘Nuclear Reactor Experiment and Management’. The students who took the undergraduate course are not recommended for this course. Individually the students present the results of the experiments after performing six different experiments and there are also group discussions in English on the analysis results of the experiments. | ||
| NE7111 | Special Problems of Reactor Physics I | |
| In this course, the graduate students who are performing the reactor physics are required in personnel to select some research topics and to perform the term project with the professor in order to develop the individual research capability on the integrated and detailed research topics. During the initial stage of the course, the research topics are selected through the discussion of students and professor. Their research performances are periodically checked through meetings. | ||
| NE7201 | Thermal Hydraulics of Nuclear Power Reactor I | |
| Basic theories for understanding and analysis of thermal-hydraulics in nuclear power plant systems are introduced with focus on thermodynamics, fluid mechanics, and heat transfer. Significant thermodynamic parameters to define thermal-hydraulic performances of a power plant are defined, and single/two-phase flow and heat transfer theories based on fluid flow and heat transfer mechanisms are introduced. Based on the basic theories, thermal-hydraulics analyses on various nuclear systems are performed. | ||
| NE7202 | Thermal Hydraulics of Nuclear Power Reactor II | |
| This class aims at understanding and modeling the thermal-hydraulic behavior of key components in nuclear and conventional power systems, Various theories of thermodynamics, fluid mechanics, and heat transfer are applied to design, thermal-hydraulic performance analysis and safety assessment of various nuclear systems. Lastly, a systematic analysis of thermal-hydraulics in single sub-channel is performed by integrating the introduced thermal-hydraulic theories. | ||
| NE7203 | Thermal Hydraulics of Nuclear Power Reactor III | |
| The lecture deals with the thermal hydraulic methodologies regarding the nuclear power plant thermal hydraulic design. In-depth studies on the first principles of the methodologies are dealt with such as fractional analysis, scaling and scale analysis, non-dimensionalization of the governing equations and derivation of governing parameters. | ||
| NE7204 | Special Problems of Thermal Hydraulics I | |
| This class introduces and discusses special topics of thermal hydraulics related to design, operation and safety of nuclear power plants. | ||
| NE7205 | Special Problems of Thermal Hydraulics II | |
| This class introduces and discusses special topics of thermal hydraulics related to design, operation and safety of nuclear power plants. | ||
| NE7208 | Nuclear Safety Analysis | |
| This lecture is an in-depth study extending the undergraduate level safety engineering regarding nuclear reactor and nuclear power plant system. It deals with the nuclear safety philosophy, characteristics of nuclear safety. Accident analysis are performed based on deterministic safety analysis of reactor core and thermal hydraulic accident as the team project. | ||
| NE7209 | Two Phase Flow Analysis | |
| The basic concept and the flow patterns of the two phase flow are dealt with. Empirical and theoretical analysis methodologies are introduced. Methods of approaches for the condensation and boiling heat transfer phenomena are discussed. Based upon the studies, nuclear power plant system, steam generator, condenser, and the nuclear reactor are anaylized. | ||
| NE7210 | Power Plant Technology | |
| Design concepts of various nuclear power plants which convert nuclear energy into electricity are introduced. Next, engineering design and operating theories of typical Korea standard pressurized light water nuclear power plants and major components of thermal-hydraulics and safety-related systems - steam generator, pressurizer, pump, turbine, condenser, BOP and engineered safety features are reviewed in detail. | ||
| NE7211 | Numerical Method of Thermal Hydraulics | |
| This course introduces theories and skills for numerical analysis of thermal-hydraulics in nuclear power plant systems. Fundamental conservation equations of mass, momentum and energy as well as equation of state are reviewed for understanding of two-phase flow and heat transfer in nuclear systems. The course starts with a primer on control volume methods and the construction of a homogeneous equilibrium model code. The primer is valuable for giving students the basics behind such codes and their evolution to more complex codes for thermal-hydraulics and computational fluid dynamics. In the later half of the course, a series of tutorial about an advanced thermal-hydraulic system analysis code are taught. Then, students conducts a term project about safety analysis of a nuclear power plant system for a postulated accident using the code. | ||
