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Nuclear Power Plant Instrumentation and Control Systems for Safety and Security

Book Description

Accidents and natural disasters involving nuclear power plants such as Chernobyl, Three Mile Island, and the recent meltdown at Fukushima are rare, but their effects are devastating enough to warrant increased vigilance in addressing safety concerns. Nuclear Power Plant Instrumentation and Control Systems for Safety and Security evaluates the risks inherent to nuclear power and methods of preventing accidents through computer control systems and other such emerging technologies. Students and scholars as well as operators and designers will find useful insight into the latest security technologies with the potential to make the future of nuclear energy clean, safe, and reliable.

Table of Contents

  1. Cover
  2. Title Page
  3. Copyright Page
  4. Book Series
  5. Editorial Advisory Board and List of Reviewers
    1. Editorial Advisory Board
    2. List of Reviewers
  6. Preface
    1. ORGANIZATION OF THE BOOK
  7. Acknowledgment
  8. Chapter 1: General Provisions
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. INSTRUMENTATION AND CONTROL (I&C) SYSTEMS
    5. COMPONENTS OF I&C SYSTEMS
    6. EQUIPMENT FAMILIES
    7. FUTURE RESEARCH DIRECTIONS
    8. CONCLUSION
  9. Chapter 2: International Standard Bases and Safety Classification
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. IAEA STANDARD BASE
    5. IAEA SAFETY CLASSIFICATION PRINCIPLES
    6. INTERNATIONAL ELECTROTECHNICAL COMMISSION STANDARD BASE
    7. IEC SAFETY CLASSIFICATION PRINCIPLES
    8. SAFETY CLASSIFICATION AND QUALITY REQUIREMENTS
    9. SHORT REMARKS ON THE NATIONAL STANDARD BASES
    10. FUTURE RESEARCH DIRECTIONS
    11. CONCLUSION
  10. Chapter 3: Properties of Safety Important I&C Systems and their Components
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. FUNCTIONAL PROPERTIES
    5. RELIABILITY OF I&C FUNCTIONS EXECUTION
    6. RESISTANCE OF FUNCTIONS EXECUTION
    7. QUALITY OF FUNCTIONS EXECUTION
    8. INDEPENDENCE OF FUNCTIONS
    9. SOFTWARE PROPERTIES
    10. FUTURE RESEARCH DIRECTIONS
    11. CONCLUSION
  11. Chapter 4: Field Programmable Gate Array Technology for NPP I&Cs
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. FEATURES OF FPGA TECHNOLOGY AND THEIR APPLICATION IN NPP I&CS
    5. FPGA-BASED NPP I&CS
    6. ANALYSIS ASPECTS OF FPGA-BASED NPP I&C SYSTEMS
    7. FUTURE RESEARCH DIRECTIONS
    8. CONCLUSION
  12. Chapter 5: Software of Safety Important I&C Systems
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. SOFTWARE OF NUCLEAR POWER PLANT I&C AS AN OBJECT OF SAFETY REQUIREMENT ESTABLISHMENT
    5. EVALUATION OF SOFTWARE FOR NUCLEAR POWER PLANT I&C SYSTEM
    6. FUTURE RESEARCH DIRECTIONS
    7. CONCLUSION
  13. Chapter 6: Diversity and Multi-Version Systems
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. COMMON EVENT AND COMMON CAUSE FAILURES
    5. ANALYSIS OF DIVERSITY RELATED STANDARDS
    6. NEW CHALLENGES OF DIVERSITY IMPLEMENTATION IN NPP I & C SYSTEM
    7. WORK RELATED ANALYSIS
    8. A LAW “NEGATION OF NEGATION”: STAGES OF DIVERSITY APPROACH IMPLEMENTATION EVOLUTION IN NPP I&CS
