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Syllabus for

Academic year
FRE051 - Nuclear engineering
 
Owner: TTFYA
5,0 Credits (ECTS 7,5)
Grading: TH - Five, Four, Three, Not passed
Level: C
Department: 16 - PHYSICS


Teaching language: English
Minimum participants: 3
Maximum participants: 35

Course module   Credit distribution   Examination dates
Sp1 Sp2 Sp3 Sp4 No Sp
0102 Examination 5,0 c Grading: TH   5,0 c   Contact examiner

In programs

TTFYA ENGINEERING PHYSICS, Year 4 (elective)

Examiner:

Professor  Imre Pázsit



Eligibility:

For single subject courses within Chalmers programmes the same eligibility requirements apply, as to the programme(s) that the course is part of.

Course specific prerequisites

Basic courses in physics and mathematics

Aim

Nuclear Engineering is a cross-disciplinary subject which covers different disciplines ranging from neutron physics to thermal hydraulics, material science and chemistry.
The aim of the course is to give basic knowledge mainly in reactor physics and thermal hydraulics (heat transfer + single- and two-phase flow). These make up the mainstay for reactor construction, whereby thermal hydraulics is also important in other engineering disciplines.

Content

AIM OF THE COURSE

Nuclear Engineering is a cross-technical subject which covers different disciplines ranging from neutron physics to thermal hydraulics, material science and chemistry.

The aim of the course is to give basic knowledge mainly in reactor physics and thermal hydraulics (heat transfer + single- and two-phase flow). These make up the mainstay för reactor construction where thermal hydraulics is also important in other engineering disciplines.

CONTENTS AND ORGANISATION

In the first part of the course, the global energy situation will be briefly reviewed together with the distribution of energy production between conventional and nuclear power. An overview of the whole process with energy production in a nuclear power plant will be given where the fuel cycle from mill to final disposal of waste is described. Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs) which are the most common reactor types in the world will be described in general as well as their components.

In the second part, an introduction to reactor physics will be given. This includes the energy release from fission, cross-sections, criticality, reactivity, reactor statics and time-dependent states together with the basis to space-dependent diffusion theory in 1- and 2-energy groups. Furthermore, the effect of poisoning and depletion (burnup) as well as reactor dynamics which integrates the neutronics with the thermalhydraulics will be discussed.

In the third part, the importance of thermal hydraulics in reactors during both steady-state and transient plant conditions will be outlined. This includes heat conduction and convection, single- and two-phase flows, the concepts of heat flux and heat transfer coefficient, boiling, empirical correlations, flow regimes, critical heat flux, dryout, etc. Finally, a short description of safety principles and safety systems as well as computer programs for thermohyraulic transient analysis is given.

Organisation

Lectures, 6 hrs/week.
Calculational exercises, 2 hrs/week.

LABORATORY EXERCISE:
Core Calculation with the advanced codes CASMO and SIMULATE is demonstrated.

Study trip to Ringhals

Literature

Lectures on Nuclear Engineering, Lecture notes by M. Analytis, printed at the Department.

Examination

Written exam.


Page manager Published: Mon 28 Nov 2016.