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Table of Contents
Intro
Handbook of Small Modular Nuclear Reactors
Copyright
Dedication
Contents
Contributors
Preface
Introduction
Part One: Fundamentals of small modular nuclear reactors (SMRs)
Chapter 1: Small modular reactors (SMRs) for producing nuclear energy: An introduction
1.1. Introduction
1.1.1. Defining SMRs
1.1.2. Strategy for development of SMRs
1.1.3. Evolution of SMRs
1.2. Incentives and challenges for achieving commercial deployment success
1.2.1. Incentives
1.2.1.1. Reduction of initial investment and associated financial risk
1.2.1.2. Improved match to smaller electric power grids
1.2.2. Challenges
1.2.2.1. Sufficient reduction of financial risk
1.2.2.2. Projected LUEC
1.2.2.3. Fuel cycle compatibility with facilities and strategy
1.3. Overview of different types of SMRs
1.3.1. Reactor mission
1.3.2. Operational reliability
1.3.3. Economic implications of SMR technologies
1.4. Public health and safety
1.4.1. Potential energy release
1.4.2. Mitigation of the release of fission products
1.4.3. LOCA and decay heat removal
1.5. The current status of SMRs
1.6. Future trends
1.7. Conclusion
1.8. Sources of further information and advice
Appendix: Nomenclature
References
Chapter 2: Small modular reactors (SMRs) for producing nuclear energy: International developments
2.1. Introduction
2.2. Water-cooled reactors
2.2.1. Argentina: Central Argentina de Elementos Modulares design
2.2.2. Peoples Republic of China: ACP-100 design
2.2.3. France: Flexblue design
2.2.4. Republic of Korea: SMART design
2.2.5. Russian Federation: KLT-40S design
2.2.6. Russian Federation: RITM-200 design
2.2.7. Russian Federation: VK-300 design
2.2.8. United States and Japan: BWRX-300 design
2.2.9. United States: NuScale design.
2.2.10. United States: SMR-160 design
2.3. Gas-cooled reactors
2.3.1. Peoples Republic of China: HTR-PM design
2.3.2. Russian Federation: GT-MHR design
2.3.3. United States: EM2 design
2.3.4. United States: Xe-100 design
2.4. Liquid metal-cooled reactors
2.4.1. Japan: 4S design
2.4.2. Russian Federation: SVBR-100 design
2.4.3. United States: PRISM design
2.5. Molten-salt-cooled reactors
2.5.1. Canada: IMSR design
2.5.2. United States: KP-FHR design
2.5.3. United States: LFTR design
2.6. Future trends
2.7. Sources of further information
References
Chapter 3: Integral pressurized-water reactors (iPWRs) for producing nuclear energy: A new paradigm
3.1. Introduction
3.2. The imperatives for nuclear power
3.3. The integral pressurized-water reactor (iPWR)
3.3.1. The evolution of iPWR design
3.4. Addressing the safety imperative
3.5. Satisfying the economic competitiveness imperative
3.6. Future trends
3.7. Conclusion
3.8 Sources of further information and advice
References
Part Two: Small modular nuclear reactor (SMR) technologies
Chapter 4: Core and fuel technologies in integral pressurized water reactors (iPWRs)**This manuscript has been authored b ...
4.1. Introduction
4.2. Safety design criteria
4.2.1. Fuel burnup
4.2.2. Reactivity coefficients
4.2.3. Power distribution
4.2.4. Shutdown margin
4.2.5. Maximum reactivity insertion rate
4.2.6. Power stability
4.3. Design features to achieve the criteria
4.3.1. Setting the enrichment of the fissile material
4.3.2. BPs
4.3.3. In-core fuel management
4.3.4. Summary of the design process
4.4. Integral pressurized water reactor (iPWR) design specifics
4.4.1. Fuel designs in the smaller cores
4.4.2. Use of control rods and BPs to control reactivity
4.4.3. Core loading.
4.4.4. Other design considerations
4.5. Conclusion
References
Chapter 5: Key reactor system components in integral pressurized water reactors (iPWRs)**This submission was written by t ...
