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Course Information
Course Unit Title : Heat Transfer in Nuclear Reactors
Course Unit Code : 01MAK6108
Type of Course Unit : Optional
Level of Course Unit : Second Cycle
Year of Study : 1
Semester : 1.Semester
Number of ECTS Credits Allocated : 6,00
Name of Lecturer(s) : ---
Course Assistants :
Learning Outcomes of The Course Unit :
Mode of Delivery : Face-To-Face
Prerequisities and Co-requisities Courses : Unavailable
Recommended Optional Programme Components : Unavailable
Course Contents : Nuclear fission, Neutron Chain-Reacting systems, Neutron moderation without absorption, Neutron moderation with absorption, Fission, Fusion, Low-Energy Neutrons, Fermi theory of the bare thermal reactor, multiregional reactors-the group diffusion method, reactor kinetics, Fuel Burnup, Pressurized Water Reactors, Boiling Water Reactors, Duel-Cycle BWR, Gas Cooled Reactors, Pressurized Heavy Water Reactors, Thermal Breeder Reactors, Fast Reactors, Nuclear Plants, Fusion Reactors, Fusion-Fission Hybrid Reactor, Reactor Behavior and Control
Languages of Instruction : Turkish
Course Goals : Review of nuclear physics, Interaction of neutrons with matter, Nuclear fission, Neutron Chain-Reacting systems, the diffusion of neutrons, Neutron moderation without absorption, Neutron moderation with absorption and fission, Low-Energy neutrons, Fermi theory of the bare thermal reactor, multiregional reactors-the group diffusion method, reactor kinetics.
Course Aims : Review of nuclear physics, Interaction of neutrons with matter, Nuclear fission, Neutron Chain-Reacting systems, the diffusion of neutrons, Neutron moderation without absorption, Neutron moderation with absorption and fission, Low-Energy neutrons, Fermi theory of the bare thermal reactor, multiregional reactors-the group diffusion method, reactor kinetics.
WorkPlacement   Not Available
Recommended or Required Reading
Textbook :
Additional Resources : Nuclear System I
Nuclear System II
Basic Nuclear Engineering
Nuclear Reaction
Experimental Nuclear Physics
Nuclear Fission
Nuclear Engineering Handbook
Thermal Reactor Theory
The Elements of Nuclear Reactor Theory
Introductory Nuclear Reactor Theory
Reactor Analysis
Reactor Handbook
The Technology of Nuclear Reactor Safety Vol.2
Control of Nuclear Reactors and Power Plants
Material Sharing
Documents :
Assignments :
Exams :
Additional Material : The course is consist of lecture and class discussion. Class sessions will be mainly used for discussions to clarify concepts, ideas elaborated in the fundamental text books. Students therefore should read the assigned chapters and prepared for class participation at each session. Case studies, simulations and presentations will also be used to accomplish this course.
Planned Learning Activities and Teaching Methods
Lectures, Practical Courses, Presentation, Seminar, Project, Laboratory Applications (if necessary)
ECTS / Table Of Workload (Number of ECTS credits allocated)
Student workload surveys utilized to determine ECTS credits.
Activity :
Number Duration Total  
Course Duration (Excluding Exam Week) :
13 3 39  
Time Of Studying Out Of Class :
13 5 65  
Homeworks :
10 5 50  
Presentation :
5 1 5  
Project :
0 0 0  
Lab Study :
0 0 0  
Field Study :
0 0 0  
Visas :
1 10 10  
Finals :
1 10 10  
Workload Hour (30) :
30  
Total Work Charge / Hour :
179  
Course's ECTS Credit :
6      
Assessment Methods and Criteria
Studies During Halfterm :
Number Co-Effient
Visa :
1 50
Quiz :
0 0
Homework :
1 25
Attendance :
0 0
Application :
0 0
Lab :
0 0
Project :
0 0
Workshop :
0 0
Seminary :
0 0
Field study :
0 0
   
TOTAL :
75
The ratio of the term to success :
40
The ratio of final to success :
60
TOTAL :
100
Weekly Detailed Course Content
Week Topics  
1 Introduction to nuclear reactors
 
2 Heat production of nuclear reactors
 
3 Heat production of nuclear reactors
 
4 Heat analysing of nuclear reactors
 
5 Heat analysing of nuclear reactors
 
6 Heat production of fuel tools
 
7 Heat production of fuel tools
 
8 Pressure lose of pipe and channel
 
9 Pressure lose of pipe and channel
 
10 Heat distributor of reactor channels
 
11 Heat distributor of reactor channels
 
12 Cycles of reactor and fuel
 
13 Numerical analysing of heat transfer of nuclear reactors
 
14 Numerical analysing of heat transfer of nuclear reactors