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CZECH TECHNICAL UNIVERSITY IN PRAGUE
STUDY PLANS
2023/2024
UPOZORNĚNÍ: Jsou dostupné studijní plány pro následující akademický rok.

Nuclear-Power-Plant Simulator Exercise

The course is not on the list Without time-table
Code Completion Credits Range Language
17CSI Z 3 0+3 Czech
Garant předmětu:
Lecturer:
Tutor:
Supervisor:
Department of Nuclear Reactors
Synopsis:

Course is pointed to pass to students the idea about main operating features of nuclear power plants with various types of reactors, about physical coupling amid single components of nuclear power plants and about principles of operating. In the theoretical part, there is briefly described each power plant and its simulator and simulator's physical background. The main part of this course is dedicated to practising of various tasks (rated output, transiensts, malfunction of components) on simulators. The course takes place in simulators of following power units: VVER-440, ABWR and CANDU 6. During these exercises the basic physical features of system are always analysed and there are also given reasons of their changes and connections between them.

Requirements:
Syllabus of lectures:

1. Introduction to simulators

1 lecture

Simulator definition, simulator division according to approximation to reality, simulators importance in nuclear power, basic principles of simulators development, development environments for their development.

2. VVER-440 simulator

1 lecture, 5 exercises

Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks at primary circuit, leaks at secondary circuit, pumps failures, etc.).

3. ABWR simulator

1 lecture, 2 exercises

Description of ABWR system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks, pumps failures, etc.).

4. CANDU 6 simulator

1 lecture, 2 exercises

Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features.

5. General evaluation

1 exercise

General evaluation of systems and their characteristics, regulation modes and dynamic features.

Syllabus of tutorials:

1. Introduction to simulators

1 lecture

Simulator definition, simulator division according to approximation to reality, simulators importance in nuclear power, basic principles of simulators development, development environments for their development.

2. VVER-440 simulator

1 lecture, 5 exercises

Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks at primary circuit, leaks at secondary circuit, pumps failures, etc.).

3. ABWR simulator

1 lecture, 2 exercises

Description of ABWR system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features, exercises and analyses of emergency situations (leaks, pumps failures, etc.).

4. CANDU 6 simulator

1 lecture, 2 exercises

Description of VVER-440 (NPP Dukovany) system and its control, description of physical background in simulator and automatic regulators which are implemented in simulator, simulator description, familiarization with simulator through exercises and analyses of power changes at nominal states and basic transients with use of automatic regulators, exercises and analyses of transients (loop set-back, turbo-generator shut- down, etc.), exercises and analyses focused on determination of system physical features.

Study Objective:

Knowledge: detailed knowledge of simulated systems, basic operational states and characteristics of systems, control modes of nuclear power plants, physical couplings amid devices of power plant, dynamics of systems.

Abilities: judge dynamics behavior of nuclear power plant, orientation in devices on nuclear power plant and their functions.

Study materials:

Key references

Gieci A., Macko J.: Návody ke cvičením na SPVS+EDU, Provozní stavy, VÚJE, Trnava, 2007

Gieci A., Macko J.: Vedení výcviku na SPVS+ETE, Odborná studie, VÚJE, Trnava, 2004

IAEA: Boiling water reactor simulator, Workshop material, IAEA, Vienna, 2003, IAEA-TCS-23

Bereznai G.: Introduction to CANDU systems and operation, University of Ontario, Ontario 2003

Recommended references:

IAEA: Reactor Simulator Development, Workshop material, IAEA, Vienna, 2001, IAEA-TCS-12

Note:
Further information:
No time-table has been prepared for this course
The course is a part of the following study plans:
Data valid to 2024-03-27
Aktualizace výše uvedených informací naleznete na adrese https://bilakniha.cvut.cz/en/predmet1906306.html