| NE7212 | Thermal Hydraulic Experiments and Practice | |
| This lecture teaches general methods of thermal hydraulic measurements such as temperature, pressure, flow rate, etc. Student choose one of the measurements as his/her team project. | ||
| NE7301 | Fracture Mechanics | |
| This class aims at cultivation of knowledge necessary for design and evaluation of major components and structures in nuclear power plants. In essential, governing equations and compatibility equations for stress analysis of materials are reviewed. Subsequently, engineering parameters relating to specific fracture mechanisms are defined and structural integrity assessment schemes as well as experimental methods are introduced. | ||
| NE7302 | Thermodynamics of Solids | |
| The thermodynamics of solids are studied on the basis of classical thermodynamics and the thermodynamic properties of important materials from statistical thermodynamics are described. Explore thermodynamic software and explore it in relation to accident source term. Review important thermodynamic models of structural materials and nuclear fuel materials. | ||
| NE7303 | Advanced Power Reactor Materials | |
| This class introduces fundamentals of structural material features and their variation due to irradiation by neutron and others. In particular, changes of nuclear fuel characteristics according to burning time and issues on major nuclides during combustion and/or disposal are reviewed. | ||
| NE7305 | Irradiation Effects for Reactor Materials | |
| This class aims at understanding of material reactions with radiation and relevant models to estimate displacements of atoms from their lattice site due to primary knock-on atom. Engineering methods to quantify mechanical properties and material damages are also reviewed with mitigation actions. | ||
| NE7306 | Corrosion Analysis for Reactor Material | |
| This course is designed to understand the corrosion process that occur during the operation of the nuclear power plants. The course will cover the mechanisms of corrosion of the structural materials and the effect of the material degradation on the system integrity. | ||
| NE7308 | Special Problems of Nuclear Materials I | |
| This class aims at understanding of elementary theories and selection of materials used in nuclear power plants. Analysis methods of crystal structures, atomic/ionic arrangements, imperfections and mechanical properties are introduced with focused on reactor operation, degradation mechanisms and relevant research activities. | ||
| NE7309 | Special Problems of Nuclear Materials II | |
| This class aims at understanding of advanced theories and selection of materials used in nuclear power plants. Manufacturing processes related to solidification and enhancement of mechanical properties of reactor materials are introduced with focused on evaluation of degradation effects, establishment of management strategies and relevant experiences. | ||
| NE7401 | Radioactive Waste Disposal Engineering | |
| This course is interrelated to Radioactive Waste Management Engineering in undergraduate course. Main themes to be introduced in this course are as follows: transport, storage and disposal of radioactive waste engineering consideration to improve the safety new trends in development of relevant technology. | ||
| NE7402 | Radioactive Waste Treatment Engineering | |
| This course is interrelated to Radioactive Waste Management Engineering in undergraduate course. Main themes to be introduced in this course are as follows: generation and processing of radioactive waste at nuclear power plants, and new trends on the treatment process for ultimate minimization of radioactive waste. | ||
| NE7403 | Special Problems of Radioactive Waste Management I | |
| The goal for sustainable utilization of nuclear energy can be attained under the valid proposition of safe treatment and disposal of radioactive waste. Development of technology for long-term isolation and containment of radioactive waste which contains radioactive material differently from industrial waste is needed. Therefore this course is designed to discuss on the themes such as: processing of radioactive waste from nuclear power plants, engineering aspects in disposal of radioactive waste, and trends in development of related technology. | ||
| NE7404 | Special Problems of Radioactive Waste Management II | |
| The goal for sustainable utilization of nuclear energy can be attained under the valid proposition of safe treatment and disposal of radioactive waste. Development of technology for long-term isolation and containment of radioactive waste which contains radioactive material differently from industrial waste is needed. Therefore this course is designed to discuss on the themes such as: processing of radioactive waste from nuclear power plants, engineering aspects in disposal of radioactive waste, and trends in development of related technology. | ||
