Spring 2010

NQE512 Nuclear Reactor Analysis and Design




Time

Tuesday 10:30-12:00  Thursday 10:30-12:00

Classroom

Room #2424 (ME Building)


Instructor

Prof. Nam Zin Cho (nzcho@kaist.ac.kr, x3819)

Teaching Assistant

Hanjong Yoo (hjyoo@nurapt.kaist.ac.kr, x3859)

Lecture

In English

Links to

 Spring 2008



[ Notice | Keywords | Course Outline | Lecture Schedule | Project Schedule | Course Grading | Problem Sets | Textbook/References ]

Notice
 

 Date

Contents

 2010.02.18

 No class on Feb. 23 (Tue) 10:30AM / Make up class on Feb. 22(Mon) 7:00PM

2010.04.19

Reading Assignment : AFEN method

2010.05.04

          No class on

                 (1) May. 11 (Tue)

                 (2) May. 13 (Thu)          

          Make up class will be on

                 (1) May.   7 (Fri)   10:30AM

                 (2) May. 20 (Thu) 10:30AM

2010.05.07

           Presentation of Class Project IV is scheduled on May 25 (Tue) 10:30 AM

 

Keywords
 
Transport Equations, Diffusion Theory, Multigroup Diffusion Equations, Multigroup Constants, Adjoint Equations, Coarse Mesh Nodal Methods, Equivalence Theory, Reactor Kinetics, Actinide Transmutation
 
 
Course Outline
 
This course is designed to cover the nuclear reactor analysis and design; introduction of neutron transport equation, approximation of diffusion theory, generation of multigroup cross sections, solutions of few-group and multi-group neutron diffusion equations, calculation of energy distribution of fast and thermal neutrons, and homogenization of heterogeneous reactor. It also include recent methods (eg. nodal method) to predict the spatial and temporal distribution of neutrons. This course includes several projects running design computer code systems under real reactor design situation.
 
Lecture Schedule
 
	2.2               Overview and Introduction
	2.4/9             Neutron Transport Equations - Multigroup Approximation
	2.11/16           Diffusion Theor Approximation
	2.18/23           Multigroup Diffusion Theory - Group Constants
	2.25/3.2          Multigroup Diffusion Theory - Group Constants
	3.4/9            	Multigroup Diffusion Theory - Numerical Analysis
	3.11/16        	Multigroup Diffusion Theory - Numerical Analysis
	3.18/23        	Multigroup Diffusion Theory - Numerical Analysis
	3.25/30        	Review, Midterm Exam
	4.1/6            	Coarse Mesh Nodal Methods
	4.8/13            Coarse Mesh Nodal Methods
	4.15/20        	Equivalence Theory
	4.22/27        	Adjoint Equations
	4.29/5.4       	Perturbation/Variational Methods
	5.6/11          	Reactor Kinetics
	5.13/18           Reactor Fuel Burnup, Actinide Trasmutation
	5.20/25	       	Review, Final Exam
  
Project Schedule
       
Problem Sets

 

           Due Date

           3. 11                    Problem Set #1

            March 9          Problem Set #1

            March 23        Problem Set #2

            April 8            Problem Set #3

            April 15          Problem Set #4

            April 27          Problem Set #5

            May 13          Problem Set #6

            May 20          Problem Set #7

 

Course Grading     
      
    1 Midterm       20%
    1 Final         20%
    Problem Sets    30%
    Projects        30%
    ----------------------
    Total          100%


Textbook


References

 


Contact hjyoo@nurapt.kaist.ac.kr