5.1. Introduction
5.2. Integral components
5.2.1. Pressure vessel and flange
5.2.2. Reactor coolant system piping
5.2.3. Pressurizer, heaters, spray valve, pressurizer relief tank and baffle plate
5.2.4. Pumps
5.2.5. Riser
5.2.6. Steam generator(s) and tube sheets
5.2.7. Control rods and reactivity control
5.2.8. Control rod drive mechanisms
5.2.9. Automatic depressurization system valves
5.2.10. Relief valves
5.2.11. Core basket, core barrel, core baffle
5.2.12. Instrumentation
5.3. Connected system components
5.3.1. Chemical and volume control system
5.3.2. Residual heat removal and auxiliary feedwater system
5.3.3. Emergency core cooling system and refueling water storage tank
5.3.4. External pool
5.3.5. Control room habitability equipment
5.3.6. Diesel generators and electrical distribution
5.4. Future trends
5.5. Sources of further information and advice
References
Chapter 6: Instrumentation and control technologies for small modular reactors (SMRs)
6.1. Introduction
6.1.1. Major components of an IandC system
6.2. Safety system instrumentation and controls
6.2.1. General requirements for safety system IandC
6.2.2. Safety system pressure transmitters
6.2.3. Safety system level transmitters
6.2.4. Safety system temperature devices
6.2.5. Safety system flow transmitters
6.2.6. Safety system power/flux devices
6.3. NSSS control systems instrumentation
6.3.1. General requirements for NSSS control system IandC
6.3.2. NSSS pressure transmitters
6.3.3. NSSS level transmitters
6.3.4. NSSS temperature devices
6.3.5. NSSS flow transmitters.
6.4. BOP instrumentation
6.5. Diagnostics and prognostics
6.6. Processing electronics
6.7. Cabling
6.8. Future trends and challenges
6.8.1. Licensing challenges in advanced SMR design
6.8.1.1. Overview
6.8.1.2. Use of probabilistic risk (safety) assessments in licensing iPWRs
6.8.1.3. Advances in safety system end-state architecture through simplification
6.8.1.4. Protection against common cause failure in iPWR IandC design
6.8.1.5. Safety classification of passive nuclear power plant electrical systems
6.8.1.6. Cybersecurity for iPWRs
6.8.2. Safety system instrumentation: Old versus new
6.8.3. Instrumentation in nonsafety systems
6.8.4. Wireless versus wired solutions
6.9. Conclusion
References
Chapter 7: Human-system interfaces in small modular reactors (SMRs)
7.1. Introduction
7.2. Human-system interfaces for small modular reactors
7.2.1. Hardware features
7.2.2. Software criteria
7.2.3. Functional criteria
7.3. The state of HSI technology in existing nuclear power plants
7.4. Advanced HSIs and the human factors challenges
7.4.1. Purpose and objectives of advanced HSIs
7.4.2. Human factors challenges of HSIs
7.5. Differences in the treatment of HSIs in the nuclear industry
7.6. How to identify and select advanced HSIs: Five dimensions
7.6.1. Dimension 1: The human factors context
7.6.2. Dimension 2: Technology characteristics
7.6.2.1. Technical characteristics
7.6.2.2. Context of use
7.6.3. Dimension 3: Operational requirements
7.6.4. Dimension 4: The organizational context
7.6.5. Dimension 5: The regulatory context
7.7. Operational domains of HSIs
7.7.1. Control and monitoring centers
7.7.1.1. Main control room
7.7.1.2. Multimodule control rooms
7.7.1.3. LCSs
7.7.2. Materials and waste fuel handling.
7.7.3. Outage control center
7.7.4. Emergency operating facility
7.7.5. Technical support center
7.8. HSI technology classification
7.8.1. Interaction modalities
7.8.2. Visual interfaces
7.8.2.1. Large screen displays
7.8.2.2. Wearable displays
7.8.2.3. 3D displays
7.8.3. Auditory interfaces
7.8.4. Control devices and mechanical interaction
7.8.5. Hybrid interfaces for multimodal interaction
7.8.5.1. Gesture interaction
7.8.5.2. Haptic interaction
7.8.5.3. Brain interaction
7.8.5.4. Intelligent and adaptive HSIs
7.9. HSI architecture and functions
7.10. Implementation and design strategies
7.10.1. Integration of human factors engineering in systems engineering
7.10.2. Regulatory requirements
7.10.3. Standards and design guidance
7.10.4. Design considerations
7.11. Future trends
7.12. Conclusion
References
Chapter 8: Safety of integral pressurized water reactors (iPWRs)
8.1. Introduction
8.1.1. Key features of SMR/iPWRs relevant for safety
8.1.2. Chapter overview
8.2. Approaches to safety: Active, passive, inherent safety and safety by design
8.3. Testing of SMR components and systems
8.3.1. IRIS SPES3 facility
8.3.2. NuScale integral system test (NIST)
8.3.3. SMART integral test loop (SMART-ITL) facility
8.3.4. BandW integrated system test (IST) facility
8.4. Probabilistic risk assessment (PRA)/probabilistic safety assessment (PSA)
8.4.1. Defense in depth (DID)
8.4.2. Improved probabilistic safety indicators
8.4.3. PRA-guided design
8.4.4. Use of PRA/PSA to support eliminating off-site emergency planning zone (EPZ) for SMRs
8.4.5. Seismic isolators
8.4.6. Safety challenges of iPWR SMRs
8.5. Security as it relates to safety
8.6. Future trends
References.
Chapter 9: Proliferation resistance and physical protection (PR&.
