Critical Embedded Systems - Segédanyagok

Félév:
2018. ősz
2017. ősz
Title	Egyedi szöveg
Final Exam questions	Final Exam Critical Embedded Systems.pdf

Félév: 2018. ősz
Title	Egyedi szöveg
01_ Intro	01_Intro.pdf
02_Safety basics	02_SafetyBasics.pdf
03_Architectures	03_Architecture.pdf
04_Hazard Analysis	04_Hazard_Analysis_new.pdf
05_Formal methods	05_Formal_verification.pdf
06_ Aviation Safety Do-178	06_DO-178BandC.pdf
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: World Nuclear Association: Physics of Uranium and Nuclear Energy Nuclear Fundamentals: Reactivity Coefficients Summary World Nuclear Association: Nuclear Power Reactors World Nuclear Association: Safety of Nuclear Power Reactors World Nuclear Association: Three Mile Island accident World Nuclear Association: Chernobyl Accident World Nuclear Association: Fukushima Accident Lecture slides: Nuclear safety basics
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:: World Nuclear Association: Safety of Nuclear Power Reactors World Nuclear Association: Advanced Nuclear Power Reactors Lecture slides: Nuclear power plant safety basics
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: IAEA Nuclear Energy Series No. NP-T-3.12: Core Knowledge on Instrumentation and Control Systems in Nuclear Power Plants Lecture slides: Nuclear I&C Systems Basics
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: CORDEL Digital Instrumentation & Control Task Force (WNA): Safety Classification for I&C Systems in Nuclear Power Plants - Current Status & Difficulties IAEA Safety Standards Series No. SSG-30: Safety Classification of Structures, Systems and Components in Nuclear Power Plants (Specific Safety Guide) IAEA Safety Standards Series No. SSG-39: Design of Instrumentation and Control Systems for Nuclear Power Plants (Specific Safety Guide) Lecture slides: Nuclear I&C Systems Safety

Félév: 2017. ősz
Title	Egyedi szöveg
OO_Glossary of terms (English-Hun)	00_Glossary of Terms.pdf
01_Introduction to the course	01_Intro.pdf
02 Safety Basics	02_SafetyBasics.pdf
03_Architectures	03_Architecture.pdf
04_Safety requirement specification	04_Safety_Requirement_Specification.pdf
05_Hazard_Analysis	05_Hazard_Analysis.pdf
Reliability modeling Lab	CES_Reliability_modeling_handout.pdf
06 Formal verification	06_Formal_verification.pdf
Formal verification Lab	CES_uppaal_handout.pdf CES_verification_laboratory.pdf
07 DO-178B&C	07_DO-178BandC.pdf
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: World Nuclear Association: Physics of Uranium and Nuclear Energy Nuclear Fundamentals: Reactivity Coefficients Summary World Nuclear Association: Nuclear Power Reactors World Nuclear Association: Safety of Nuclear Power Reactors World Nuclear Association: Three Mile Island accident World Nuclear Association: Chernobyl Accident World Nuclear Association: Fukushima Accident
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:: World Nuclear Association: Safety of Nuclear Power Reactors World Nuclear Association: Advanced Nuclear Power Reactors
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: IAEA Nuclear Energy Series No. NP-T-3.12: Core Knowledge on Instrumentation and Control Systems in Nuclear Power Plants
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: CORDEL Digital Instrumentation & Control Task Force (WNA): Safety Classification for I&C Systems in Nuclear Power Plants - Current Status & Difficulties IAEA Safety Standards Series No. SSG-30: Safety Classification of Structures, Systems and Components in Nuclear Power Plants (Specific Safety Guide) IAEA Safety Standards Series No. SSG-39: Design of Instrumentation and Control Systems for Nuclear Power Plants (Specific Safety Guide)