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Materials for nuclear reactors, fuels and structures - International school in nuclear engineering

1.1.4 Matériaux pour le nucléaire

Fundamentals

Materials

Materials for nuclear

Nuclear reactor

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© CEA

In summary

The ISNE international training course aims at promoting knowledge in the field of nuclear sciences. This module is dedicated to materials behavior in nuclear reactors.

Who should take this course ?

The doctoral course is designed for young researchers, PhD students, post-doctorates and engineers from nuclear industry companies, research centres, Universities, Technical Safety Organizations (TSO), regulatory bodies.

Learning outcomes

• Describe the mechanisms of irradiation damage.
• Identify the available techniques to investigate the evolution of materials under irradiation.
• Compare the properties of steels used for reactor core structures;
• Explain the evolution of fuel and cladding during operation.

Technical visit organized (if possible, depending on the availability of the experimental facilities)

- Mechanisms of irradiation damage.
- Introduction to fuel materials.
- Behaviour of in core metallic materials:
• Steels for LWR, FBR and fusion,
• Zr alloys for Fuel Assembly in LWR.
- Carbides, SiC and ZrC high temperature materials for GenIV reactors.

Minimum background: Master of Science in Nuclear Engineering or Materials Science.

self-assessment

Teaching method and tools

On-site visit

Collaboration

  • Logo CEA original

Contact(s)

Program manager :

Servane COSTE-LECONTE
servane.coste-leconte@cea.fr
+33 1 69 08 33 89

training sessions

No training session is scheduled for the moment, if this training interests you, please contact us.

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