Filière Semestre à choix : EMINE - Semestre 5

Cursus ingénieur->FSC-EMI->Semestre 5

Intitulés des modules/matières

ECTS

Volume horaire

Semestre 5 SC EMINE 30.0 393.0

UE 1 Reactor concepts and materials 6.0 104.0
Fundamentals in materials science - WPMUFMS4 1.0 26.0
- BLOC 12 Nuclear reactor coolants 1.0 10.0
- Liquid Metals Technology - WPMULME4 0.5 6.0
  Liquid Metals Technology - WPMULMT4 0.5 4.0
- BLOC 11 Reactor Design 2.0 22.0
- Gen IV - WPMUGEN4 0.5 6.0
  Operations of nuclear reactors - WPMUONR4 0.5 6.0
  Reactor Design - WPMURED4 1.0 10.0

BLOC 13 Materials for reactors 2.0 46.0

Choice of materials - WPMUCHM4	0.25	4.0
Welding and RPV - WPMUCOMD	0.0	4.0
Reactor Pressure vessel - WPMUCOME	0.0	4.0
Description and Operation of NPP - WPMUDON4	0.25	8.0
EDF activity on Materials and Structures - WPMUEDF4	0.0	4.0
Materials selection - WPMUMAS4	1.0	16.0
Materials used in nuclear reactor - WPMUMNR4	0.5	6.0

- UE 2 Material ageing in nuclear environnement 6.0 114.0
- - BLOC 22 Corrosion and fracture mechanics 2.5 62.0
  - Fundamental of corrosion - WPMUFCO4 1.0 24.0
    Fracture mechanics - WPMUFME4 1.0 30.0
    Nuclear corrosion - WPMUNCO4 0.5 8.0
- - BLOC 21 Materials under irradiation 3.5 52.0
  - Dislocations - WPMUDIS3 1.0 16.0
    Irradiation ageing - WPMUIRA4 1.0 12.0
    Irradiation defects - WPMUIRD4 0.5 8.0
    Microstructure - WPMUMIC4 1.0 16.0
- UE 3 Components EDF + Energy issues 6.0 101.0
- - BLOC 32 Energy issues 2.0 40.0
  - General approach to energy - WPMUGAE4 2.0 40.0
- - BLOC 31 Components EDF 4.0 61.0
  - - BLOC 31a Chemistry and radioanalysis 0.0 8.0
    - Chemistry and radioanalysis - WPMUCRD4 0.0 8.0
  - - BLOC 31b Civil works 0.0 8.0
    - Civil works - WPMUCOMF 0.0 8.0
  - - BLOC 31c Corrosion and thermal effect 0.0 11.0
    - Corrosion in secondary circuit - WPMUCOMH 0.0 1.0
      Thermal ageing - WPMUCOMI 0.0 2.0
      Corrosion (Primary circuit) - WPMUCOMJ 0.0 4.0
      Thermal fatigue - WPMUCOMK 0.0 2.0
      Corrosion (Fundamentals) - WPMUCOMP 0.0 2.0
  - - BLOC 31d Fuel_cladding 0.0 16.0
    - Fuel_cladding - WPMUCOMG 0.0 16.0
  - - BLOC 31e Reactor pressure vessel and internals 0.0 4.0
    - Internals - WPMUCOMC 0.0 4.0
  - - BLOC 31f Non destructive testing 0.0 8.0
    - Non destructive examination - WPMUCOMA 0.0 8.0
  - - BLOC 31g Polymers 0.0 4.0
    - Polymers - WPMUCOMB 0.0 4.0
  - - BLOC 31h Maintenance, ageing and fuel 0.0 2.0
    - Maintenance_ageing and fuel reprocessing - WPMUCOML 0.0 2.0
  - - BLOC 31i Visit and evaluation 0.0 0.0
    - Visit - WPMUCOMM 0.0 0.0
      Evaluation of formation and Closure - WPMUCOMO 0.0 0.0
- UE 4 Nuclear fuels CEA 6.0 74.0
- - BLOC 42 Nuclear fuel fabrication 0.0 18.0
  - Fuel fabrication and characterisation - WPMUNUCC 0.0 18.0
- - BLOC 44 Nuclear fuel cycle 0.0 16.0
  - Fuel cycle - WPMUNUCJ 0.0 13.0
    Scenarios - WPMUNUCK 0.0 3.0
- - BLOC 41 Nuclear fuel design 0.0 15.0
  - Design methodology - WPMUNUCA 0.0 3.0
    Introduction to design - WPMUNUCB 0.0 3.0
    Fuel element design - WPMUNUCF 0.0 9.0
- - BLOC 43 Nuclear fuels behaviour under irradiation 0.0 25.0
  - Film - WPMUNUCD 0.0 1.0
    Irradiation effect - WPMUNUCE 0.0 12.0
    Fission gas - WPMUNUCG 0.0 5.0
    Off normal - WPMUNUCH 0.0 2.0
    Fuel modelling - WPMUNUCI 0.0 5.0
- - BLOC 45 Visit and evaluation 0.0 0.0
  - Evaluation - WPMUNUCL 0.0 0.0
    Visit - WPMUNUCM 0.0 0.0

Mise à jour - 11/01/2017

English version

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Liquid Metals Technology - WPMULME4	0.5	6.0
Liquid Metals Technology - WPMULMT4	0.5	4.0

Gen IV - WPMUGEN4	0.5	6.0
Operations of nuclear reactors - WPMUONR4	0.5	6.0
Reactor Design - WPMURED4	1.0	10.0

Fundamental of corrosion - WPMUFCO4	1.0	24.0
Fracture mechanics - WPMUFME4	1.0	30.0
Nuclear corrosion - WPMUNCO4	0.5	8.0

Dislocations - WPMUDIS3	1.0	16.0
Irradiation ageing - WPMUIRA4	1.0	12.0
Irradiation defects - WPMUIRD4	0.5	8.0
Microstructure - WPMUMIC4	1.0	16.0

Corrosion in secondary circuit - WPMUCOMH	0.0	1.0
Thermal ageing - WPMUCOMI	0.0	2.0
Corrosion (Primary circuit) - WPMUCOMJ	0.0	4.0
Thermal fatigue - WPMUCOMK	0.0	2.0
Corrosion (Fundamentals) - WPMUCOMP	0.0	2.0

Visit - WPMUCOMM	0.0	0.0
Evaluation of formation and Closure - WPMUCOMO	0.0	0.0

Design methodology - WPMUNUCA	0.0	3.0
Introduction to design - WPMUNUCB	0.0	3.0
Fuel element design - WPMUNUCF	0.0	9.0

Film - WPMUNUCD	0.0	1.0
Irradiation effect - WPMUNUCE	0.0	12.0
Fission gas - WPMUNUCG	0.0	5.0
Off normal - WPMUNUCH	0.0	2.0
Fuel modelling - WPMUNUCI	0.0	5.0