Spring 2008

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

JaeJun Lee (leejj@nurapt.kaist.ac.kr, x3859)

Lecture

In English

Links to

 Spring 2006



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

Notice
 

 Date

Contents

2008.2.18

     We have no class on Feb. 19(Tuesday) and 21(Thursday), and We will have make up class in another day.

2008.2.27

     We will have makeup class 8:30 pm on Feb. 27(Tuesday) in group lecture room(1402).

2008.2.27

      Regular lecture room is changed to group lecture room(1402).

2008.3.3

       Reading Assignment : cf. Henry, pp 398-402

2008.3.19

       Appendix A. PWR Benchmark Problems : note4A

2008.5.15

       VENTURE manuals for final project : venture

2008.5.19

      We have no class on May 19(Tuesday) , and We will have make up class in another day.

2008.5.26

  We have no class on May. 17(Tuesday).

2008.5.26

  We will have makeup class 7:30 pm on May 26(Monday) in group lecture room(1402).

2008.5.26

  We will have Final Presentation on June 3 (Tuesday)10:30 am on  

                 i) PS #7       and          ii) PS #8

 

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
 	2.12		Overview and Introduction
	2.14/19         	Neutron Transport Equations
	2.21/26        	Diffusion Theory
	2.28/3.4        	Multigroup Diffusion Theory - Group Constants
	3.6/11       	Multigroup Diffusion Theory - Group Constants
	3.13            	Multigroup Diffusion Theory - Numerical Analysis
	3.18/20         	Multigroup Diffusion Theory - Numerical Analysis
	3.25/27        	Multigroup Diffusion Theory - Numerical Analysis
	4.1/3        	Review, Midterm Exam
	4.8           	Coarse Mesh Nodal Methods
	4.10/15          	Coarse Mesh Nodal Methods
	4.17/22         	Equivalence Theory
	4.24/29        	Adjoint Equations
	5.1/6        	Perturbation/Variational Methods
	5.8/13       	Reactor Kinetics
	5.15/20		Reactor Fuel Burnup, Actinide Trasmutation
	5.22/27		Review, Final Exam
  
Project Schedule
 
 
Problem Sets
 

 

           Due Date

           3. 11                    Problem Set #1

           3. 18                    Problem Set #2

           3. 25                    Problem Set #3

           4. 22                    Problem Set #4

           4. 29                    Problem Set #5

           5.   6                    Problem Set #6

           5. 20                    Problem Set #7

            6.  3                    Problem Set #8

 

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


Textbook


References

 


Contact leejj@nurapt.kaist.ac.kr