1 / 24

Belene NPP Design Features

Belene NPP Design Features. Jordan Georgiev BNPP Manager. 28 - 30 May, 200 8 Riviera Holiday Club, Varna, Bulgaria. Original BNPP Design Advanced Design Features Main Equipment Safety Features Highlights of Evaluation Your Contacts. Content. Original BNPP Design.

todd-roy
Download Presentation

Belene NPP Design Features

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript


  1. Belene NPP Design Features Jordan Georgiev BNPP Manager 28 - 30 May, 2008 Riviera Holiday Club, Varna, Bulgaria

  2. Original BNPP Design Advanced Design Features Main Equipment Safety Features Highlights of Evaluation Your Contacts Content

  3. Original BNPP Design

  4. Original Design Features • Single Wall Containment: • pre-stressed reinforced concrete • leak tight metal liner • DBA and BDBA Conditions: • Pressure – 0.5 MPa • Temperatire – 150 C Reactor Type : WWER 1000/V320 RPV Service Life 40 years Active SS: 3x100% (HP SIS, LP SIS, EFWS, UPS, DG, HVAC, SW) Passive ECCS: 4x50% Features: ISFSPools, IRWST, DSI into RPV, ES/GRS

  5. Advanced Design Features

  6. General Data Reactor type PWR Plant supplier ASE, AREVA NP, Siemens Reactor thermal power 3012 MW Electric output 1060 MW Capacity factor 90 % Design Service Life 60 years

  7. Main Equipment: RCS • Reactor type PWR Russian Design • VVER 1000/V 466 • Reactor thermal power 3012 MW • Service Life 60 years • Loops 4 • Core inlet temperature 291 C • Core outlet temperature 321 C • Coolant pressure 15.7 MPa • Features: • - Direct Safety Injection in RPV • Emergency Steam/Gas • Removal System • Lower core elevation relative • to the cold legs • Larger SG and • Pressurizer volume

  8. Main Equipment: Core FA Type Advansed with bow resistant skeleton FA Number 163 FR Number 312 RCCA Number 121 Fuel material UO2 - Average enrichment 4.361% UO2 - Integrated burnable absorber 5% Gd2O3 Skeleton material - SG and GT Zr Alloy FP burn up 66.6 MWd/kg U FR burn up 61.2 MWd/kg U Average FA burn up 55.0 MWd/kg U

  9. Main Equipment: TG TurbineK-1000-60/3000 Type HP+4xLPSpeed 3000 rev/min Bypass 8*125 kg/s (62% of nom. power) Generator TVV-1000-2UZ Rated output 1111 MVA Voltage 24 kV Frequency 50 Hz

  10. Electrical Systems Main Transformers 2x630 MVA Voltage 24/400 kV Auxiliary Transformers 2x63 MVA Voltage 24/6.3 kV Start up Transformers 2x63 MVA Voltage 110/6.3 kV 4x100% 2x100% 4x100%

  11. Main Equipment: I&C Systems Safety I&C 4x100% Normal Operation I&C 4x100%

  12. Safety Features • Safety Objectives – A two fold strategy: • Enhancement of the prevention level of the defense in • depth safety concept, particularly to reduce significantly • severe accident probability • Mitigation of severe accidents consequences up to • and including core meltdown accidents

  13. Main Safety Systems Double Containment with Ventilation and Filtration Passive Heat Removal System Active ECCS Water Reserves inside the Containment (1910 m3) IRWST – 750 m3 Passive ECCS I – 4x50 m3 Passive ECCS II – 8x120 m3 Active SG Emergency Cooling and Blow down System Passive Fast Boron Injection System under ATWS Melted Core Catcher Large water source in the IRWST, gravity draining into the corium retention area

  14. Containment System • Primary Containment: • pre-stressed reinforced concrete • leak tight metal liner • Secondary Containment: • reinforced concrete • leak tight metal liner • DBA and BDBA Conditions: • Pressure – 0.5 MPa • Temperatire – 210 C • Containment Spray System: • Capacity 4x100% • Hydrogen Mitigation System: • 154 Catalytic recombiners • Maximum hydrogen concentration in the long term – 0.56% • Local peak hydrogen concentration in any time in dry air condition – 1.8%

  15. Severe Accident Management Systems • Passive Heat Removal System • DHRup to 2 % of nominal power • Capacity 4x33% • Natural recirculation driven • Outside air cooling

  16. Severe Accident Management System • Corium retention and cooling System • Capacity 1x100% • Strategy: • prevention of basemat concrete erosion • maintain containment integrity • Measures: • core catcher on basis of a melt retention concept • water cooling from top and bottom • water-supply from external sources provided • Result: • stabilization of melt on defined area • solidification of core melt within 3 to 5 days

  17. Severe Accident Management Systems • Passive Annulus Filtering System • Convection driven by hot air • Purification Efficiency of filter unit • Aerosols – 99.9% • Molecular Iodine – 99.9% • Organic Iodine – 99.0% • Leak Purification Flow – up to 500 kg/h

  18. UCA UJA UKC UKA 2 3 1 4 UCB Protection against External Hazards Reactor building, Fuel building, Safety Systems Building, Main Control Room, Remote Shut down Building - protected against the impact by design The DG Building 1, 2 and 3, 4 - protected against the impact by separation Reinforced Concrete Protection Protection by separation Standard Protection The APC protection approach shall be fulfilled by sufficient thick dimensioned outer building walls, separated from inner structures and other technical measures like physical separation

  19. Release Targets for Design Basis Category 3 and 4 Conditions no action beyond 800 m limited economic impact Criteria for Limited Impact for Design Extended Conditions no Emergency Protection Action /evacuation/ beyond 800 m no Delayed Action /temporary relocation/ beyond 3 km no Long Term Action /permanent resettlement/ beyond 800 m limited economic impact No Emergency Protection Action beyond 800 m No Long Term Action beyond 800 m No Delayed Action beyond 3 km Limited economic impact Criteria for Limited Impact

  20. Highlights of Evaluation V 466 Advanced Design vs V 320 Serial Design Annual Electricity Production Annual Uranium Consumption -24.5% +20% Annual Spent Fuel Generation Current Levelized Electricity Cost -11% -50%

  21. Highlights of Evaluation V 466 Advanced Design vs V 320 Serial Design Core Damage Frequency Early Large Release Frequency 1.5E-07 5.5E-10 1E-05 1E-06

  22. VVER AES 92 Design has successfully passed all the steps of the analysis of compliance vs European Utility Requirements for LWR Plants for 1998-2006 Design Certification • VVER AES 92 Design was certified in April 2007

  23. Belene NPP design is based on proven and advanced technologies Evolutionary approach has been carefully selected: it is considered as the best approach for largepower plants it allows to benefit fully from operating experience it minimizes the risk for investors and operators Belene NPP safety is at the highest level Belene NPP provides efficient and friendly operating and maintenance conditions Belene NPP is designed to achieve high efficiency, high availability and low operating costs Conclusions

  24. Your Contacts

More Related