Phelma Formation 2022

5PMGSND0 : Deterministic methods for neutron transport - WPMEDND9

  • Number of hours

    • Lectures 8.0
    • Projects 0
    • Tutorials 8.0
    • Internship 0
    • Laboratory works 0
    • Written tests 0

    ECTS

    ECTS 2.0

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

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

TD = Exercice session evaluation (3*10%)

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



Présentiel ou distanciel =
Contrôle continu : 3*10% non rattrapable
Projet = 70% rattrapable

Additional Information

This course brings 1.0 ECTS to students in UE Simulations JUAS

This course brings 1.0 ECTS to students in UE Common core

This course brings 2.0 ECTS to students in TU Simulations

This course brings 1.0 ECTS to students in UE Common core JUAS/ESIPAP (DD-S9)

Course list
Curriculum->Double-Diploma Engineer/Master->Semester 9
Curriculum->Master->Semester 9

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