Glossary Term

Term: Boiling Water Reactor

The Boiling Water Reactor (BWR) is the second most common type of nuclear reactor, representing about 20% of the world's nuclear power plants.

Boiling Water Reactor

Overview

The Boiling Water Reactor (BWR) is the second most common type of nuclear reactor, representing about 20% of the world’s nuclear power plants. Unlike PWRs, BWRs allow water to boil directly in the reactor core, creating steam that drives the turbine-generator—a simpler design that came to symbolize both nuclear power’s promise and its perils after Fukushima.

Basic Design

Single-Loop System

  • Reactor pressure vessel: Contains fuel, control rods, and steam separation
  • Steam separation: Internal dryers remove moisture from steam
  • Direct cycle: Steam from reactor drives turbine directly
  • Condensate return: Water returns to reactor after turbine

Core and Vessel

  • Lower plenum: Water enters from bottom
  • Core region: Fuel assemblies where boiling occurs
  • Upper plenum: Steam separation and drying
  • Steam lines: Carry steam to turbine building

Key Features

Direct Boiling

  • Operating pressure: ~1,000 psi (70 bar)
  • Core exit temperature: ~285°C (545°F)
  • Steam quality: ~15% steam, 85% water at core exit
  • Natural circulation: Buoyancy drives water flow

Steam Separation

  • Steam separators: Remove water droplets from steam
  • Steam dryers: Further dry steam to <0.1% moisture
  • Recirculation: Separated water returns to core

Safety Systems

Engineered Safety Features

  • Emergency core cooling: Multiple injection systems
  • Reactor protection system: Automatic scram capability
  • Containment: Primary and secondary containment structures
  • Isolation systems: Automatic containment isolation

Unique BWR Features

  • Standby liquid control: Liquid poison injection
  • Automatic depressurization: Rapid pressure relief
  • Suppression pool: Pressure suppression system
  • Isolation condenser: Passive heat removal

Control Systems

Control Rod Design

  • Bottom entry: Control rods insert from below
  • Cruciform shape: Cross-shaped control rods
  • Hydraulic drive: Water pressure drives control rods
  • Scram capability: Rapid insertion for shutdown

Power Control

  • Control rod positioning: Primary reactivity control
  • Recirculation flow: Secondary power control
  • Steam flow: Affects reactor power through pressure

Fuel and Core Design

Fuel Assemblies

  • 8×8 or 10×10 arrays: Fuel rod configurations
  • Fuel channels: Zircaloy boxes around assemblies
  • Gadolinium burnable poison: Integrated neutron absorber
  • Enrichment: Typically 3-4% U-235

Core Configuration

  • Fuel assembly loading: Quarter-core symmetry
  • Control rod patterns: Checkerboard insertion
  • Refueling: 18-24 month cycles, 1/4 core replacement

Advantages

Design Simplicity

  • Single loop: Fewer components than PWR
  • Natural circulation: Reduced pumping requirements
  • Direct cycle: Higher thermal efficiency

Safety Features

  • Negative void coefficient: Power decreases with increased boiling
  • Pressure suppression: Efficient containment design
  • Passive systems: Natural circulation and gravity-driven safety

Disadvantages

Operational Challenges

  • Radioactive steam: Turbine becomes radioactive
  • Water chemistry: More complex than PWR
  • Maintenance access: Radiation concerns in turbine building

Design Limitations

  • Power density: Lower than PWR due to voiding
  • Stability concerns: Potential for power oscillations
  • Complexity: More instrumentation required

Variants

BWR Generations

  • BWR/1-3: Early designs (1960s-1970s)
  • BWR/4-5: Improved designs (1970s-1980s)
  • BWR/6: Advanced BWR design (1990s)
  • ABWR: Advanced Boiling Water Reactor (Generation III+)

Modern Designs

  • ABWR: Toshiba/Hitachi advanced design
  • ESBWR: GE-Hitachi Economic Simplified BWR
  • UK ABWR: Hitachi design for UK market

Global Deployment

Major BWR Countries

  • United States: 32 operating BWRs
  • Japan: Significant BWR fleet (many post-Fukushima shutdown)
  • Sweden: Several BWRs in operation
  • Taiwan: ABWR technology

Fukushima Impact

The 2011 Fukushima Daiichi accident involved three BWRs:

  • Station blackout: Loss of electrical power
  • Cooling system failure: Unable to remove decay heat
  • Hydrogen explosions: Resulted from overheated fuel
  • Lessons learned: Improved emergency procedures and equipment

Relevance to Nuclear Weapons

BWR technology is relevant to weapons programs because:

  • Plutonium production: Can produce weapons-grade plutonium
  • Nuclear infrastructure: Demonstrates nuclear technology capability
  • Dual-use concerns: Peaceful technology can support weapons programs
  • Safeguards: Subject to international monitoring and inspection

However, like PWRs, commercial BWRs are not optimized for weapons material production and operate under strict international oversight.


Sources

Authoritative Sources:

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