Number of hours
- Lectures 8.0
- Projects 0
- Tutorials 8.0
- Internship 0
- Laboratory works 0
- Written tests 0
ECTS
ECTS 1.5
Goal(s)
Understand numerical method used in deterministic neutron transport codes : collision probabilities.
Understand the industrial neutron calculation scheme.
Experience the practical use of a deterministic neutron transport code for simplified reactor physics calculations.
Calculate temperature coefficients, homogeneisation, in static or in depletion calculations.
Contact Tanguy COURAU, Pamela LOPEZ, Nicolas CAPELLAN, Olivier DOCHEContent(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
Controle continu = Exercice session evaluation (3*10%)
No catch up exam for that part
Written report project = Simulation project : Fuel burn-up of simple fuel cells (70%)
Redo exam would be another written report project.
Project: 70% + Contrôle Continu : 3*10%
Additional Information
This course brings 2.0 ECTS to students in TU Simulations
This course brings 1.0 ECTS to students in UE Simulations JUAS
Course list
Curriculum->Double-Diploma Engineer/Master->Semester 9
Curriculum->Physics and Nuclear Engineering->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