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ABWR Overview

J. Alan Beard
April 13, 2007

Outline
• • • • • • • • BWR Overview Containment Nuclear Steam Supply Engineered Safety Features Digital C&I (separate presentation) Miscellaneous Systems (separate presentation) Safety (Core Damage) (separate presentation) Defense in Depth (Severe Accidents) (separate
presentation)

Copyright © 2007 by GE Energy / Nuclear

2 GE Energy /Nuclear April, 2007

BWR Overview
• Operates under saturated conditions
– Over 40 years of operational experience – Operating Pressure is nominally 7.2 MPa (1040 psia) with saturation temperature ~ 287 °C (550 ºF) – Direct Cycle
» Saturated Steam » Quality at exit is greater than 99.9%
• Higher than most PWRs

– Evolution

Copyright © 2007 by GE Energy / Nuclear

3 GE Energy / NuclearApril, 2007

BWR Overview (cont’d)
• Power is controlled by positioning control rods & varying core flow
– Flow control in ABWR provides rapid power changes – No Boric Acid as moderator

• ABWR* (and ESBWR) are designed for 100% load rejection without reactor Scram
– Standard USA ABWR designed for 33% Bypass – Can operate in “Island Mode” where licensed
*Lungmen
Copyright © 2007 by GEEnergy / Nuclear 4 GE Energy / Nuclear April, 2007

BWR Evolution

Dresden 1

KRB

ABWR

Oyster Creek

Dresden 2
5 GE Energy / Nuclear April, 2007

Copyright © 2007 by GE Energy / Nuclear

ABWR RPV Assembly

Copyright © 2007 by GE Energy / Nuclear

6 GE Energy / Nuclear April, 2007

Pressure Suppression Containment
• Reinforced Concrete Containment Vessel
– Steel LeakageLiner

• Consists of Two Major Elements
– Drywell
» Upper and Lower

– Wetwell
» Suppression pool and airspace

• Inerted with Nitrogen During Operation • Steam released during accident or transient
– Routed to Suppression Pool – Non-condensable gases are transferred to wetwell airspace

Copyright © 2007 by GE Energy / Nuclear

7 GE Energy / Nuclear April, 2007

Primary ContainmentEvolution
MARK I

DRY MARK II

ABWR

MARK III

Copyright © 2007 by GE Energy / Nuclear

8 GE Energy / Nuclear April, 2007

ABWR Reactor Building & Containment
SECONDARY CONTAINMENT BOUNDARY DRYWELL CONNECTING VENT

DRYWELL HEAD

PRIMARY CONTAINMENT VESSEL
D IAPHRAGM FLOOR

UPPER DRYWELL

CLEAN ZONE

SPILLOVER VENT

SUPPRESS. C HAMBER A IRSPACE (WETW ELL)

VACUUMBREAKER LOWER DRYWELL
SU PPRESS. POOL

HORIZ. VENT

THERMAL ACTUATED VALVE PRIMARY CONTAINMENT BOUNDARY

BASEMAT

Note: This drawing is to illustrate the scope and requirements of the design and is not intended to show the final detail.

Copyright © 2007 by GE Energy / Nuclear

9 GE Energy / Nuclear April, 2007

ABWR 3D Cutaway
32 28 29

30

24

19 23 22 25 21 5 18 20 11 2 3 7 89 1 4 26 27 31

10 6 17

Advanced Boiling Water Reactor
1. Reactor Pressure Vessel 2. Reactor Internal Pumps 3. Fine Motion Control Rod Drives 4. Main Steam Isolation Valves 5. Safety/Relief Valves 6. SRV Quenchers 7. Lower Drywell Equipment Platform 8. Horizontal Vents 9. Suppression Pool 10. Lower Drywell Flooder 11. Reinforced Containment Concrete Vessel 12. Hydraulic Control Units 13.Control Rod Drive Hydraulic System Pumps 14. RHR Heat Exchanger 15. RHR Pump 16. HPCF Pump 17. RCIC Steam Turbine and Pump 18. Diesel Generator 19. Standby Gas Treatment Filter and Fans 20. Spent Fuel Storage Pool 21. Refueling Platform 22. Shield Blocks 23. Steam Dryer and Separator Storage Pool 24. Bridge Crane 25. Main Steam Lines 26. Feedwater Lines 27. Main Control Room 28. Turbine Generator29. Moisture Separator Reheater 30. Combustion Turbine Generator 31. Air Compressor and Dryers 32. Switchyard

12 15 13 14

16

Copyright © 2007 by GE Energy / Nuclear

10 GE Energy / Nuclear April, 2007

Advanced Boiling Water Reactor
• Licensed / Certified in 3 Countries
– First Design Certified by NRC under Part 52 – Generation III

• Four operating in Japan • Several more under...
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