Boiling Water Reactors

Boiling Water Reactors
Copyright
Contributors
About the Authors
Preface of JSME series in Thermal and Nuclear Power Generation
Preface
Editing working group for volume 4: Boiling water reactors
Abbreviations
History of BWR development
Nuclear energy development in Japan
Primary energy supply
Electric power generation
Nuclear power generation
Nuclear power generation legislation
References
Establishment and realization of BWR technologies
Established stage
Introduction
Development of BWR by the Argonne National Laboratory in the United States
Realizing stage [3,6-22]
The early stage of GEs BWR development
The further stage of GEs BWR development
ABWR development with international cooperation
Next BWR development
References
Improvement and standardization program in Japan
Technology importation
First improvement and standardization program
Countermeasure for SCC [9,11,12,17,18]
Improved primary containment vessel (improved PCV)
Second improvement and standardization program [12,16]
Improvement of fuel-core design and CRD
Third improvement and standardization program
Development program of ABWR [9,13,20-27]
References
Improvement of system and construction
Reduction of the construction period of BWRs [1-3]
Large block and module technologies
Management by computer and information technologies
Improvement of ABWR system and construction [4-8]
Large block-module construction method
All-weather construction method
References
Construction experience and operation performance
Introduction period [1-4]
Improvement and standardization programs of Japan [2-7]
Recent status
References
Features of BWR plant
Introduction
Reference
Reactor
Overview
Reactor system
Reactor pressure vessel (RPV)
Reactor internals
Core and fuel
Control rods and control rod drive
Reactivity control system
Control rod drive system
Standby liquid control system
Core monitoring system
References
Reactor coolant system and connectedsystems
Overview
Nuclear boiler system
Main steam system
Feedwater system
Reactor recirculation system
Reactor water cleanup system
Residual heat removal system
Leak detection system
References
Engineered safety features
Overview
Containment system
Overview
Primary containment vessel (PCV)
Primary containment isolation system (PCIS)
Primary containment vessel gas control systems
Overview
Atmospheric control system (AC)
Flammability control system (FCS)
Containment heat removal system
Secondary containment
Standby gas treatment system (SGTS)
Emergency core cooling system
Overview of ECCS
Reactor core isolation cooling (RCIC) system
High-pressure core flooder system
Low-Pressure Flooder (LPFL)
References
Instrumentation and controls
Introduction
Overall architecture (example of ABWR)
Major control systems and auxiliary control systems
Major control systems
Auxiliary control systems
Safety systems
Process computer system
Human-machine interface
Electric power
Overview
Function
Configuration/main equipment (example of ABWR)
Grid connection
Transformers
Auxiliary medium-voltage distribution buses
Emergency diesel generators
DC power supply system
AC instrumentation power supply system
Auxiliary system
Overview
Auxiliary system
Fuel pool cooling and cleanup system [1]
Reactor building cooling water system [2]
Reactor building service water system [2]
Turbine building cooling water system [2]
Turbine building service water system [2]
Makeup water condensate system [2]
Instrument air system [2]
High-pressure nitrogen gas supply system [2]
Sampling system [2]
Heating ventilating and air conditioning system [2]
References
Steam and power conversion systems
Overview
Steam and power conversion systems
Turbine generator [1]
Main steam system, auxiliary steam system, and turbine bypass system [1]
Extraction steam system [1]
Turbine gland steam system [1]
Feedwater heater drain and vent system [1]
Condenser [1]
Circulating water system [1]
Condensate and feedwater system [2]
Off-gas system [2]
References
Nuclear reactor dynamics and thermal hydraulics of reactor core and fuel assembly
Reactor internals and coolant flow paths in a reactor pressure vessel
Unique basic characteristics of the BWR core
Application of negative void reactivity
BWR core configuration and basic design concept
Reactor core support structure and other reactor internals
Coolant flow paths and the BWR operating map
Coolant flow paths
Operating map
References
Advances of reactor core and fuel assembly
High burnup fuel design
Introduction
Reliability improvement (1970s)
Operational improvement
Economical improvement-Step I fuel and core
Economical improvement-Step II fuel and core
Economical improvement-Step III fuel and core
Summary
References
MOX fuel design
Thermal-hydraulic design
Thermal-hydraulic design basis of the reactor core
Nuclear thermal-hydraulic stability
Flow-induced vibration
References
Introduction
Basic information about Pu
Characteristics of Pu should be considered for utilization
MOX fuel assembly design
MOX core design
Summary
References
Countermeasures and cause of fuel rodfailure
Overview of fuel failures in BWRs
Countermeasures and cause of fuel rod failure
References
Proving test on the thermal-hydraulicperformance of BWR fuel assembly
Introduction
Proving test on thermal-hydraulic performance of a BWR fuel assembly
Void fraction measurement test for BWR fuel assembly [11-13]
Development of thermal-hydraulic correlations based on the full-scale BWR fuel assemblies data
References
Advances in reactor core and fuel assemblyanalysis
Nuclear analysis in BWRs
2D lattice calculation
3D core calculation analysis
Validation with measurements
References
General reference for nuclear analysis
Thermal-hydraulic system analysis code
Thermal-hydraulic subchannel analysis code
References
Advances in containment vessel design
Thermal hydraulics of severe accidents
Introduction
Initiation of fuel melt
Progression of core melt
Water-Zircaloy reaction accelerating fuel melt
Melting relocation inside the RPV
Melting jet structure and behaviors (from the RPV bottom to the PCV floor)
FP aerosol behaviors [3,4]
Accident management for BWR
Summary of AM
Defense in depth
International event scale (INES)
Selection of BWR AM measures
Typical BWR core damage sequence
