Phelma Formation 2022

5PMGSND0: Stochastic neutron simulati(GEN-S5) - 5PMXSND0

  • Number of hours

    • Lectures 8.0
    • Laboratory works 8.0

    ECTS

    ECTS 1.0

Goal(s)

Introduction to one numerical method used in deterministic neutron transport codes : collision probabilities.

Understanding the industrial neutron calculation scheme.

Getting experience with the practical use of a deterministic neutron transport code for simplified reactor physics calculations.

Calculation of temperature coefficients, homogeneisation, fuel burn up calculations.

Contact Adrien BIDAUD, Tanguy COURAU

Content(s)

Neutron Transport theory :
From transport to diffusion equation : assumptions and approximations.
Example of a transport solution method : Collision Probabilities.
Preparing diffusion cross section : energy condensation, flux-volume homogeneisation, transport-diffusion equivalence.
Fuel burn-up calculation.
Fuel management
Industrial calculation scheme



Prerequisites
  • Reactor physicis : criticality, temperature feedbacks, fuel management
  • Neutronics : slowing-down equation, resonance self-shielding, transport equation, diffusion model
  • Numerical methods : PDEs, numerical quadrature methods, solving numerically linear systems.

Test

Exercice session evaluation (3*10%)

Simulation project : Fuel burn-up of simple fuel cells (70%)



note = 30%TD + 70%projet

Additional Information

Course list
Curriculum->Master-Recherche->Semester 5
Curriculum->FD2MEP->Semester 5

Bibliography

DRAGON User Manual : TECHNICAL REPORT IGE–174 Rev. 12 (Release 3.06L)
"La Neutronique", Monographies CEA/DEN, 2013, ISBN 978-2-281-11371-6
Applied Reactor Physics, Alain Hebert, Presses internationales Polytechnique, 2009