Phelma Formation 2022

Nuclear fuel - 5PMGCBN1

  • Number of hours

    • Lectures 10.0
    • Projects 0
    • Tutorials 10.0
    • Internship 0
    • Laboratory works 0

    ECTS

    ECTS 1.5

Goal(s)

The course provides an up-to-date overview of the different technological aspects associated to the design, fabrication and operation of the PWR (Pressurized Water Reactor) nuclear fuel. The introduction is devoted to present the major existing reactor designs and fuel technologies. The course then focalizes on the fuel assemblies of PWR and on a lesser degree SFR (sodium Fast Reactor). The final objective is to provide a global vision of fuel design with particular emphasis on the relationships between the various physical phenomena that affect the fuel assemblies. This course is taught in English.

Contact Nicolas CAPELLAN, Pablo RUBIOLO, Olivier DOCHE

Content(s)

Chapter 1 - Overview of reactors and fuel designs
Chapter 2 -PWR fuel assembly design
Chapter 3- Nuclear fuel materials (PWR and SFR)
Chapter 4 - Fuel rod design (PWR)
Chapter 5 - Fuel assembly mechanical design (PWR)
Chapter 6 - Fuel assembly thermal-hydraulics design (PWR)
Chapter 7 - Neutronics design (PWR)



Prerequisites

• Nuclear materials
• Nuclear reactor technology
• Introduction to reactor physics
• Single phase Thermal hydraulics
• Solid and fluid mechanics

Test

Semester 9 - The exam is given in english only 

The students are evaluated on a 2-hour written exam. All documents are forbidden at the written exam. The exams will have two parts: multiple choice questions and questions to be developed. One of the questions to be developed will be based on the conclusions of the student from the lecture of research papers provided during the course.



Contrôle continu : CC
Examen écrit Session1 : DS1
Examen écrit Session 2 : DS2
N1 = Note finale session 1
N2 = Note finale session 2

En présentiel :
N1 = % max(TdE, CC) + % DS1
N2 = % max(TdE, CC) + % DS2

En distanciel :
N1 =
N2 =

Commentaire :

Additional Information

This course brings 3.0 ECTS to students in UE Energy JUAS-ESIPAP

Semester 9 - This course is given in english only EN
Course list
Curriculum->Double-Diploma Engineer/Master->Semester 9
Curriculum->Physics and Nuclear Engineering->Semester 9

Bibliography

[1] « Le Combustible Nucléaire des Réacteurs a Eau sous Pression et des Réacteurs a Neutron Rapides: Conception et Comportement », H Bailly, D. Ménessier, C. Prunier, Eyrolles, 1996.
[2] « RCC-C: Règles de conception et de construction applicables aux assemblages de combustible des centrales nucléaires REP », Association Française pour les règles de conception et de construction des matériel des chaudières électro-nucléaires (AFCEN), 1995.
[3] « Examen des critères techniques de sûreté du combustible nucléaire », OECD 2001.
[4] « Thermal analysis of Pressurized Water Reactors », L.S. Tong, J Weisman, American Nuclear Society, 1996.
[5] « Thermal Analysis of Liquid Metal Fast Breeder Reactors », Y.S. Tang, R.D. Coffield, Jr. R.A. Markley, American Nuclear Society, 1978.
[6] « Nuclear Reactor Engineering », S. Glasstone and A. Sesonske, 1994.
[7] « Nuclear Heat Transport », M.M. El-Wakil, 1971.