Handbook of Small Modular Nuclear Reactors
Copyright
Dedication
Contents
Contributors
Preface
Introduction
Part One: Fundamentals of small modular nuclear reactors (SMRs)
Chapter 1: Small modular reactors (SMRs) for producing nuclear energy: An introduction
1.1. Introduction
1.1.1. Defining SMRs
1.1.2. Strategy for development of SMRs
1.1.3. Evolution of SMRs
1.2. Incentives and challenges for achieving commercial deployment success
1.2.1. Incentives
1.2.1.1. Reduction of initial investment and associated financial risk
1.2.1.2. Improved match to smaller electric power grids
1.2.2. Challenges
1.2.2.1. Sufficient reduction of financial risk
1.2.2.2. Projected LUEC
1.2.2.3. Fuel cycle compatibility with facilities and strategy
1.3. Overview of different types of SMRs
1.3.1. Reactor mission
1.3.2. Operational reliability
1.3.3. Economic implications of SMR technologies
1.4. Public health and safety
1.4.1. Potential energy release
1.4.2. Mitigation of the release of fission products
1.4.3. LOCA and decay heat removal
1.5. The current status of SMRs
1.6. Future trends
1.7. Conclusion
1.8. Sources of further information and advice
Appendix: Nomenclature
References
Chapter 2: Small modular reactors (SMRs) for producing nuclear energy: International developments
2.1. Introduction
2.2. Water-cooled reactors
2.2.1. Argentina: Central Argentina de Elementos Modulares design
2.2.2. Peoples Republic of China: ACP-100 design
2.2.3. France: Flexblue design
2.2.4. Republic of Korea: SMART design
2.2.5. Russian Federation: KLT-40S design
2.2.6. Russian Federation: RITM-200 design
2.2.7. Russian Federation: VK-300 design
2.2.8. United States and Japan: BWRX-300 design
2.2.9. United States: NuScale design.
2.2.10. United States: SMR-160 design
2.3. Gas-cooled reactors
2.3.1. Peoples Republic of China: HTR-PM design
2.3.2. Russian Federation: GT-MHR design
2.3.3. United States: EM2 design
2.3.4. United States: Xe-100 design
2.4. Liquid metal-cooled reactors
2.4.1. Japan: 4S design
2.4.2. Russian Federation: SVBR-100 design
2.4.3. United States: PRISM design
2.5. Molten-salt-cooled reactors
2.5.1. Canada: IMSR design
2.5.2. United States: KP-FHR design
2.5.3. United States: LFTR design
2.6. Future trends
2.7. Sources of further information
References
Chapter 3: Integral pressurized-water reactors (iPWRs) for producing nuclear energy: A new paradigm
3.1. Introduction
3.2. The imperatives for nuclear power
3.3. The integral pressurized-water reactor (iPWR)
3.3.1. The evolution of iPWR design
3.4. Addressing the safety imperative
3.5. Satisfying the economic competitiveness imperative
3.6. Future trends
3.7. Conclusion
3.8 Sources of further information and advice
References
Part Two: Small modular nuclear reactor (SMR) technologies
Chapter 4: Core and fuel technologies in integral pressurized water reactors (iPWRs)**This manuscript has been authored b ...
4.1. Introduction
4.2. Safety design criteria
4.2.1. Fuel burnup
4.2.2. Reactivity coefficients
4.2.3. Power distribution
4.2.4. Shutdown margin
4.2.5. Maximum reactivity insertion rate
4.2.6. Power stability
4.3. Design features to achieve the criteria
4.3.1. Setting the enrichment of the fissile material
4.3.2. BPs
4.3.3. In-core fuel management
4.3.4. Summary of the design process
4.4. Integral pressurized water reactor (iPWR) design specifics
4.4.1. Fuel designs in the smaller cores
4.4.2. Use of control rods and BPs to control reactivity
4.4.3. Core loading.
4.4.4. Other design considerations
4.5. Conclusion
References
Chapter 5: Key reactor system components in integral pressurized water reactors (iPWRs)**This submission was written by t ...
