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Neutronics - 4PMGNEU1

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  • Number of hours

    • Lectures : 22.0
    • Tutorials : 12.0
    • Laboratory works : 0
    • Projects : 0
    • Internship : 0
    ECTS : 2.5

Goals

To learn how to use wisely the neutron diffusion approximation and how to modelize as simply as possible a nuclear reactor core for quick and easy neutronic calculations.
To prepare for more powerful tools like deterministic or stochastic transport codes.

Contact Alexis NUTTIN

Content

Diffusion approximation
Slowing-down of neutrons
Criticality : condition and flux calculation
Refinements : heterogeneous, multigroup

In parallel with this lecture, the program "Neutronique en Clips" (see specific page in same semester) allows to acquire this fundamental knowledge by application on a practical case (conference article).



Prerequisites

Basic tools in mathematics and notions in nuclear physics
Introduction to nuclear reactor physics

Tests

exam (2h) with a problem in 2 or 3 parts



N1 = 100% DS1
N2 = 100% DS2

Additional Information

Curriculum->Engineering degree->Semester 8

Bibliography

Lamarsh, Introduction to Nuclear Reactor Theory (1972)
Barjon, Physique des Réacteurs Nucléaires (1992)
La Neutronique, Monographie du CEA (2012)

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Date of update March 13, 2019

Université Grenoble Alpes