Safety Analyses of Nuclear Installations

The course is not on the list Without time-table
Code Completion Credits Range Language
17BAJZ KZ 4 2P+2C Czech
Department of Nuclear Reactors

The scope of this lecture is focused on general content of safety analysis report of nuclear installation, purpose of safety analysis and its preparation according to Czech legal framework and international recommendations. Model example is represented by reactor VR-1 and its safety analysis report that will be introduced to students during lectures. Special interest is put on design basis characteristics, i.e. its description and evidence of fulfilment for geodynamics, geotechnics, seismicity and transport paths of radionuclide. In addition, students will get familiar with topic of design-basis incidents and following design extensions for reactor VR-1. Students will be acquainted with common calculation codes for safety analyses and they will also gain hands-on experience with model problems.

Syllabus of lectures:

1.Purpose of safety analyses and safety analysis reports in different stages of nuclear installations

2.Czech legal framework requirements on safety calculations; IAEA recommendations for evaluation of safety analyses

3.Research reactor and nuclear power plant specifics

4.Safety analysis report of reactor VR-1

5.Design basis characteristics

6.Utilization of calculation codes for safety analyses

7.Postulated Initiating Events

8.Design-basis incidents and following design extensions for reactor VR-1

Syllabus of tutorials:

1.Introduction to thermohydraulic code: RELAP5

2.Preparation of input data for nuclear fuel IRT-4M

3.Introduction to neutronic code: SERPENT

4.Analysis of operational limits and conditions

5.Analysis of temperature effects at reactor VR-1

6.Occurrence of design-basis incident during critical experiment and its analysis

Study Objective:
Study materials:

Key references:

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

[2]IAEA: Safety in the Utilization and Modification of Research Reactors, International Atomic Energy Agency, 2012, ISBN 978-92-0-129110-3

[3]IAEA: Safety Reassessment for Research Reactors in the light of the Accident at the Fukushima Daiichi Nuclear Power Plant, International Atomic Energy Agency, 2014, ISBN 978-92-0-100814-5

Recommended references:

[4]Leppänen J.: Development of a New Monte Carlo Reactor Physics Code, VTT Technical Research Centre of Finland, 2007, ISBN 978-951-38-7019-5

[5]Act No. 263/2016 Coll., atomic act, Czech Republic, 2016

[6]Decree No. 378/2016 Coll., on siting of a nuclear installation, Czech Republic, 2016

Further information:
No time-table has been prepared for this course
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/predmet6304606.html