5.1. Introduction
5.2. Integral components
5.2.1. Pressure vessel and flange
5.2.2. Reactor coolant system piping
5.2.3. Pressurizer, heaters, spray valve, pressurizer relief tank and baffle plate
5.2.4. Pumps
5.2.5. Riser
5.2.6. Steam generator(s) and tube sheets
5.2.7. Control rods and reactivity control
5.2.8. Control rod drive mechanisms
5.2.9. Automatic depressurization system valves
5.2.10. Relief valves
5.2.11. Core basket, core barrel, core baffle
5.2.12. Instrumentation
5.3. Connected system components
5.3.1. Chemical and volume control system
5.3.2. Residual heat removal and auxiliary feedwater system
5.3.3. Emergency core cooling system and refueling water storage tank
5.3.4. External pool
5.3.5. Control room habitability equipment
5.3.6. Diesel generators and electrical distribution
5.4. Future trends
5.5. Sources of further information and advice
References
Chapter 6: Instrumentation and control technologies for small modular reactors (SMRs)
6.1. Introduction
6.1.1. Major components of an IandC system
6.2. Safety system instrumentation and controls
6.2.1. General requirements for safety system IandC
6.2.2. Safety system pressure transmitters
6.2.3. Safety system level transmitters
6.2.4. Safety system temperature devices
6.2.5. Safety system flow transmitters
6.2.6. Safety system power/flux devices
6.3. NSSS control systems instrumentation
6.3.1. General requirements for NSSS control system IandC
6.3.2. NSSS pressure transmitters
6.3.3. NSSS level transmitters
6.3.4. NSSS temperature devices
6.3.5. NSSS flow transmitters.
6.4. BOP instrumentation
6.5. Diagnostics and prognostics
6.6. Processing electronics
6.7. Cabling
6.8. Future trends and challenges
6.8.1. Licensing challenges in advanced SMR design
6.8.1.1. Overview
6.8.1.2. Use of probabilistic risk (safety) assessments in licensing iPWRs
6.8.1.3. Advances in safety system end-state architecture through simplification
6.8.1.4. Protection against common cause failure in iPWR IandC design
6.8.1.5. Safety classification of passive nuclear power plant electrical systems
6.8.1.6. Cybersecurity for iPWRs
6.8.2. Safety system instrumentation: Old versus new
6.8.3. Instrumentation in nonsafety systems
6.8.4. Wireless versus wired solutions
6.9. Conclusion
References
Chapter 7: Human-system interfaces in small modular reactors (SMRs)
7.1. Introduction
7.2. Human-system interfaces for small modular reactors
7.2.1. Hardware features
7.2.2. Software criteria
7.2.3. Functional criteria
7.3. The state of HSI technology in existing nuclear power plants
7.4. Advanced HSIs and the human factors challenges
7.4.1. Purpose and objectives of advanced HSIs
7.4.2. Human factors challenges of HSIs
7.5. Differences in the treatment of HSIs in the nuclear industry
7.6. How to identify and select advanced HSIs: Five dimensions
7.6.1. Dimension 1: The human factors context
7.6.2. Dimension 2: Technology characteristics
7.6.2.1. Technical characteristics
7.6.2.2. Context of use
7.6.3. Dimension 3: Operational requirements
7.6.4. Dimension 4: The organizational context
7.6.5. Dimension 5: The regulatory context
7.7. Operational domains of HSIs
7.7.1. Control and monitoring centers
7.7.1.1. Main control room
7.7.1.2. Multimodule control rooms
7.7.1.3. LCSs
7.7.2. Materials and waste fuel handling.
7.7.3. Outage control center
7.7.4. Emergency operating facility
7.7.5. Technical support center
7.8. HSI technology classification
7.8.1. Interaction modalities
7.8.2. Visual interfaces
7.8.2.1. Large screen displays
7.8.2.2. Wearable displays
7.8.2.3. 3D displays
7.8.3. Auditory interfaces
7.8.4. Control devices and mechanical interaction
7.8.5. Hybrid interfaces for multimodal interaction
7.8.5.1. Gesture interaction
7.8.5.2. Haptic interaction
7.8.5.3. Brain interaction
7.8.5.4. Intelligent and adaptive HSIs
7.9. HSI architecture and functions
7.10. Implementation and design strategies
7.10.1. Integration of human factors engineering in systems engineering
7.10.2. Regulatory requirements
7.10.3. Standards and design guidance
7.10.4. Design considerations
7.11. Future trends
7.12. Conclusion
References
Chapter 8: Safety of integral pressurized water reactors (iPWRs)
8.1. Introduction
8.1.1. Key features of SMR/iPWRs relevant for safety
8.1.2. Chapter overview
8.2. Approaches to safety: Active, passive, inherent safety and safety by design
8.3. Testing of SMR components and systems
8.3.1. IRIS SPES3 facility
8.3.2. NuScale integral system test (NIST)
8.3.3. SMART integral test loop (SMART-ITL) facility
8.3.4. BandW integrated system test (IST) facility
8.4. Probabilistic risk assessment (PRA)/probabilistic safety assessment (PSA)
8.4.1. Defense in depth (DID)
8.4.2. Improved probabilistic safety indicators
8.4.3. PRA-guided design
8.4.4. Use of PRA/PSA to support eliminating off-site emergency planning zone (EPZ) for SMRs
8.4.5. Seismic isolators
8.4.6. Safety challenges of iPWR SMRs
8.5. Security as it relates to safety
8.6. Future trends
References.
Chapter 9: Proliferation resistance and physical protection (PR&.