Nuclear Reactor Physics

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Code Completion Credits Range Language
17FARE Z,ZK 4 2P+2C Czech
Filip Fejt (guarantor), Jan Frýbort (guarantor), Lenka Frýbortová (guarantor)
Filip Fejt (guarantor), Jan Frýbort (guarantor), Lenka Frýbortová (guarantor)
Department of Nuclear Reactors

The subject “Nuclear reactor physics” builds on previously gained knowledge from fundamentals of reactor physics, kinetics, dynamics, thermohydraulics, and thermomechanics. The lectures start with transport theory introduction, trans-port equation formulation, and its utilization in reactor physics. The transport theory requires broad range of nuclear data. The students will learn how continuous and group-wise nuclear data are prepared and how the self-shielding effect is respected in heterogeneous reactors. A special chapter is utilization of perturbation theory. The importance of the adjoint flux for uncertainty and sensitivity calculations in reactor physics will be explained. The final part of lectures is devoted to coupled calculations of neutronics, termohydraulics, and thermomachanics in nuclear reactors.

Syllabus of lectures:

1.Transport theory in reactor physics (3 lectures): definition of transport theory requirements and its development, utili-zation of transport theory in reactor physics, methods for numerical solutions, simplification to diffusion theory,

2.Nuclear data for reactor physics (3 lectures): nuclear data required in reactor physics, sources of nuclear data, evalua-tion and validation of nuclear data, specific features of continuous and group-wise nuclear data,

3.Self-shielding effect and its importance in reactor physics (2 lectures): importance of self-shielding effect in reactor physics, ways to respect the self-shielding effect, practical examples,

4.Perturbation theory and its importance (2 lectures): mathematical requirements for the perturbation theory analysis, development of one-group and multi-group perturbation theory in diffusion approximation, perturbation theory utili-zation in reactor physics,

5.Coupled neutronic, thermomechanical, and thermohydraulic calculations (2 lectures): effect of nuclear fuel character-istics and heat removal system on nuclear fuel neutronic characteristics, definition of a feasible numerical coupling of neutronic, thermomechanical, and thermohydraulic calculations, illustration on a simple example for LWR.

Syllabus of tutorials:

1.Transport theory (2 seminars)

2.Differential cross-section (1 seminar)

3.Nuclear data preparation (2 seminars)

4.Perturbation theory (1 seminar)

5.Temperature effects in calculations of nuclear reactors (2 seminars)

Study Objective:
Study materials:

Key references:

[1]Lamarsh J.R., Baratta A.J: Introduction to Nuclear Engineering, Pearson, 2017, ISBN: 978-0134570051

[2]Hebert A.: Applied Reactor Physics, Presses internationales Polytechnique, 2016, 406 s. ISBN 978-2553016981

Recommended references:

[3]Lamarsh J.R.: Introduction to Nuclear Reactor Theory, American Nuclear Society, 2002, ISBN: 978-0894480409

Time-table for winter semester 2020/2021:
Time-table is not available yet
Time-table for summer semester 2020/2021:
Time-table is not available yet
The course is a part of the following study plans:
Data valid to 2021-03-05
For updated information see http://bilakniha.cvut.cz/en/predmet6303806.html