
Boiling Water Reactors
- 1st Edition - January 26, 2023
- Imprint: Elsevier
- Editors: Koji Nishida, Shinichi Morooka, Michitsugu Mori, Yasuo Koizumi
- Language: English
- Paperback ISBN:9 7 8 - 0 - 1 2 - 8 2 1 3 6 1 - 2
- eBook ISBN:9 7 8 - 0 - 1 2 - 8 2 1 3 6 8 - 1
Boiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins wi… Read more
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Request a sales quoteBoiling Water Reactors, Volume Four in the JSME Series on Thermal and Nuclear Power Generation compiles the latest research in this very comprehensive reference that begins with an analysis of the history of BWR development and then moves through BWR plant design and innovations. The reader is guided through considerations for all BWR plant features and systems, including reactor internals, safety systems and plant instrumentation and control. Thermal-hydraulic aspects within a BWR core are analyzed alongside fuel analysis before comparisons of the latest BWR plant life management and maintenance technologies to promote safety and radiation protection practices are covered.
The book's authors combine their in-depth knowledge and depth of experience in the field to analyze innovations and Next Generation BWRs, considering prospects for a variety of different BWRs, such as High-Conversion-BWRs, TRU-Burner Reactors and Economic Simplified BWRs.
- Written by experts from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers
- Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits
- Considers societal impacts and sustainability concerns and goals throughout the discussion
- Explores BWR plant design, thermal-hydraulic aspects, the reactor core and plant life management and maintenance in one complete resource
1. History of BWR Development
1.1 Nuclear Energy Development in Japan
1.1.1 Primary energy supply
1.1.2 Electric power generation
1.1.3 Nuclear power generation
1.1.4 Nuclear power generation legislation
1.2 Establishment and Realization of BWR Technologies
1.2.1 Established stage
1.2.2 Realizing stage
1.3 Improvement and Standardization program in Japan
1.3.1 Technology importation
1.3.2 First improvement and standardization program
1.3.3 Second improvement and standardization program
1.3.4 Third improvement and standardization program
1.4 Improvement of System and Construction
1.4.1 Reduction of construction period of BWRs
1.4.2 Improvement of ABWR system and construction
1.5 Construction Experience and Operation Performance
1.5.1 Introduction period
1.5.2 Improvement and standardization programs of Japan
1.5.3 Recent status
2. Features of BWR Plant
2.1 Introduction
2.2 Reactor
2.2.1 Overview
2.2.2 Reactor system
2.2.3 Reactivity control system
2.2.4. Core monitoring system
2.3 Reactor Coolant System and Connected Systems
2.3.1 Overview
2.3.2 Nuclear boiler system
2.3.3 Reactor recirculation system
2.3.4 Reactor water clean-up system
2.3.5 Residual heat removal system
2.3.6 Leak detection system
2.4 Engineered Safety Features
2.4.1 Overview
2.4.2 Containment system
2.4.3 Emergency core cooling system
2.5 Instrumentation and Controls
2.5.1 Introduction
2.5.2 Overall architecture (example of ABWR)
2.5.3 Major control systems and auxiliary control systems
2.5.4 Safety systems
2.5.5 Process computer system
2.5.6 Human machine interface
2.6 Electric Power
2.6.1 Overview
2.6.2 Function
2.6.3 Configuration/Main equipment (example of ABWR)
2.7 Auxiliary System
2.7.1 Overview
2.7.2 Fuel pool cooling and clean-up system
2.7.3 Reactor building cooling water system
2.7.4 Reactor building service water system
2.7.5 Turbine building cooling water system
2.7.6 Turbine building service water system
2.7.7 Makeup water condensate system
2.7.8 Instrument air system
2.7.9 High pressure nitrogen gas supply system
2.7.10 Sampling system
2.7.11 Heating ventilating and air conditioning system
2.8 Steam and Power Conversion Systems
2.8.1 Overview
2.8.2 Steam and power conversion systems
3. Nuclear Reactor Dynamics and Thermal-Hydraulics of Reactor Core and Fuel Assembly
3.1 Reactor Internals and Coolant Flow Paths in Reactor Pressure Vessel
