Control Systems of Nuclear Reactors

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Code Completion Credits Range Language
17BES Z,ZK 2 2+0 Czech
Martin Kropík (guarantor)
Martin Kropík (guarantor)
Department of Nuclear Reactors

Matter of the subject is concentrated on categorization of systems in nuclear power plant according to importance to nuclear safety; next on requirements of different categories of systems and typical instrumentation of research nuclear facilities and nuclear power plants. Attention is given to definition of nuclear safety, single failure criterion and redundancy, common cause failures, independence and diversity; furthermore to qualification of safety systems. At the end, lectures deal with control and safety systems of systems research nuclear facilities. The lectures are completed with visit of the training reactor VR 1 with demonstration of its safety and control system.



Syllabus of lectures:

1. Nuclear safety and systems in nuclear facilities, introduction into problematic, introduction of lectures into complete education and relation to other subjects, objectives of the subject; definition of nuclear safety and its use in nuclear facilities, basic approaches to providing of nuclear safety

2. Categorization of systems in nuclear facilities according to IAEA 1; approach of IAEA to categorization of systems in nuclear facilities in accordance of their importance to nuclear safety, requirements on safety (protection) systems and safety related systems - e.g. control systems; defense in depth, single failure criterion, redundancy

3.Categorization of systems in nuclear facilities according to IAEA 1; independence, spatial separation and functional isolation of systems, common cause failures, diversity, control rooms, emergency control rooms, introduction into problematic of use of computers in systems important to nuclear safety

4. Categorization of system in nuclear power plants according to IEC, IEC612226 standard for categorization of systems in nuclear power plants, similarities and differences in comparison to IAEA; categories A, B, C, requirements on their structure, quality and reliability

5. Categorization of systems according to IEEE; American approach to categorization of system according to importance to nuclear safety, systems class 1E a non 1E, similarities and differences in comparison to IAEA and IEC

6. Requirements on protection systems according to German standards KTA; German requirements on protection systems of nuclear facilities according to KTA 3501, specific German requirements on reliability, functionality, diversity, backed-up power supply, signalization; comparison with common European and American standards

7. Requirements on instrumentation and control systems of nuclear power plants; architecture of systems, requirements on instrumentation, nuclear safety guarantee, life cycle of facilities, operation, documentation and licensing according to IEC61513

8. Qualification of systems; standard IEC60780 for qualification of systems, type test, operational experience, analysis; type tests methodology, documentation of operational experience, limitations of system qualification by analysis

9. Safety and control systems of research nuclear facilities; Safety Guide of Czech State Office for Nuclear Safety (SONS), requirements on safety and control systems of research nuclear facilities according to the Safety Guide of SONS, systems structure, redundancy, coincidence logic, diversity, backed-up power supply, signalization, reactivity control

10. Diagnostics of nuclear research facilities; neutron flux measurement - types of neutron chambers, pulse, DC current and Campbell regimes; technical realization, comparison of methods

11. Safety and control system of the VR 1 training reactor; system structure, its components and their importance, assessment of fulfillment of SONS Safety Guide requirements, safety limits, safety function, reactor operation

12. Excursion of VR 1 reactor; visit of safety and control system, human machine interface, system testing, reactor start up, reactor operation, neutron flux measurement, demonstration of safety functions

13. Instrumentation of other research nuclear facilities; instrumentation of LR 15 and LR 0 in NRI Ře6, training reactor in KURRI (Japan), SUR reactor in TU Dresden, reactor TRIGA MARK II in Atominstitut Vienna (Austria), reactor FRM in Garching (Germany) and reactor AGN in Suwon university (Republic of Korea)

Syllabus of tutorials:

No tutorials, only discussion about required literature and excursion at training reactor VR 1

Study Objective:

Knowledge: detailed knowledge of safety systems of nuclear facilities, their philosophy, robustness against potential problems and failures

Abilities: orientation in matter of safety systems, use gained knowledge in other subjects of reactor physics, nuclear power plants and operator?s course during further education

Study materials:

Key references:

Instrumentation and Control Systéme Important to Safety in Nuclear Power Plants, Safety Guide, NS-G-1.3, IAEA, Vienna, 2002

Recommended references:

Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions, IEC 61226, 2009

IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations -Description, IEEE Std 603-1998

Nuclear power plants - Electrical equipment of the safety system - Qualification, IEC60780, 1998

Media and tools:

training reactor VR 1 laboratory

Time-table for winter semester 2018/2019:
Time-table is not available yet
Time-table for summer semester 2018/2019:
Time-table is not available yet
The course is a part of the following study plans:
Data valid to 2019-06-16
For updated information see http://bilakniha.cvut.cz/en/predmet1182806.html