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Nuclear fuel - 5PMGCBN1

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  • Number of hours

    • Lectures : 10.0
    • Tutorials : 10.0
    • Laboratory works : 0
    • Projects : 0
    • Internship : 0
    ECTS : 1.5

Goals

The course provides an up-to-date overview of the different technological aspects associated to the design, fabrication and operation of the PWR 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 LMR (sodium). 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.

Contact Pablo RUBIOLO

Content

1) Overview of reactors and fuel designs
2) PWR fuel assembly design
3) Nuclear fuel materials
4) Fuel rod design
5) Fuel assembly mechanical design
6) Fuel assembly thermal-hydraulics design
7) Neutronics design
8) Fuel cycle and nuclear wastes



Prerequisites

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

Tests

Semester 9 - The exam is given in english only 

The students are evaluated on a project report and a 1-hour written exam. All documents are forbidden at the written exam. The final score is 50% based on the project report and 50% based on one hour written exam without documents.



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

Semester 9 - This course is given in english only EN

Curriculum->Engineering degree->Semester 9
Curriculum->Double-Diploma Engineer/Master->Semester 9

Bibliography

  • « 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.
  • “Thermal analysis of Pressurized Water Reactors”, L.S. Tong, J Weisman, American Nuclear Society, 1996.
  • “Thermal Analysis of Liquid Metal Fast Breeder Reactors”, Y.S. Tang, R.D. Coffield, Jr. R.A. Markley, American Nuclear Society, 1978.
  • “Nuclear Reactor Engineering”, S. Glasstone and A. Sesonske, 1994.

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Date of update March 13, 2019

Université Grenoble Alpes