Nuclear Reactor Engineering

 

Openning date

 The second semester, 2^nd grade

 

Course outline

 This is a basic and core course work in nuclear engineering, which addresses neutron behavior in nuclear reactor core. This course work starts from the important concepts such as neutron flux and reaction cross sections to the derivation and its solution methods of the neutron diffusion equation for multiplying and non-multiplying systems. The course works addresses many things like : one-group reactor and critical equations, criticality condition, flux solutions for bare and reflected reactors, point kinetic equation and its solution, reactivity control and power change as time, reactivity feedback effects, and reactivity change as fuel depletion.

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Main subject

 The course works addresses many things like : one-group reactor and critical equations, criticality condition, flux solutions for bare and reflected reactors, point kinetic equation and its solution, reactivity control and power change as time, reactivity feedback effects, and reactivity change as fuel depletion.

 

Nuclear Reactor Theory

 

Openning date

 The first semester, 3^rd grade

 

Course outline

 This course addresses the mathematical formulations and physics of the nuclear reactor theory. The topics of this course includes the diffusion and transport theory of neutrons, analytic solution techniques of the neutron diffusion and transport equation. In addition, the applications of these equations for reactor analysis are introduced. Special emphasis is given on the understanding of the mathematical and physical characteristics of the eigenvalue problem in nuclear reactor theory.

In particular, this course work gives the detailed numerical solution methods for multi-group diffusion equation having fission source. A term project is given, in which each team has to write down a computer program to numerically solve multi-group diffusion equation. 

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Main subject

 Nuclear reactions and cross sections, Nuclear chain reaction, neutron multiplication and six factor formula, neutron transport theory, derivation of diffusion equation from transport equation, Analytic solution methods of one-speed diffusion equation, Mathematical understanding of slab-reactor with analytic solution, Mathematical and physical understanding of eigenvalue problem and criticality condition, Numerical solution methods for multi-group diffusion equation (1D and 2D).

 

Nuclear Reactor Physics

 

Openning date

 The second semester, 3^rd grade

 

Course outline

 This course work addresses theories and methods for nuclear reactor analysis as the advanced one of "Nuclear Reactor Theory" course work in the previous semester. In addition, it addresses the practical fuel assembly design using a commercial computer code in which the students will evaluate the reactivity coefficients and reactivity change as fuel depletion. The topics of this course work includes the followings : Nuclear Kinetic Theory, Multi-group Diffusion Theory, Perturbation theory, Slowing down theory and resonance approximations, Power distribution calculation and reactivity control, core depletion, fuel assembly calculation and design.

 

Main subject

 The topics of this course work includes the followings : Nuclear Kinetic Theory, Multi-group Diffusion Theory, Perturbation theory, Slowing down theory and resonance approximations, Power distribution calculation and reactivity control, core depletion, fuel assembly calculation and design.

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