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International School in Nuclear Engineering 2019

Released on Saturday 10 November 2018

International School in Nuclear Engineering 2019


The National Institute for Nuclear Science and Technology (INSTN) is organizing the International School in Nuclear Engineering, aiming at promoting knowledge in the field of reactor physics and engineering at a high education level.

The 2019 edition will offer 6 one-week advanced courses in reactor physics and nuclear engineering to be held in France (Cadarache, Marcoule, or Saclay) in January and February 2019.

The courses are designed for young researchers, PhD students, post-doctorates and engineers, already having a Master of Science in nuclear engineering as background. The courses will present the international state-of-the-art in the main topics of nuclear engineering:

   -  reactor core physics,
   -  thermal hydraulics,
   -  materials,
   -  fuels,
   -  fuel cycle,
   -  nuclear waste.


3 ECTS will be awarded for each successfully completed course (one week). Lecturers are internationally known experts mostly from CEA, the leading research organisation in France for nuclear energy.





For each course technical visits of CEA facilities are planned.


Reactor Core Physics: Deterministic and Monte Carlo Methods

(C. Diop, A. Santamarina)

  • Chain reaction and neutron balance
  • Neutron slowing-down and resonance absorption, self-shielding modelling
  • The neutron transport equation and calculation schemes: the steady-state integrodifferential transport equation.
  • The neutron diffusion equation… Verification & Validation of neutronics code package: process, sensitivity and uncertainty studies
  • The Monte Carlo method for solving the transport equation
  • Monte Carlo techniques: fixed source, variance reduction, criticality, perturbation calculations, adjoint calculation, applications to shielding


Thermal Hydraulics and Safety

(D. Bestion, J-M. Seiler, E. Studer)

  • Basic modelling of two-phase flow
  • Two-phase flow phenomena in LWRs
  • Multi-scale approach of LWR thermal hydraulics
  • System code modelling of reactor thermal hydraulics, including advanced modelling
  • Simulation of LWR design basis accidents
  • Application of two-phase CFD to reactor thermal hydraulic issues
  • Multiphase phenomena and modelling of severe accidents in LWRs
  • Hydrogen risk (production, dispersion, combustion, mitigation)


n Materials for Nuclear Reactors, Fuels and Structures

(J-L. Béchade, J-C. Brachet, F. Garrido)

  • Mechanisms of irradiation damage: neutrons, photons, electrons
  • Behaviour of materials under irradiation: ferritic steels for reactor pressure vessel, austenitic stainless steels for internals or fuel cladding (FBR), Zr alloys for fuel cladding and fuel assemblies (LWR)
  • Fuel materials (UO2, PuO2): irradiation-induced effects
  • Materials for high temperature conditions: SiC, ZrC, low swelling alloys
  • Materials for fusion: low activation materials, resistance to high-energy neutrons, breading blankets


Nuclear Fuels for Light Water Reactors and Fast Reactors

(D. Parrat, J. Noirot)

  • Nuclear fuels fundamentals
  • Fuel element thermal performance and temperature effects
  • Nuclear fuel behaviour under irradiation
  • Main limiting phenomena in the different types of fuels
  • Fuel behaviour during some off-normal conditions
  • Modelling of fuel behaviour
  • Fuel challenges for the future


Nuclear Fuel Cycle and Reprocessing

(Ch. Poinssot)

  • Fuel cycle and spent fuel
  • Fundamentals of fuel cycle: chemistry of actinides and fission products in solution
  • PUREX spent fuel processing: fundamental knowledge and industrial process
  • Minor actinide reprocessing
  • Advanced fuel cycles


Nuclear Waste Management

(B. Bonin)

• General considerations on nuclear waste

•Waste conditioning

•Waste storage and disposal


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