GE BWR

GE BWR (General Electric Boiling Water Reactor)
Generation	Generation I (BWR-1) Generation II Generation III (ABWR) Generation III+ (ESBWR)
Reactor concept	Light water reactor (LWR)
Reactor line	Boiling water reactor (BWR)
Designed by	General Electric
Manufactured by	General Electric
Status	83 reactors built, 67 reactors operational (As of August 2018)
Main parameters of the reactor core
Fuel (fissile material)	235U/235Pu (LEU/MOX)
Fuel state	Solid
Neutron energy spectrum	Thermal
Primary control method	Control rods
Primary moderator	Light water
Primary coolant	Liquid (water)
Reactor usage
Primary use	Generation of electricity
Power (thermal)	530 MWth (BWR-1) 1500 MWth (BWR-2) 2400 MWth (BWR-3) 3000 MWth (BWR-4) 3100 MWth (BWR-5) 3400 MWth (BWR-6) 4000 MWth (ABWR) 4500 MWth (ESBWR)
Power (electric)	160 MWe (BWR-1) 650 MWe (BWR-2) 460 MWe (BWR-3) 784 MWe (BWR-4) 1050 MWe (BWR-5) 1150 MWe (BWR-6) 1400 MWe (ABWR) 1600 MWe (ESBWR)

Schematic GE BWR inside a Mark I containment.

General Electric's BWR product line of boiling water reactors represents the designs of a relatively large (~18%) percentage of the commercial fission reactors around the world.

The progenitor of the BWR line was the 5 MW Vallecitos Boiling Water Reactor (VBWR), brought online in October 1957. Six design iterations, BWR-1 through BWR-6, were introduced between 1955 and 1972.

This was followed by the Advanced Boiling Water Reactor (ABWR) introduced in the 1990s and the Economic Simplified Boiling Water Reactor (ESBWR) introduced in the early 2010s.

As of August 2018, 83 reactors of this design family have been built, of which 67 reactors are operational.

The design garnered world attention in the aftermath of the INES level 7 Fukushima Daiichi nuclear disaster of 11 March 2011. GE had been a major contractor to the Fukushima Daiichi Nuclear Power Plant in Japan, which consisted of six boiling water reactors of GE design. The reactors for Units 1, 2, and 6 were supplied by General Electric, the other three by Toshiba and Hitachi. Unit 1 was a 460 MW boiling water reactor from the BWR-3 design iteration introduced in 1965 and constructed in July 1967.

After the plant became severely damaged in the Tōhoku earthquake and tsunami, loss of reactor core cooling led to three nuclear meltdowns, three hydrogen explosions, and the release of radioactive contamination in Units 1, 2 and 3 between 12 and 15 March. Safe operation of this reactor design family depends on continued coolant flow at all times during operation. A reactor after a full-power shutdown may require active cooling of decay heat from long-lived radioactive isotopes for a year or more.

History

The progenitor of the BWR line was the 5 MW Vallecitos Boiling Water Reactor (VBWR), brought online in October 1957.

BWR-1

• BWR Type 1 (BWR-1, BWR/1): In 1955 GE developed their original VBWR design into the 197 MW Dresden 1 (6×6, 7×7) reactor, embodying the first iteration of GE's BWR/1 design. Dresden 1 used forced circulation (via external recirculation pumps) and a unique dual cycle (direct+indirect) heat transfer design that proved to be uneconomical. GE further developed the BWR-1 design with the 70 MW Big Rock Point (9×9, 11×11, 12×12) reactor, which (like all GE BWR models following Dresden 1) used the more economical direct cycle method of heat transfer, but disposed with the external recirculation pumps in favor of natural circulation (an unusual strategy that only the 55 MW Dodewaard reactor adopted, although this technique has been resurrected for the newest Gen III+ ESBWR). The 65 MW Humboldt Bay (6×6, 7×7) reactor followed Big Rock Point, returning to the more efficient forced circulation method (via external recirculation pumps). These experimental designs (all of which shared the BWR-1 classification despite their divergent designs) used fuel rod bundles in 6×6, 7×7, 8×8, 9×9, 11×11, and 12×12 configurations, but GE's 9×9 bundle later used in BWR/2–6 reactors is different from the one used in the BWR/1 era. The BWR/1 was the first BWR design with internal steam separation. It also had an isolation condenser, and pressure suppression containment.

BWR-2

• BWR Type 2 (BWR-2, BWR/2): Introduced in 1963, >500 MW_e, typically around 650 MW_e gross (Oyster Creek, Nine Mile Point 1). Included a large direct cycle. 5 recirculation loops, variable speed external recirculation pumps (one pump per loop, each pump's flow rate could be varied from 6,400 to 32,000 US gallons per minute (0.40 to 2.02 m³/s)). This design, as well as the BWR/3–6, would all later be classified as Generation II reactors for their increased scale, improved safety features, commercial viability, profitability, and long lifetime.

BWR-3

• BWR Type 3 (BWR-3, BWR/3): Introduced in 1965, 800 MW (Dresden 2–3). First use of internal jet pumps (single nozzle, 10 per loop, 20 total). 2 recirculation loops, variable speed recirculation pumps (one pump per loop, each pump had a rated flow of 45,200 US gallons per minute (2.85 m³/s)). Improved ECCS spray and flood, improved feedwater spargers. Monticello and Pilgrim 1 had significantly lower power ratings despite also being classified as BWR/3 models.

