Overordnede kursusmål
The course aims at developing the skills required for the design
and analysis of nuclear reactors, addressing key questions. How to
set-up a neutronics model of a nuclear reactor to perform a simple
analysis both in steady-state and in depletion? How to extract data
like neutron energy spectrum and neutron flux? What can be the
impact of nuclear data libraries on obtained results? In the
course, you will learn how to find answers to these questions by
guided hands-on work centered on Monte-Carlo simulations of a
simplified nuclear reactor design of the Molten Salt Fast Reactor.
Monte-Carlo simulations are not only used for nuclear reactor
analysis but also for all kind of radiation transport calculations
including applications in neutronics design, radiation protection,
fusion energy, nuclear medicine, dosimetry, detectors. This course
will give you basic knowledge that can be applied in other
contexts.
Læringsmål
En studerende, der fuldt ud har opfyldt kursets mål, vil kunne:
- Forklare Saltsmelte Reaktor princip og design.
- Forklare og anvend fundamentale neutronik koncepter.
- Forklare princippet bag Monte-Carlo burnup beregninger.
- Udvikle og anvende simplificerede Monte-Carlo neutronik
modeller baseret på litteratur data.
- Uddrage resultater opnået i Monte-Carlo simuleringer, især,
forklare og analysere neutronenergi spektra, neutronfluks
fordeling, reaktivitet og brændselsindhold som funktion af
burnup.
- Analysere og validere resultater med information fra den
videnskabelige litteratur.
- Analysere indflydelsen af valget af nuklear data bibliotek på
simulerings resultater.
- Designe en poster til et videnskabelig forum.
Kursusindhold
Based on the theory presented in 10411 , this learn-by-doing course
will allow you to perform a basic neutronics analysis of a nuclear
reactor. The general teaching format consists of a three-step loop:
1) Briefing in plenum with introductory concepts and instructions
2) Hands-on work in groups (model setup, simulations, data analysis
and comparison with available literature
3) Feedback on preliminary poster submission to prepare the final
poster submission.
In the first week, you will be introduced to the chosen reactor
design and learn about its characteristic properties. Based on
provided literature, you will set-up the Monte-Carlo modelling to
perform a basic neutronics analysis and perform first sanity
checks.
In the second week, you will perform simulations in order to obtain
the neutron energy spectrum, the neutron flux shape and the fuel
inventory as a function of burnup. At each step of the analysis,
you will compare your results with literature and with the
underlying reactor physics theory. Each group will make a
scientific-style poster based on their results taking inspiration
from examples provided. In the third week, you will mainly work on
completing the analysis and preparing the poster. Comments will be
provided on a preliminary version of the poster.
Litteraturhenvisninger
Custom compendium provided by the teacher.
Bemærkninger
A laptop is required to access the cluster on which the Monte-Carlo
simulations will be run.
Sidst opdateret
02. maj, 2025
