Nuclear Reactor Physics
Code  Completion  Credits  Range  Language 

17FARE  Z,ZK  4  2P+2C  Czech 
 Garant předmětu:
 Jan Frýbort, Lenka Frýbortová
 Lecturer:
 Jan Frýbort, Lenka Frýbortová
 Tutor:
 Jan Frýbort, Lenka Frýbortová, Pavel Suk
 Supervisor:
 Department of Nuclear Reactors
 Synopsis:

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, transport equation formulation, and its utilization in reactor physics. The transport theory requires broad range of nuclear data. The students will learn how continuous and groupwise nuclear data are prepared and how the selfshielding 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.
 Requirements:
 Syllabus of lectures:

1.Transport theory in reactor physics (3 lectures): definition of transport theory requirements and its development, utilization 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, evaluation and validation of nuclear data, specific features of continuous and groupwise nuclear data,
3.Selfshielding effect and its importance in reactor physics (2 lectures): importance of selfshielding effect in reactor physics, ways to respect the selfshielding effect, practical examples,
4.Perturbation theory and its importance (2 lectures): mathematical requirements for the perturbation theory analysis, development of onegroup and multigroup perturbation theory in diffusion approximation, perturbation theory utilization in reactor physics,
5.Coupled neutronic, thermomechanical, and thermohydraulic calculations (2 lectures): effect of nuclear fuel characteristics 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 crosssection (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: 9780134570051
[2]Hebert A.: Applied Reactor Physics, Presses internationales Polytechnique, 2016, 406 s. ISBN 9782553016981
Recommended references:
[3]Lamarsh J.R.: Introduction to Nuclear Reactor Theory, American Nuclear Society, 2002, ISBN: 9780894480409
 Note:
 Timetable for winter semester 2023/2024:
 Timetable is not available yet
 Timetable for summer semester 2023/2024:
 Timetable is not available yet
 The course is a part of the following study plans: