SNU Monte Carlo LaboratoryNUCLEAR ENGINEERING

409.301A 001(전필 / 학사 / 3학년)

A firm understanding of neutron behavior in a nuclear reactor is crucial in the design of a new reactor or in the safe operation of an existing one. This course deals with the basic concepts, facts, and analysis methods needed for understanding the neutron behavior. Major subjects to be covered are: 1) various neutron interaction with matter; 2) the basic concepts and methods needed for reactor analysis such as cross sections, flux, slowing down power, multiplication constants, and etc; 3) derivation and solution of the governing equations for the neutron behavior in a finite medium, with suitable assumptions and simplification in composition, geometry, and reactions.

M1509.001100 001(전선 / 학사 / 4학년)

This course copes with computer software widely applied in the field of nuclear engineering. They include a therm-fluid analysis code, structure-materal analysis code, Monte Carlo particle transport code, neutron diffusion code, etc., which are essential for the design and transient analyses of a nuclear engineering system (nuclear fission, nuclear fission, radiation source, etc.). In the course, students learn knowledge on the computer programs and practice simulations using them. They gain a hands-on experience with the use of the programs through computational homeworks and projects on various nuclear system simulations. The course also provides tutorials for data exchange between codes to establish code coupling and multi-physics simulation. Finally, the state-of-the-art and future perspectives of the nuclear engineering simulations are provided.

409.310A 001(전선 / 학사 / 3학년)

In the process of solving engineering problems, it is often impossible to obtain exact mathematical solutions or to identify the physical phenomena by experiments. Computers are used in this case to obtain approximate solutions or to perform simulations for numerical experiments. Numerical analysis is to develop the methods required for the numerical solution and then to make computer programs to obtain the practical solutions. This course deals with the basic methods and programming practices needed for the numerical analysis for various engineering purposes so that the students attain the fundamental ability of practical problem solving. This course is an introductory course to general numerical methods and is open to all the disciplines of college of engineering. More advanced numerical methods for nuclear reactor analysis is covered in the companion course named nuclear reactor numerical analysis and design.

409.328 001(전필 / 학사 / 3학년)

This course provides seminars regarding nuclear systems, as well as industrial trends of nuclear engineering.

M1509.000400 001(전선 / 학사 / 4학년)

Through this course, students can learn theories of nuclear reactor physics experiments and participate real-time experiments at AGN-201K of Kyung Hee University by Internet Reactor Laboratory equipments. The reactor physics experiments at AGN-201K are composed of reactor operation, reactivity measurements, critical approach, rod worth measurement, flux mapping, and temperature and reflector effects. The neutron diffusion equation and the point kinetics equations are reviewed and various nuclear reactor behaviors are simulated using Matlab and a Monte Carlo neutron transport analysis code. Analyses of experimental data will enhance the understanding of the nuclear reactor behavior.