BWR-4

Browns Ferry Unit 1 drywell and wetwell under construction, within a Mark I containment

• BWR Type 4 (BWR-4, BWR/4): Introduced in 1966, 1100 MW (Browns Ferry 1–3). Largely similar to the BWR/3 in design with an identical recirculation system, but power density was increased by 20%. Available with either Mark I or Mark II containment.

BWR-5

• BWR Type 5 (BWR-5, BWR/5): Introduced in 1969, 1100 MW (LaSalle 1–2). Same number of loops (2) & jet pumps (20), but the jet pumps were upgraded to a five nozzle design. Variable speed pumps were replaced with two-speed pumps (each rated at 35,400 US gallons per minute (2.23 m³/s) for a discharge pressure head of 865 feet (264 m)), and a flow control valve (adjustable from 22% open to 100% open with a linear flow response) was added to each loop for use in regulating recirculation flow (capable of regulating recirculation flow between 35% and 100% with the pumps in the fast speed setting, or between 30% and 40% with the pumps in the slow speed setting). Improved ECCS valve flow control. Only available with Mark II containment.

BWR-6

• BWR Type 6 (BWR-6, BWR/6): Introduced in 1972, available in configurations ranging from 600–1400 MW. Transitioned from 7×7 to 8×8 fuel bundle with longer and thinner fuel rods that fit within the same external footprint as the previous 7×7 fuel bundle, reduced fuel duty (to 13.4 kW/ft (44 kW/m)), improved compact jet pumps with higher circulation capacity (available with 16–24 total jet pumps depending on the configuration), increased capacity of the steam separators and dryers, increased fuel capacity, increased output (20% increase vs. BWR/5 when using the same size pressure vessels), improved ECCS, introduced an option for a compact control room, and introduced a solid-state nuclear system protection system option (only Clinton took this). First and only model available with Mark III containment.

ABWR

• ABWR: Higher safety margins, no external recirculation loops, reactor internal pumps. It also has fine motion control rod drives.

ESBWR

• ESBWR: Passive safety, natural circulation (no loops or pumps), 1600 MW. It has a gravity flooder, isolation condenser, and passive containment cooling.

Fuel Rod Bundles

GE-2

• 7x7 fuel bundle.

GE-3

• Improved 7x7 fuel bundle with 49 fuel rods, one of which is segmented.

GE-4

• 8x8 fuel bundle with 63 fuel rods and 1 water rod.

GE-5

• Retrofit 8x8 fuel bundle Prepressurized and Barrier fuel bundles containing 62 and two water rods.

GE-6 & 7

• Prepressurized at 3 standard atmospheres (300 kPa) with helium with a Barrier

GE-8

• 8x8 fuel bundle with 58 to 62 fuel rods and 2-6 water rods. Prepressurized at 5 standard atmospheres (510 kPa) with helium.

Containment

See also: Boiling water reactor safety systems

Schematic GE BWR inside a Mark I containment.

Mark I

Schematic BWR inside Mark I containment.

A drywell containment building which resembles an inverted lightbulb above the wetwell which is a steel torus containing water.

Mark II

BWR inside a Mark II containment.

Described as an "over-under" configuration with the drywell forming a truncated cone on a concrete slab. Below is a cylindrical suppression chamber made of concrete rather than just sheet metal.

Mark III

The GE Mark III Containment-system is a single barrier pressure containment and multi-barrier fission containment system, consisting of the containment vessel plus associated dry- and wetwell (pressure and fission barriers), the external shield building of it, the auxiliary building and the fuel building, all of which are normally kept at negative pressure which prevents the egress of fission products.

Features of the containment :

• Improved seismic response
• Lower pressure containment design, but significant larger volume than Mark I and II
• Improved pipe whip design
• Combines the dry containment (PWR-type) with the typical BWR-pressure suppression type containment

Advantages

• One advantage of the BWR design (compared to PWR) is improved load-following by virtue of control rod manipulation combined with changing the recirculation flow rate. The integration of the turbine pressure regulator and control system with the recirculation flow control system allows automatic power changes of up to 25% of rated power without altering control rod settings.
• Bottom-entry bottom-mounted control rods allow refueling without removal of the control rods and drives, while also allowing drive testing with an open vessel prior to fuel loading.
• BWR allow lower primary coolant flow than PWR.
• Jet pumps internal to the reactor vessel provide 2/3rds of the recirculation flow, allowing the external recirculation flow loop to be small and compact compared to contemporary PWR designs.
• Under loss of coolant jet pumps provide 10% power similar to boilers.
• BWR designs operate constantly at about half the primary system pressure of PWR designs while producing the same quantity and quality of steam in a compact system: 1020 psi (7 MPa) reactor vessel pressure, and 288 °C temperature for BWR which is lower than 2240 psi (14.4 MPa) and 326 °C for PWR.
• Steam is generated in the reactor pressure vessel in a BWR, whereas it is generated in the steam generator on a second loop in a PWR.
• BWR allows for bulk boiling while PWR doesn't.

Disadvantages

• Steam generated in a BWR contains trace amounts of radioactive materials, as a result, large portions of the Turbine Building are compartmentalized to prevent radiation exposure to workers. PWR Turbine Buildings, on the other hand, are essentially the same as a fossil fuel power plant's Turbine Building with all equipment accessible at all times.

See also

• Nuclear power
• Generation I reactor
• Generation II reactor
• Generation III reactor
• Nuclear safety in the U.S.
• Economics of new nuclear power plants
• Pressurized water reactor
• Reduced moderation water reactor
• Advanced Heavy Water Reactor
• Other Gen III+ designs:
  • AP1000
  • EPR
  • US-APWR
  • ACR
  • VVER-TOI
  • Kerena boiling water reactor