| NE7405 | Engineering for Decontamination and Decommissioning | |
| This course is interrelated to the pre-disposal aspect of Radioactive Waste Management Engineering in undergraduate course. Decontamination and decommissioning (D&D) issues which are to be essentially considered in nuclear facilities are introduced. Main themes to be discussed in this course are as follows: current status of and new trends in D&D technology, and establishment of D&D scenarios through D&D case studies. | ||
| NE7406 | Advanced Reactor Chemistry | |
| Important theories on the chemical aspects of nuclear power plants such as high temperature thermodynamics, electrochemistry, metal corrosion, and radiochemistry are introduced. In addition, water chemistry technology for reducing material corrosion and ensuring nuclear fuel integrity is reviewed and related state-of-the art technology is discussed. | ||
| NE7407 | Nuclear Chemical Engineering | |
| This course introduces main theories and technical status regarding nuclear fuel cycle. Major research and new direction of research on processing and disposal of spent nuclear fuel such as the followings are mainly discussed: nuclide composition change in burning of nuclear fuel, prediction of spent nuclear fuel composition, and reprocessing technology. | ||
| NE7501 | Advanced Health Physics I | |
| Course correlated with health physics in undergraduate curriculum. This course covers Scientific and engineering concerned with radiation physics, radiation biology, radiation protection, and nuclear regulations with goal of safety of radiation. Students determined a project associated with health physics and performed the project. | ||
| NE7502 | Advanced Health Physics II | |
| Course correlated with health physics in undergraduate curriculum. This course covers dosimetry methods for external exposure and internal exposure. Students determined a project associated with health physics and performed the project. | ||
| NE7503 | Environmental Impact Analysis | |
| Course correlated with health physics in undergraduate curriculum. This course covers environmental impact analysis, site selection criteria for nuclear facilities, computer codes for environmental impact analysis. | ||
| NE7504 | Radiation Shielding Technology | |
| Course correlated with radiation detection and dosimetry experiment course in undergraduate curriculum. This course covers radiation shielding theory, radiation interactions with matter, radiation transport theory, recent radiation shielding technology, and design of radiation shielding for nuclear and radiation facilities. | ||
| NE7505 | Avanced Radiation Detection Theory I | |
| Course correlated with radiation detection theory in undergraduate curriculum. This course covers physics and electronics of radiation detection and instrumentation systems for application to nuclear energy, radiological sciences, radiation protection, health physics, medical physics and imaging, and industrial safety and control system. Students determined a project associated with radiation detection and performed the project. | ||
| NE7506 | Advanced Radiation Detection Theory II | |
| Course covers radiation experiments and design of radiation detectors based on theory from Advanced Radiation Detection Theory 1 and computer codes of radiation transports for radiation detector design. | ||
| NE7601 | Advanced Engineering Mathematics | |
| This course deals with calculus, linear algebra, discrete math, and probability and statistics among advanced mathematical theories that are essential for graduate education courses in nuclear/radiology. This course will be extended from the undergraduate curriculums, and will also deal with special topics that are necessary for understanding and applying other subjects. If necessary, the special lectures will be organized to pay attention to specific topics in detail. | ||
| NE7602 | Probabilistic Safety Assessment | |
| The basic theory and practice of probabilistic safety assessment is introduced. Students will learn the history of probabilistic safety analysis, mathematics, system analysis methods, and conduct a project to analyze simple systems using software. It provides the latest issues related to probabilistic safety assessment and has an opportunity to understand pros and cons and future development and application directions. | ||
| NE7603 | Advanced Nuclear Thermal-Hydraulic Measurement Methodology | |
| Temperature, pressure, and flow rate are the three main measurement parameters composing more than 90% of measurements. Advanced measurement methodologies based on the first principles are dealt with. Especially the principles of measurements and the various causes of measurement errors are taught and relevant experiments are performed. | ||
| NE7604 | Fractional Analysis and Similarity Theory | |
