Accidents of Nuclear Installations

Course guarantor:

Lecturer:

Tutor:

Supervisor:

Department of Nuclear Reactors

Synopsis:

The scope of this lecture is focused on basic principles of management of severe accidents, specific requirements that are described in SAMG (Serious accident management guides) and EOP (Emergency operating procedures) based on definition of Czech legal framework. Students will enhance their knowledge of technologies and management structure of nuclear power plant necessary to successfully manage a serious accident. In addition a theoretical background will be presented for basic phenomenology of serious accidents, including behaviour of fission products, source term, and introduction to physical and chemical basis of selected processes that are frequent in nuclear power plant accidents. Students will be acquainted with codes for accident analyses utilization and understanding of basic calculation aspects. Specific phenomena will be presented with the help of actual accidents at nuclear power plants, namely TMI-2 and Fukushima. The final part of the course is devoted to thermal-hydraulic issues in Generation IV reactor systems.

Requirements:

To be awarded course credit, students are required to actively participate in class sessions and to successfully complete (with at least 50% correct answers) short multiple-choice tests administered at the beginning of each lecture. Tests from missed lectures must be completed by the student during the next class session attended. If these criteria are fulfilled, the student will be granted course credit with a grade of A. In cases where, at the end of the semester, a student has multiple tests with fewer than 50% correct answers, they are entitled to take a remedial comprehensive multiple-choice test composed of selected questions from the semesters tests. The grade will then be determined according to the standard CTU grading scale.

Syllabus of lectures:

1.Serious accidents and basic principles for management

2.SAMG (Serious accident management guides), EOP (Emergency operating procedures)

3.Technologies for serious accident management

4.WENRA and its reference levels

5.Description of ongoing processes during serious accident at nuclear power plant

6.Source term

7.Utilization of calculation codes

8.Analyses of TMI-2 and Fukushima accidents

Syllabus of tutorials:

1. MELCOR: modelling of FL leakage in the containment system

2. MELCOR: design of passive autocatalytic recombiners (PARs)

3. MELCOR: GenPWR-1000 steady-state simulation

4. MELCOR: GenPWR-1000 transients

5. MELCOR: GenPWR-1000 evaluation and post-processing

6. ASTEC post-processing aerosol transport

7. ASTEC post-processing iodine speciation

8. VINSAP: simulation of thermal-hydraulics at NPP Dukovany/Temelín using a visualisation tool

9. MELTSPREAD: corium spreading calculations

10. CORQUENCH: corium coolability calculations

Study Objective:

Study materials:

Recommended references:

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

[2]IAEA: Severe Accident Management Programmes for Nuclear Power Plants, International Atomic Energy Agency, 2009, ISBN 978-92-0-112908-6

[3]IAEA: Accident Management Programmes for Nuclear Power Plants, International Atomic Energy Agency, 2019, ISBN 978-92-0-108318-0

[4]LANL: A Review of Criticality Accidents. LA-13638, Los Alamos National Laboratory, USA, 2000

Note:

Further information:

No time-table has been prepared for this course

The course is a part of the following study plans: