Master Recherche International EMINE - Semestre 5

Cursus ingénieur->Master RI EMINE->Semestre 5

Intitulés des modules/matières

ECTS

Volume horaire

Semestre 5 M2 RI EMINE 30.0 345.0

UE 1 Reactor concepts and materials 6.0 86.0
Fundamentals in materials science - 5PMUFMS4 1.0 26.0
- BLOC 12 Nuclear reactor coolants 1.0 10.0
- Liquid Metals Technology - 5PMULME4 0.5 6.0
  Liquid Metals Technology - 5PMULMT4 0.5 4.0
- BLOC 11 Reactor Design 2.0 22.0
- Gen IV - 5PMUGEN4 0.5 6.0
  Operations of nuclear reactors - 5PMUONR4 0.5 6.0
  Reactor Design - 5PMURED4 1.0 10.0

BLOC 13 Materials for reactors 2.0 28.0

Choice of materials - 5PMUCHM4	0.25	4.0
Description and Operation of NPP - 5PMUDON4	0.25	4.0
EDF activity on Materials and Structures - 5PMUEDF4	0.0	6.0
Materials selection - 5PMUMAS4	1.0	8.0
Materials used in nuclear reactor - 5PMUMNR4	0.5	6.0

- UE 2 Material ageing in nuclear environnement 6.0 102.0
- - BLOC 22 Corrosion and fracture mechanics 2.5 50.0
  - Fundamental of corrosion - 5PMUFCO4 1.0 18.0
    Fracture mechanics - 5PMUFME4 1.0 24.0
    Nuclear corrosion - 5PMUNCO4 0.5 8.0
- - BLOC 21 Materials under irradiation 3.5 52.0
  - Dislocations - 5PMUDIS3 1.0 16.0
    Irradiation ageing - 5PMUIRA4 1.0 12.0
    Irradiation defects - 5PMUIRD4 0.5 8.0
    Microstructure - 5PMUMIC4 1.0 16.0
- UE 3 Energy and Components EDF 6.0 83.0
- - BLOC 32 Energy 1.0 10.0
  - General approach to energy - 5PMUGAE4 1.0 10.0
- - BLOC 31 Components EDF 5.0 73.0
  - - BLOC 31a Chemistry and radioanalysis 0.0 8.0
    - Chemistry and radioanalysis - 5PMUCRD4 0.0 8.0
  - - BLOC 31b Civil works 0.0 8.0
    - Civil works - 5PMUCOMF 0.0 8.0
  - - BLOC 31c Corrosion and thermal effect 0.0 11.0
    - Corrosion in secondary circuit - 5PMUCOMH 0.0 1.0
      Thermal ageing - 5PMUCOMI 0.0 2.0
      Corrosion (Primary circuit) - 5PMUCOMJ 0.0 4.0
      Thermal fatigue - 5PMUCOMK 0.0 2.0
      Corrosion (Fundamentals) - 5PMUCOMP 0.0 2.0
  - - BLOC 31d Fuel 0.0 16.0
    - Fuel - 5PMUCOMG 0.0 16.0
  - - BLOC 31e Reactor pressure vessel and internals 0.0 16.0
    - Internals - 5PMUCOMC 0.0 4.0
      Welding and RPV - 5PMUCOMD 0.0 4.0
      Reactor Pressure vessel - 5PMUCOME 0.0 8.0
  - - BLOC 31f Non destructive testing 0.0 8.0
    - Non destructive examination - 5PMUCOMA 0.0 8.0
  - - BLOC 31g Polymers 0.0 4.0
    - Polymers - 5PMUCOMB 0.0 4.0
  - - BLOC 31h Maintenance, ageing and fuel 0.0 2.0
    - Maintenance_ageing and fuel reprocessing - 5PMUCOML 0.0 2.0
  - - BLOC 31i Visit and evaluation 0.0 0.0
    - Visit - 5PMUCOMM 0.0 0.0
      Evaluation of formation and Closure - 5PMUCOMO 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 - 5PMUNUCC 0.0 18.0
- - BLOC 44 Nuclear fuel cycle 0.0 16.0
  - Fuel cycle - 5PMUNUCJ 0.0 13.0
    Scenarios - 5PMUNUCK 0.0 3.0
- - BLOC 41 Nuclear fuel design 0.0 15.0
  - Design methodology - 5PMUNUCA 0.0 3.0
    Introduction to design - 5PMUNUCB 0.0 3.0
    Fuel element design - 5PMUNUCF 0.0 9.0
- - BLOC 43 Nuclear fuels behaviour under 0.0 25.0
  - Film - 5PMUNUCD 0.0 1.0
    Irradiation effect - 5PMUNUCE 0.0 12.0
    Fission gas - 5PMUNUCG 0.0 5.0
    Off normal - 5PMUNUCH 0.0 2.0
    Fuel modelling - 5PMUNUCI 0.0 5.0
- - BLOC 45 Visit and evaluation 0.0 0.0
  - Evaluation - 5PMUNUCL 0.0 0.0
    Visit - 5PMUNUCM 0.0 0.0

Mise à jour - 28/08/2014

English version

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Liquid Metals Technology - 5PMULME4	0.5	6.0
Liquid Metals Technology - 5PMULMT4	0.5	4.0

Gen IV - 5PMUGEN4	0.5	6.0
Operations of nuclear reactors - 5PMUONR4	0.5	6.0
Reactor Design - 5PMURED4	1.0	10.0

Fundamental of corrosion - 5PMUFCO4	1.0	18.0
Fracture mechanics - 5PMUFME4	1.0	24.0
Nuclear corrosion - 5PMUNCO4	0.5	8.0

Dislocations - 5PMUDIS3	1.0	16.0
Irradiation ageing - 5PMUIRA4	1.0	12.0
Irradiation defects - 5PMUIRD4	0.5	8.0
Microstructure - 5PMUMIC4	1.0	16.0

Corrosion in secondary circuit - 5PMUCOMH	0.0	1.0
Thermal ageing - 5PMUCOMI	0.0	2.0
Corrosion (Primary circuit) - 5PMUCOMJ	0.0	4.0
Thermal fatigue - 5PMUCOMK	0.0	2.0
Corrosion (Fundamentals) - 5PMUCOMP	0.0	2.0

Internals - 5PMUCOMC	0.0	4.0
Welding and RPV - 5PMUCOMD	0.0	4.0
Reactor Pressure vessel - 5PMUCOME	0.0	8.0

Visit - 5PMUCOMM	0.0	0.0
Evaluation of formation and Closure - 5PMUCOMO	0.0	0.0

Design methodology - 5PMUNUCA	0.0	3.0
Introduction to design - 5PMUNUCB	0.0	3.0
Fuel element design - 5PMUNUCF	0.0	9.0

Film - 5PMUNUCD	0.0	1.0
Irradiation effect - 5PMUNUCE	0.0	12.0
Fission gas - 5PMUNUCG	0.0	5.0
Off normal - 5PMUNUCH	0.0	2.0
Fuel modelling - 5PMUNUCI	0.0	5.0