Prof. Dr. Ahmet Cengiz B. U. Ü. Fen-Edebiyat Fakültesi Fizik Bölümü 16059 Görükle Bursa email: acengiz@uludag.edu.tr Tel: 0224 2941695
18
Website:
19
Objective of the Course:
Aim of the course is to provide students with advanced knowledge related to the neutron physics. Neutron interactions with matter, neutron transport equation, the teaching physical information about nuclear reactors.
20
Contribution of the Course to Professional Development
Learns information of Neutron Physics the necessary for Nuclear Physics.
21
Learning Outcomes:
1
The Neutron Transport Equation: Basic concepts and definitions of variables are learned. ;
2
The Diffusion Approximation of Neutron Transport Equation. Neutron Diffusion Theory are learned. ;
3
Derivation of One-Speed Diffusion Equation are learned. ;
4
Criticality Conditions in Bare Homogeneous Reactor, Reflected Reactor for special geometry are learned.;
5
Numerical Solution of Diffusion Equation are learned.;
22
Course Content:
Week
Theoretical
Practical
1
The Neutron Transport Equation
2
Derivation of time-dependent neutron transport equation
3
The Diffusion Approximation of Neutron Transport Equation.
4
Neutron Diffusion Theory
5
Derivation of Fick's law
6
Derivation of One-Speed Diffusion Equation
7
Solutions of the One-Speed Diffusion Equation for Non-multiplying Media
8
Solutions of the One-Speed Diffusion Equation for Multiplying (Reactor Core) Media
9
Criticality Conditions in Bare Homogeneous Reactor, Reflected Reactor for special geometry
10
Introduction to multi-group diffusion theory
11
multiplying media and criticality conditions
12
Continue
13
Slowing-Down and Diffusion of Neutrons
14
General Review and Problem Solutions
23
Textbooks, References and/or Other Materials:
K.H.Beckurts; K.Wirtz, Neutron physics,Springer-Verlag, 1964. Raymond L. Murray., Introduction to Nuclear Engineering,Prentice-Hall,INC.1954. Duderstadt J.J. and Martin W.R., Transport Theory, Wiley , New York,1979. Bell George I. and Glasstone Samuel, Nuclear Reactor Theory, Krieger Publishing Company, 1985. Lamarsh John R., Introduction to Nuclear Reactor Theory , Amer Nuclear Society; ISBN: 0894480405; September 2002.
24
Assesment
TERM LEARNING ACTIVITIES
NUMBER
PERCENT
Midterm Exam
0
0
Quiz
0
0
Homeworks, Performances
0
0
Final Exam
1
100
Total
1
100
Contribution of Term (Year) Learning Activities to Success Grade
0
Contribution of Final Exam to Success Grade
100
Total
100
Measurement and Evaluation Techniques Used in the Course
The system of relative evaluation is applied.
Information
25
ECTS / WORK LOAD TABLE
Activites
NUMBER
TIME [Hour]
Total WorkLoad [Hour]
Theoretical
14
3
42
Practicals/Labs
0
0
0
Self Study and Preparation
14
3
42
Homeworks, Performances
0
3
42
Projects
14
1
14
Field Studies
0
0
0
Midtermexams
0
0
0
Others
14
3
42
Final Exams
1
2
2
Total WorkLoad
184
Total workload/ 30 hr
6,13
ECTS Credit of the Course
6
26
CONTRIBUTION OF LEARNING OUTCOMES TO PROGRAMME QUALIFICATIONS