| Fractional analysis is the methodology of getting the information instead of solving the governing equations. In the process of mathematical modeling of the physics and solving the problem, using the dimensional information, methods of deriving governing parameters, parameter absorption, and simplifications, are taught. Based on the methodology, design method for simialr system using reduced scale facitity is dealt with. | ||
| NE7608 | Advanced Radiation Detection | |
| Course is correlated with radiation detection in undergraduate curriculum. This course covers Radiation detection counting statistics, Nuclide analysis by spectrum analysis, approach of external and internal dose assessment. Students determined a project associated with dose assessment using radiation detection and performed the project | ||
| NE7609 | Advanced Health Physics | |
| This course is scientific and engineering field concerned with radiation protection of people and their environment from potential radiation hazards, while making it possible to enjoy the beneficial uses of radiation and nuclear power. The course covers atomic and nuclear physics, radiation detection, radiation protection, and radiation safety regulations. | ||
| NE7610 | Comprehensive Design of Radiation Safety | |
| The process of collecting and solving difficulties by designating mentors for each entity, such as regulatory agencies/users/waste management agencies, etc., is carried out in the form of a team project during the comprehensive design time. | ||
| NE7611 | Special Topics on Nuclear Safety Regulation | |
| This course helps students to understand the philosophy, principles and background knowledge on nuclear and radiation safety regulation, and to learn practical knowledge on how the safety regulation is implemented in actual nuclear facilities. A series of theoretical lectures on the Global Nuclear Safety Regime based on the Convention on Nuclear Safety and Principles of Nuclear Safety Regulation along with the domestic legal bases of safety regulation such as the Nuclear Safety Act, the Act for Physical Protection and Radiological Emergency, and the Act on Protective Action Guidelines against Radiation in the Natural Environment are to be delivered. The inter-dependencies between engineering technology and administrative regulations are to be discussed together with the main lecturer-in-charge and invited experts in various sub-areas of the nuclear safety regulation. Furthermore, an opportunity of in-clsss on-the-job training on nuclear and radiation safety review will be provided through mentorship of respective experts. | ||
| NE7612 | Special Topics on Nuclear Security Regulation | |
| This course helps students to understand the philosophy and background knowledge on nuclear non-proliferation and security, and to experience the interface between engineering technology and administrative regulation. A series of theoretical lectures on the history and development of the International Convention for the Suppression of Acts of Nuclear Terrorism and Convention on the Physical Protection of Nuclear Material, and the domestic legal bases such as the Nuclear Safety Act, and the Act for Physical Protection and Radiological Emergency are to be delivered. An on-the-job training is provided to explore major issues in the fields of safeguards, export control, physical protection, cyber security, and safety-security interface and to actually conduct a review process on a specific issue through a mentor of experts. | ||
| NE7616 | Energy Industry-Academia Colloquium | |
| The goal is to enhance the level of knowledge and understanding in the field of intelligent energy production system design, operation, and analysis. This is achieved through expert-invited seminars, student team discussions, and research projects, all related to topics in intelligent energy production systems. These activities aim to foster an improved grasp of the subject matter. | ||
| ENV7103 | Carbon Neutral System Theory | |
| Causes and consequences of climate crisis, policies and agreements for overcoming the climate crisis, carbon neutral concept and reduction plans for each industry, overall theory on carbon emission calculation and energy efficiency | ||
| IE733 | Digital Manufacturing | |
| Digital manufacturing is the course to lean manufacturing IT component as well as Computer aided solutions in order to improve the productivity and interoperability by using cyber physical system. | ||
| IE742 | Analysis of Smart-Technology Market | |
| "Consumer preference theory and application to model and analyze smart energy technology market. Understanding the consumer preference analysis process and related main theories and analysis methodologies. The goal of this course is to review the fundamental theory and methodologies of consumer behavior. Particularly, this course covers the theoretical, empirical and applied methods of consumer decision-making process." | ||
