Nuclear fuel cycle

Cycle du combustible

REP

Cycle du combustible

Réacteurs nucléaires

4.7

Recommandation: 95 %

Note moyenne de satisfaction des participants

Pourcentage de recommandation

En bref

NFC is an OUTSTANDING Course and UNIQUE experience to discover the step-by-step process of the Nuclear Fuel Cycle.

The scientific content relies on renowned experts who explain in details each step of the nuclear fuel cycle. It is completed by a series of amazing nuclear site visits that France can offer on its territory. Those visits give the opportunity for an exposure to the industrial applications and various aspects of operational safety.

The course takes advantage of the INSTN collaboration with CEA, Orano, Framatome and ANDRA.

A qui s’adresse cette formation ?

Technicians, scientists and engineers working in the nuclear field and interested in obtaining advanced knowledge in the nuclear fuel cycle.

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Ref :

087

Durée :

10j

- 51h

Formation :

Prix :

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Compétences visées

Identify and describe the various front-end processes needed for the Uranium to be used in the core of the Pressurized Water Reactors in France: mining, milling, conversion, enrichment and fuel fabrication
Explain how France manages the nuclear spent fuel: reprocessing and recycling
Explain how France manages the nuclear waste: storage and disposal

Technical visits (subject to acceptance, but most of them are insured):

Conversion sites: Orano Malvési and Philippe Coste (Orano)
Enrichment sites: GB and GB II (Orano)
Fuel fabrication site: FBFC (Framatome)
La Hague: vitrification, pools, UP3 unit
MELOX site (Orano)
ANDRA: geological disposal and on surface disposal site

Nuclear Fuel Cycle: Overview
Geology of Uranium: Exploration, mining and Resources
Uranium Enrichment
Boiler/Fuel: the constraints
Fuel Assembly: General Design
Activity, History and Public Acceptance Issues
The Front-End of the Fuel Cycle: Markets and Economic
Interim Storage of Spent Fuel and HLW-Current State of the Art Technology
Options for Spent Fuel Management
The Recycling of Reprocessed Uranium
Recycling Operations and Technology
Transport of Nuclear Fuel Cycle Materials

Basic concepts of chemistry (solutions, solvents, etc…) and separative chemistry
Basic concepts of nuclear physics: fission reaction, Radioactivity, law of radioactive decay and
radiological properties of U and Pu
Basic concepts of the design and functionning of the pressurized water reactor core
Basic concepts of radiological protection and nuclear criticality safety

Self evaluation