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5PMGSNS0 : Monte Carlo methods for neutron transport - WPMEDNS9

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  • Number of hours

    • Lectures : 10.0
    • Tutorials : 10.0
    • Laboratory works : 0
    • Projects : 0
    • Internship : 0
    • Written tests : 0
    ECTS : 1.5

Goals

Get some first expertise in using a Monte Carlo code for simulation of neutron transport, to be used in typical nuclear reactor core studies

Contact Alexis NUTTIN

Content

Classes in october and november, in 4 big chapters :
Chapter 1 : getting familiar with the code
Chapter 2 : criticality calculations
Chapter 3 : calculation of fluxes and reaction rates
Chapter 4 : from cell calculations to full core calculations (and beyond)
Will be completed by a seminar given by an industrial (former student) on radioprotection calculations



Prerequisites

Basic neutronics
Basic knowledge of Linux

Tests

Exam on paper, checking acquisition of basic techniques (such as geometry definition, simple modelization of a system, definition of tallies and exploitation of results)



N1 = Note finale session 1 = 100% DS1
N2 = Note finale session 2 = 100% DS2

Additional Information

This course brings 1.0 ECTS to students in UE Simulations JUAS

This course brings 2.0 ECTS to students in TU Simulations

Semester 9 - This course may be followed in french or in english  
Curriculum->Double-Diploma Engineer/Master->Semester 9
Curriculum->Master->Semester 9

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Date of update March 18, 2019

Université Grenoble Alpes