    9. AN EVOLUTION OF FPGA TECHNOLOGY AND DIVERSITY APPLICATION IN NPP I&CS
    10. MAIN CONCEPTS AND MODELS OF MULTI-VERSION COMPUTING
    11. ASSESSEMENT OF MVS SAFETY
    12. DIVERSITY ASSESSMENT TECHNIQUES AND TOOLS
    13. ASSESSMENT OF MULTI-VERSION FPGA-BASED SYSTEMS SAFETY
    14. IMPLEMENTATION OF FPGA-BASED SAFETY-CRITICAL NPP I&CS: UKRAINIAN EXPERIENCE
    15. RADIY RTS DIVERSITY ASSESSMENT
    16. FUTURE RESEARCH DIRECTIONS
    17. CONCLUSION
  14. Chapter 7: Security of Safety Important I&C Systems
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. STATE-OF-ART DOCUMENTS IN THE AREA OF CYBER SECURITY
    5. SAFETY AND SECURITY CONCEPTS FOR I&C SYSTEMS
    6. ASSESSMENT OF I&C SYSTEMS CYBER SECURITY
    7. ASSURANCE OF CYBER SECURITY FOR SAFETY IMPORTANT I&C SYSTEMS
    8. FUTURE RESEARCH DIRECTIONS
    9. CONCLUSION
  15. Chapter 8: Overall Instrumentation and Control Systems
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. BRIEF INFORMATION ON POWER UNITS WITH REACTORS WWER
    5. PRINCIPLES I&C SYSTEMS MODERNIZATION AT NPPS IN UKRAINE
    6. OVERALL I&C SYSTEM
    7. REACTOR CONTROL AND PROTECTION SYSTEM
    8. FUTURE RESEARCH DIRECTIONS
    9. CONCLUSION
  16. Chapter 9: Emergency and Preventive Reactor Protection Systems
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. PURPOSE
    5. FUNCTIONS
    6. CHARACTERISTICS
    7. CONSTRUCTION PRINCIPLES
    8. SAFETY ASSURANCE
    9. FUTURE RESEARCH DIRECTIONS
    10. CONCLUSION
  17. Chapter 10: Rod Group and Individual Control System
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. PURPOSE
    5. FUNCTIONS
    6. CHARACTERISTICS
    7. CONSTRUCTION PRINCIPLES
    8. SAFETY ASSURANCE
    9. SOLUTIONS AND RECOMMENDATIONS
    10. FUTURE RESEARCH DIRECTIONS
    11. CONCLUSION
  18. Chapter 11: Safety Parameters Display Systems
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. PURPOSE AND FUNCTIONS
    5. SPDS DESCRIPTION
    6. STRUCTURE
    7. ASSURANCE OF COMPLIANCE WITH SAFETY REQUIREMENTS
    8. IMPLEMENTATION OF SPDS PROJECT
    9. FUTURE RESEARCH DIRECTIONS
    10. CONCLUSION
  19. Chapter 12: Organization and Information Support of Expert Reviews of I&C Systems Modernization at NPP of Ukraine
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. SAFETY LIFE CYCLE OF THE NPP I&C SYSTEMS DURING THE MODERNIZATION
    5. PRINCIPLES OF SAFETY ASSESSMENT OF THE MODERNIZED NPP I&C SYSTEMS IN UKRAINE
    6. INFORMATION SUPPORT OF THE EXPERT REVIEWS OF THE NPP I&C SYSTEMS MODERNIZATION
    7. FUTURE RESEARCH DIRECTIONS
    8. CONCLUSION
    9. APPENDIX: ADDITIONAL READING
    10. Other Scientific and Technical Publications
  20. Chapter 13: NPP
    1. ABSTRACT
    2. INTRODUCTION
    3. BACKGROUND
    4. NPP – POWER GRID SAFETY ASSESSMENT BASED ON MUTUAL INFLUENCE ANALYSIS
    5. POWER GRID SAFETY: DYNAMICAL CRITICALITY CWW-BASED ANALYSIS
    6. PRINCIPLES AND TECHNIQUES OF DYNAMICAL CRITICALITY
    7. APPROACH TO NPP SAFETY ASSESSEMENT COMBINING FUZZY MODELS AND BAYESIAN BELIEF NETWORKS UNDER UNCERTANTIES
    8. FUTURE RESEARCH DIRECTIONS
    9. CONCLUSION
  21. Compilation of References
  22. About the Contributors