| IE762 | Sustainable Decision Making | |
| Introduction of basic theories and concepts of energy innovation cases in major countries, policies related to carbon neutral implementation, and analysis of sustainable decision-making. Various modeling methods and analysis techniques to formulate decision-making problems and solve them | ||
| IE763 | Energy Big Data Analysis | |
| The concept, technology, and use cases of big data used in various industrial fields including the energy field will be reviewed, and the role and required competency as a big data analyst | ||
| IE765 | Statistical Learning | |
| "The lecture offers a comprehensive exploration of the fundamental concepts of statistical learning, an innovative field that fuses statistical principles with data-driven pattern recognition. The subject matter spans both the theoretical foundations and the practical techniques necessary to leverage statistical learning in real-world scenarios." | ||
| ME7108 | Advanced Heat Transfer | |
| This course covers the fundamental governing equations of conduction, convection, radiation, and phase change heat transfer that are closely related to layered manufacturing processes. It focuses on the understanding of these equations and methodologies for practical problem-solving. | ||
| ME7119 | Startup Practice | |
| The course aims to mentor the actual start-up process for prospective or early start-up students. In addition, it provides opportunities for industry mentor seminars and mentoring. | ||
| ME7126 | Hydrogen Energy Fundamentals | |
| The objective of this study is to understand the basic electrochemical and thermodynamic principles involved in the production and utilization of hydrogen energy. Based on this foundational knowledge, the study aims to provide a comprehensive understanding of the working principles and engineering designs of various fuel cells (including PEM, AFC, SOFC) and electrolysis methods (such as PEM, SOEC, AEM). | ||
| ME7127 | Energy System Design and Optimization | |
| This course introduces the fundamental mechanisms, practical applications, and advanced topics of conduction, convection, and radiation heat transfer. This course includes thermal physics, transient heat conduction, heat exchangers, blackbody radiation & radiative transfer equation, and solar radiation. | ||
| ME7128 | Intelligent Thermo-Fluid Engineering | |
| This course reviews the fundamental theories related to thermodynamics, heat transfer, and fluid dynamics relevant to energy systems. It aims to enable not only mechanical engineering students but also students from other backgrounds to grasp the foundational content of mechanical engineering core subjects. Around the latter 3-4 weeks of the course, an introduction to multiphysics simulation is provided. | ||
| ME7129 | Computational Analysis of Intelligent Thermo-Fluid System | |
| This course covers the partial differential equations and numerical analysis of heat transfer and fluid dynamics constituting energy systems, as well as applications of Computational Fluid Dynamics (CFD) and Computer-Aided Engineering (CAE). We apply fundamental theories like multiphase flows and optimization to energy systems. | ||
| ME728 | Viscous Fluid Flow | |
| "Learn the effect of viscosity on fluid flow. Students learn the concept of viscous fluid, learn kinematics of flow field, and deal with basic equations of viscous flow. We study Navier-Stokes equations and deal with boundary layer equations." | ||
| NE7101 | Nuclear Reactor Analysis I | |
| "This course provides the advanced contents for the Nuclear Reactor Theory 1 and 2 courses in undergraduate course. This course is one of the common courses in all the courses of the graduate school. This course is closely related to the Nuclear Reactor Analysis 2. This course addresses the neutron diffusion theory, nuclear reactor kinetics, and core analysis methods coupled with depletion calculations. Also, this course provides numerical methods for solving neutron diffusion analysis, resonance treatment methods, integral transport methods, and homogenization methods for the nuclear reactor core. However, this course can be attended by all the graduate students." | ||
| NE7102 | Nuclear Reactor Analysis Ⅱ | |
| This course is an advanced one for the graduate students who have taken the Nuclear Reactor Analysis 1. This course mainly addresses advanced numerical methods for solving the neutron and gamma transport equations. The contents of this course includes the derivation of neutron transport equation, adjoint transport equation, PN method, discrete ordinates methods (DOM), integral transport methods, and acceleration methods for DOM. | ||
| NE7108 | Monte Carlo Methods | |
