Description of Individual Course Units
Course Unit CodeCourse Unit TitleType of Course UnitYear of StudySemesterNumber of ECTS Credits
9105046222003Quality Assurance and Quality Control in Nuclear Fuel Fabrication IIElective128
Level of Course Unit
Third Cycle
Objectives of the Course
The aim of the course is to provide to the students; to comprehend the basic processes of Nuclear Fuel Fabrication, to assimilate the purpose and the frequency of the quality control in the process steps, to apply the quality control methods, evaluation of data and to gain knowledge and experience on quality assurance and quality control methods and techniques at Nuclear Fuel Fabrication.
Name of Lecturer(s)
Prof.Dr. Hüseyin TEL, Prof.Dr. Yüksel ALTAŞ
Learning Outcomes
1Being able to comprehend the importance of Quality Assurance in Nuclear Fuel Fabrication.
2To gain experience and knowledge on production, quality control and quality assurance relations in Nuclear Fuel Fabrication installations.
3Being able to assimilate the effect of sintering mecanism on pellet.
4Being able to predict sintering conditions to obtain easily sinterable, homogenous and with high density, good uranium dioxide pellets.
5Being able to determine crystal structure and to calculate crystallite size of uranium dioxide powders.
6Being able to apply statistical methods to evaluate quality control data.
7Being able to compare natural and enriched uranium dioxide production processes.
Mode of Delivery
Face to Face
Prerequisites and co-requisities
Recommended Optional Programme Components
Course Contents
Comparison of natural and enriched uranium dioxide production processes, sintering, sintering mecanisms, crystal structure of uranium dioxide, statistical methods in Quality Control, Quality Assurance, Quality Assurance Programme and applications.
Weekly Detailed Course Contents
1Presentation of the course, its content, book and suggested litterature.Representation of Laboratories
2Nuclear Fuel Cycle and and the place of Nuclear Fuel Fabrication in the cycle.Literature review (identifying research topics for paper presentation )
3Comparison of Metallic uranium, uranium oxide and uranium carbide fuels in view of density, thermal resistivity, thermal conductivity, radiation and corrosion resistivity.Laboratory study
4The role of cladding material and required properties to possess, comparison of cladding materials in view of mechanical properties, thermal resistivity and cross section.Laboratory study
5Comparison of cladding material used for PWR(Pressurized Water Reactor), BWR (Boiling Water Reactor) and PHWR (Pressurized Heavy Water Reactor).Laboratory study
6The properties of the components of nuclear fuel assembly.Laboratory study
7The factors influencing uranium dioxide powder properties, the powder properties required for uranium dioxide and quality control methods of powders.Paper presentation
8Mid-term Exam
9The importance of bulk density, tab density, flowablity, particle size distribution, average of particle size, specific surface area and porosity for suitable powder properties.Paper presentation
10Pellet production, use of binder and lubricant, additives and effect of pre-compaction, relation of green pellet density with powder properties and compaction pressure. Laboratory study
11Theoretical density, real density, open and closed porosity. Laboratory study
12O/M ratio, thermogravimetric method, titrimetric method.Laboratory study
13Limits of impruties and influences on fuel.Laboratory study
14The presentation of the semester project.The presentation of the semester project.
15The presentation of the semester project.The presentation of the semester project.
16Final Exam
Recommended or Required Reading
Course Book(s): 1. Vollath. D., Kummerer K., Characterization and Quality Control of Nuclear Fuels, North Holland Publishing Company, Amsterdam,1982. 2. Quality Assurance and Quality Control in Nuclear Fuel Fabrication I-II Course Notes(in Turkish), Prof. Dr. Hüseyin TEL, Prof. Dr. Yüksel ALTAŞ, Ege University, Institute of Nuclear Sciences, Nuclear Technology Division, 2007. Helper Book(s): 1. Vollath. D., Practical Experience in the Application of Quality Control in Water-Reactor Fuel Fabrication, GmbH, Karlsruhe, KfK 3777, 1984. 2. AIEA, L'Assurance De La Qualité Pour La Sureté Des Centrales Nucléaires Et Autres Installatıons Nucléaires, Collection Sécurité N° 50-C/Sg-Q, Vıenne, 1999
Planned Learning Activities and Teaching Methods
Activities are given in detail in the section of "Assessment Methods and Criteria" and "Workload Calculation"
Assessment Methods and Criteria
Term (or Year) Learning ActivitiesQuantityWeight
End Of Term (or Year) Learning ActivitiesQuantityWeight
Language of Instruction
Work Placement(s)
Workload Calculation
ActivitiesNumberTime (hours)Total Work Load (hours)
Midterm Examination122
Final Examination122
Attending Lectures14228
Report Preparation14228
Project Preparation13030
Project Presentation122
Criticising Paper11616
Self Study14342
Individual Study for Mid term Examination12020
Individual Study for Final Examination13030
Contribution of Learning Outcomes to Programme Outcomes
LO15 55  4  5 
LO25  5  5    
LO354       5 
LO45  5  554  
LO55  5  55   
LO6  5  55  5 
LO7 45 45    5
* Contribution Level : 1 Very low 2 Low 3 Medium 4 High 5 Very High
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