Critical Embedded Systems - Segédanyagok

Félév:
2018. ősz
2017. ősz
Title Egyedi szöveg
Final Exam questions
Félév: 2018. ősz
Title Egyedi szöveg
01_ Intro
02_Safety basics
03_Architectures
04_Hazard Analysis
05_Formal methods
06_ Aviation Safety Do-178
Nuclear Safety Basics

Nuclear Safety Basics - Introduction to the goals and terminology of Nuclear Safety

  • Basics of nuclear power generation, inherent security, feedback
  • Comparison of Functional Safety (61508) and Nuclear Safety
  • Postulated initial events (PIE), design basis
  • Nuclear incidents, accidents - INES scale
  • Important reactor accidents and malfunctions:
    • Three Mile Island
    • Chernobyl
    • Fukushima
    • Serious incident at Paks in 2003
  • Regarding each nuclear accident:
    • What causes and events led to the accident?
    • How did the accident proceed and what were the consequences?
    • What and how could/should have been done differently to avoid the accident / reduce the consequences?
    • What lessons were learned from the accident and how did nuclear safety change, with particular regard to control systems?

Sources, background material:

Nuclear Power Plant Safety Basics

Nuclear Power Plant Safety Basics - Construction Principles and Safety Features on the Nuclear Power Plant Level

  • Characteristics of nuclear power plants
  • Security objectives and basic defense strategies
  • Major protection systems and their functions
  • Major Generation III + reactor types and their main characteristics

Sources, background material::

Nuclear Istrumentation and Control Systems Basics

Nuclear I&C Systems Basics - The role of Instrumentation and Control Systems in Nuclear Power Plants, and their Characteristics

  • Essential functions of the control systems of nuclear power plants
  • Hierarchical and functional grouping of nuclear control systems
  • (Normal operation) Control systems, Limiters (limiting controls), Interlocks, Protection systems
    • what role do fulfill, how do they influence the process?
  • Protection systems in the Paks NPP
  • Unit power control strategies, their characteristics
    • Power Control with Pre-Turbine Intervention
    • Power Control with Reactor-side Intervention
    • Integrated
  • I&C functions in reactivity control, heat removal from the core, and confinement of radioactive materials
  • Typical architecture of the I&C systems of nuclear power plants

Sources, background material:

Nuclear Istrumentation and Control Systems Safety

Nuclear I&C Systems Safety - The Principles of Nuclear Safety for Instrumentation and Control Systems

  • Legal and regulatory background (Atomic Act, NSC (Govt. Decree 118/2011), Govt. Decree 190/2011)
  • OAH's (Hungarian Atomic Energy Authority) role and responsibilities
  • IAEA's role and responsibilities
    • IAEA standards and guides
  • IEC (International Electrotechnical Commission)
    • IEC standards for nuclear I&C systems
  • Security categorization, security classification (IAEA, IEC and Hungarian)
  • Main principles of nuclear I&C design
  • Design for reliability of I&C systems important to safety:
    • The principle, the levels and the purpose of the defense in depth concept
    • The concept and tools of single failure tolerance
    • The concept of common cause failure, the means of avoiding it
      • independence
      • separation
      • diversity
    • Fail-safe design, safety orientation concept

Resources, background material:

Félév: 2017. ősz
Title Egyedi szöveg
OO_Glossary of terms (English-Hun)
01_Introduction to the course
02 Safety Basics
03_Architectures
04_Safety requirement specification
05_Hazard_Analysis
Reliability modeling Lab
06 Formal verification
Formal verification Lab
07 DO-178B&C
Nuclear Safety Basics

Nuclear Safety Basics - Introduction to the goals and terminology of Nuclear Safety

  • Basics of nuclear power generation, inherent security, feedback
  • Comparison of Functional Safety (61508) and Nuclear Safety
  • Postulated initial events (PIE), design basis
  • Nuclear incidents, accidents - INES scale
  • Important reactor accidents and malfunctions:
    • Three Mile Island
    • Chernobyl
    • Fukushima
    • Serious incident at Paks in 2003
  • Regarding each nuclear accident:
    • What causes and events led to the accident?
    • How did the accident proceed and what were the consequences?
    • What and how could/should have been done differently to avoid the accident / reduce the consequences?
    • What lessons were learned from the accident and how did nuclear safety change, with particular regard to control systems?

Sources, background material:

Nuclear Power Plant Safety Basics

Nuclear Power Plant Safety Basics - Construction Principles and Safety Features on the Nuclear Power Plant Level

  • Characteristics of nuclear power plants
  • Security objectives and basic defense strategies
  • Major protection systems and their functions
  • Major Generation III + reactor types and their main characteristics

Sources, background material::

Nuclear I&C Systems Basics

Nuclear I&C Systems Basics - The role of Instrumentation and Control Systems in Nuclear Power Plants, and their Characteristics

  • Essential functions of the control systems of nuclear power plants
  • Hierarchical and functional grouping of nuclear control systems
  • (Normal operation) Control systems, Limiters (limiting controls), Interlocks, Protection systems
    • what role do fulfill, how do they influence the process?
  • Protection systems in the Paks NPP
  • Unit power control strategies, their characteristics
    • Power Control with Pre-Turbine Intervention
    • Power Control with Reactor-side Intervention
    • Integrated
  • I&C functions in reactivity control, heat removal from the core, and confinement of radioactive materials
  • Typical architecture of the I&C systems of nuclear power plants

Sources, background material:

Nuclear I&C Systems Safety

Nuclear I&C Systems Safety - The Principles of Nuclear Safety for Instrumentation and Control Systems

  • Legal and regulatory background (Atomic Act, NSC (Govt. Decree 118/2011), Govt. Decree 190/2011)
  • OAH's (Hungarian Atomic Energy Authority) role and responsibilities
  • IAEA's role and responsibilities
    • IAEA standards and guides
  • IEC (International Electrotechnical Commission)
    • IEC standards for nuclear I&C systems
  • Security categorization, security classification (IAEA, IEC and Hungarian)
  • Main principles of nuclear I&C design
  • Design for reliability of I&C systems important to safety:
    • The principle, the levels and the purpose of the defense in depth concept
    • The concept and tools of single failure tolerance
    • The concept of common cause failure, the means of avoiding it
      • independence
      • separation
      • diversity
    • Fail-safe design, safety orientation concept

Resources, background material:

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