| "This course is for all the graduate student irrespective of their majorities. This course addresses the basic theories and techniques such as probability distributions, sampling methods, and variance reduction techniques. In particular, the Monte Carlo methods for particle transport are given to include the eigenvalue and fixed source problems. The computer programing will be assigned to the students to implement the Monte Carlo method for neutron or gamma transport." | ||
| NE7211 | Numerical Method of Thermal Hydraulics | |
| This course introduces theories and skills for numerical analysis of thermal-hydraulics in nuclear power plant systems. Fundamental conservation equations of mass, momentum and energy as well as equation of state are reviewed for understanding of two-phase flow and heat transfer in nuclear systems. The course starts with a primer on control volume methods and the construction of a homogeneous equilibrium model code. The primer is valuable for giving students the basics behind such codes and their evolution to more complex codes for thermal-hydraulics and computational fluid dynamics. In the later half of the course, a series of tutorial about an advanced thermal-hydraulic system analysis code are taught. Then, students conducts a term project about safety analysis of a nuclear power plant system for a postulated accident using the code. | ||
| NE7302 | Thermodynamics of Solids | |
| The thermodynamics of solids are studied on the basis of classical thermodynamics and the thermodynamic properties of important materials from statistical thermodynamics are described. Explore thermodynamic software and explore it in relation to accident source term. Review important thermodynamic models of structural materials and nuclear fuel materials. | ||
| NE7306 | Corrosion Analysis for Reactor Material | |
| This course is designed to understand the corrosion process that occur during the operation of the nuclear power plants. The course will cover the mechanisms of corrosion of the structural materials and the effect of the material degradation on the system integrity. | ||
| NE7601 | Advanced Engineering Mathematics | |
| This course deals with calculus, linear algebra, discrete math, and probability and statistics among advanced mathematical theories that are essential for graduate education courses in nuclear/radiology. This course will be extended from the undergraduate curriculums, and will also deal with special topics that are necessary for understanding and applying other subjects. If necessary, the special lectures will be organized to pay attention to specific topics in detail. | ||
| NE7607 | Engineering parallel computing | |
| We cover the MPI(Message Passing Interface), OpenMP, GPGPU parallel computing technique to enhance the performance of the multiphysics simulations and big data processing in the nuclear engineering. This subject also deal with the programming methodology for high efficiency parallelizing and performance profiling of the numerical analysis code. | ||
| NE7613 | Novel materials for next-generation nuclear system | |
| Learn the requirements for materials to be used in molten salt reactors, high-temperature gas reactors, and high-temperature metal-coolant reactors among the 4th generation nuclear power systems, and the basic knowledge required to design materials for next-generation nuclear systems. | ||
| NE7614 | Hydrogen Production Using Nuclear Energy | |
| Learn about the concepts, characteristics and design theories of 3.5~4 generation nuclear reactor-based hydrogen production plants | ||
| NE7615 | Hydrogen storage and material degradation | |
| Study the basic theory to learn the material deterioration mechanism of hydrogen, learn about various hydrogen storage alloys including Zr cladding, Fe-based alloys, Ni-based alloys, and hydrogen/hydride degradation. | ||
| NE7618 | Energy Industry-Academia Collaborative Project | |
| Students seeks issue problems from energy industry and perform industry-academia collaborative design projects, Each student takes supervision under a team of an industrial expert and a professor. | ||
| NE7619 | Nuclear energy policy | |
| Nuclear engineering is closely related to the international policies. Accordingly, nuclear engineers should be equipped with knowledge of not only the technology but also the policy. The lecture deals with various elements constituting the policy such as nuclear related administration, government, organization, law, nuclear regulation, R&Ds', radioactive management etc. | ||
| NE7620 | Introduction to Intelligent Energy | |
| Learn about the concept of next-generation reactor-based P2X sector coupling and the future energy portfolio for the realization of carbon neutrality by 2050. | ||
| NE7621 | Nuclear security for advanced nuclear reactors | |
| This course focuses on nuclear security, physical protection, and nuclear safeguards for an advanced nuclear reactor. This lecture is aimed to know how to encourage peaceful uses and how to enhance the proliferation resistance of the advanced nuclear reactor system. |