In-vessel phenomena (from core melt to RPV bottom leak)
Ex-vessel phenomena after RPV failure
AMs for existing BWR
AMs for the recently operated and planned plants (also with PWR)
References
Advances in safety analysis codeand safety systems
Various BWR analysis codes
Importance of nuclear analysis codes
Best estimate code and evaluation model code
Verification and validation (VandV) of simulation [3,4]
BWR analysis code (EM code) [5]
LOCA analysis code (BE code)
SA progression analysis code
Computational fluid dynamic (CFD) analysis code
Large-scale test facility for code verification and obtaining correlations
BWR safety systems for severe accident
Passive safety concept
Reinforcement for passive safety
Lineup of passive safety systems
References
Fukushima Daiichi nuclear power plant accident and analysis evaluation
Outline of accident
Event progress and analysis evaluation at Unit 1
Event progress and analysis evaluation at Unit 2
Event progress and analysis evaluation at Unit 3
Hydrogen explosion at Unit 4
Avoiding severe accidents at Fukushima Daini NPS
Overview of emergency response at Fukushima Daini NPS
Fukushima Daini Unit 1 response and station behavior
Response status at the time of tsunami arrival
Reactor cooling water injection and PCV cooling
RHR restoration and reactor cold shutdown
Continuous ERC planning activities
Lessons learned from Fukushima Daiichi accident
Causes of severe accidents and countermeasures
Measures for severe accidents installed in the United States and European NPPs
Filtered containment venting system
Special emergency heat removal system
Tsunami protection
New nuclear regulatory requirements in Japan
New nuclear regulatory requirements
Tsunami protection examples
Tornado protection examples
Example of compliance with new regulatory standards for PWRs that can be used as a reference for BWRs
BWR NPS to be reviewed for new requirements or restarting
Activities toward decommissioning Fukushima Daiichi
Current status of reactors at Units 1 through 4
Finding contaminated water leak path for leak shutdown from PCV
Isolation of groundwater flow from contaminated water
Contaminated water management
Preparation for fuel-debris removal
Important lessons learned from Fukushima Daiichi NPS accident
References
BWR innovations
Trans-uranic (TRU) burner reactor and reduced-moderation water reactor
TRU burner reactor
Introduction
RBWR concept
RBWR specifications
RBWR core characteristics
Progressive introduction of RBWR [10]
References
Reduced-moderation light water reactor
Introduction [1-4]
Research and development of the cost-reduced low-moderation spectrum BWR
References
Design innovation of BWR and high-pressureBWR
Introduction
Objective of LSBWR design
Natural circulation core concept
Conceptual design of long cycle core of LSBWR
Examination of plant operating pressure and plant thermal efficiency
Safety system and PCV concept
Module fabrication and construction
Ship hull structure for reactor building
General arrangement of LSBWR and LLBWRs building design
Construction methodology and evaluation
Summary of design innovation of LSBWR, LLBWR, and high-pressure BWR
References
Power uprate in BWR
Current status and trend of reactor power uprates
Benefits and safety of constant rated reactor thermal power operation
Possibilities and issues on constant rated reactor thermal power operation
Current status of reactor power uprate with equipment modification
Reactor thermal power and electric power
Reactor power uprate with constant rated reactor thermal power operation
Relationship between reactor thermal power and electric power outputs
Issues and safety in constant rated reactor thermal power operation
Experiences in BWR operation with constant rated reactor thermal power operation
Power uprate with equipment modification
Uprate by measurement uncertainty recapture
High accuracy leading edge flowmeter (LEFM) for nuclear reactor feedwater measurement in MU
Inevitable issues on the accuracy of the PF in high accuracy ultrasonic flowmeters and new-concept flowmeter pos ...
Recent implementation and issues of uprates in the United States
References
Post-BT standard for BWR power plant
Introduction
Standard for the assessment of fuel integrity under anticipated operational occurrences
The method for predicting the change of rod temperature during post-BT operation
The criteria of fuel integrity after BT [9,10,13,20]
References
Core catcher
Overview of core melt stabilization and cooling
Core catcher of EU-ABWR
Concept of core catcher
Performance evaluation test
Core catcher for the existing BWR
Concept of core catcher
Performance evaluation test
References
Steam injector
Introduction
Principle and application of SI
SI analysis model
Visualized fundamental tests
Test apparatus and measurements
Test results
Application of steam jet-type SI to PCIS
High-pressure tests and analysis
Application of water jet type SI to RLP
Confirmation of analysis method
Scale-up examination of SI for application to RLP
High-pressure tests using scale models
Simplified feed water system by SI
Scaled model tests of simplified feedwater system
Analysis for improving SI-FWH
Transient test result of the first stage
Advantages of SI introduction to ABWR in volume and mass reduction
Steam injector (SI) pump-up water system to refill pool for passive containment cooling isolation condenser (PCC/I ...
Concept of SIPOWER
Evaluation of PCC/IC pool water level transient by SIPOWER
Full-scale mock-up test to confirm feasibility of SIPOWER
Air-purge analysis in PCC/IC pool for SIPOWER
Summary of SIPOWER
References
Built in upper internal control rod drives(CRDs) for ABWR-III
Introduction of merits and technical tasks for internal CRD
Plant concepts of ABWR-III
Power devices for the internal CRD
Magnet coupling power connector
Magnet coupling signal connector
Internal CRDs mechanism
Latch mechanism for scram operation and lift a control rod
Development of heatproof motor
Ceramics coil radiation durability test
Neutron flux at the internal CRD
Evaluation of ABWR-III conditions
Durability test of ball bearing
Two-phase flow and structural integrity
LOCA and pressure transient analysis
Aseismic analysis results
Summary
References
Index