3.1.1 Unique basic characteristics of BWR core
3.1.2 Reactor core support structure and other reactor internals
3.1.3 Coolant flow paths and BWR operating map
3.2 Advances of Reactor Core and Fuel Assembly
3.2.1 High burnup fuel design
3.2.2 MOX fuel design
3.2.3 Thermal-hydraulics design
3.2.4 Enhancement of critical power
3.2.5 Countermeasure and cause of fuel rod failure
3.2.6 Proving test on thermal-hydraulic performance of BWR fuel assemblies
3.3 Advances in Reactor Core and Fuel Assembly Analysis
3.3.1 Nuclear analysis in BWR
3.3.2 Thermal-hydraulic system analysis codes and subchannel analysis codes
3.4 Advances in Containment Vessel Design
3.4.1 Thermal-hydraulics of severe accident
3.4.2 Accident management
for BWR3.5 Advances of Safety Analysis Code and Safety Systems
3.5.1 Various BWR analysis codes
3.5.2 BWR safety systems for sever accident
4. Fukushima Daiichi (Fukushima I) Nuclear Power Plant Accident and Analysis Evaluation
4.1 Outline of Accident
4.2 Event Progress and Analysis Evaluation at Unit 1
4.3 Event Progress and Analysis Evaluation at Unit 2
4.4 Event Progress and Analysis Evaluation at Unit 3
4.5 Hydrogen Explosion at Unit 4
4.6 Avoiding Severe Accidents at Fukushima Daini NPS
4.6.1 Overview of emergency response at Fukushima Daini NPS
4.6.2 Fukushima Daini Unit 1 response and station behavior
4.7 Lessons Learned from Fukushima Daiichi Accident
4.7.1 Causes of severe accidents and countermeasures
4.7.2 Measures for severe accidents installed in western NPPs
4.7.3 Filtered containment venting system
4.7.4 Special emergency heat removal system
4.7.5 Tsunami protection
4.8 New Nuclear Regulatory Requirements in Japan
4.8.1 New nuclear regulatory requirements
4.8.2 Tsunami protection examples
4.8.3 Tornado protection examples
4.9 Example of Compliance with New Regulatory Standards for PWRs that can be used as a Reference for BWRs
4.10 BWR NPS to be Reviewed for New Requirements or Restarting
4.11 Activities towards Decommissioning Fukushima Daiichi
4.11.1 Current status of the reactors at Units 1 through 4
4.11.2 Finding contaminated water leak path for leak shut-down from PCV
4.11.3 Isolation of ground-water flow from contaminated water
4.11.4 Contaminated water management
4.11.5 Preparation for fuel debris removal
4.12 Important Lessons Learned from Fukushima Daiichi NPS Accident
5. BWR Innovations
5.1 Trans-Uranic (TRU) Burner Reactor and Reduced-Moderation Water Reactor
5.1.1 TRU burner reactor
5.1.2 Reduced-Moderation light water reactor
5.2 High Pressure BWR
5.3 Power Uprate in BWR
5.3.1 Current status and trend of reactor power uprates
5.3.2 Reactor thermal power and electric power
5.3.3 Reactor power uprate with constant rated reactor thermal power operation
5.3.4 Relationship between reactor thermal power and electric power outputs
5.3.5 Issues and safety in constant rated reactor thermal power operation
5.3.6 Experiences in BWR operation with constant rated reactor thermal power operation
5.3.7 Power uprate with equipment modification
5.4 Post-BT Standard for BWR Power Plant
5.4.1 Introduction
5.4.2 Standard for assessment of fuel integrity under anticipated operational occurrences
5.5 Core Catcher
5.5.1 Overview of core melt stabilization and cooling
5.5.2 Core catcher of EU-ABWR
5.5.3 Core catcher for the existing BWR
5.6 Steam Injector
5.6.1 Introduction
5.6.2 Principle and application of SI
5.6.3 SI analysis model
5.6.4. Visualized fundamental tests
5.6.5 Application to SI-PCIS
5.6.6 Characteristic analysis for SI-PLR by using water jet type SI
5.6.7 Simplified feed water system
5.6.8 SI pump up system for PCC/IC pool water refill (SIPOWER)
5.7 Built in Upper Internal Control Rod Drives (CRD) for Next Generation BWR
5.7.1 Introduction of merits and technical tasks for internal CRD
5.7.2 Plant concepts
5.7.3 Power devices for the internal CRD
5.7.4. Internal CRD`s mechanism
5.7.5 Evaluation of BWR conditions
- Edition: 1
- Published: January 26, 2023
- No. of pages (Paperback): 616
- Imprint: Elsevier
- Language: English
- Paperback ISBN: 9780128213612
- eBook ISBN: 9780128213681
KN
Koji Nishida
SM
Shinichi Morooka
MM
Michitsugu Mori
YK