Saint-Petersburg InstituteSaint-Petersburg Institute
“Atomenergoproekt”“Atomenergoproekt”
((JSCJSC SPAEPSPAEP))
2
Key Features of MIR.1200Key Features of MIR.1200 (AES-2006)(AES-2006)
design and current stage ofdesign and current stag...
3
MIR.1200/AES-2006 DesignDesign
MIR.1200/AES-2006MIR.1200/AES-2006 is abbreviated name of evolving NPPis abbreviated name...
4
Evolutionary Development of NPP Designs
(with VVER reactors)
B - 3 2 0 A E S - 9 1 /9 9
V V E R - 6 4 0
A E S - 2 0 0 6
5
References. Tianwan NPP in China
(AES-91/99 Design)
Units #1 and #2 are
under commercial
operation
since 2007
6
Tianwan NPP Construction
7
Evolutionary Approach BenefitsEvolutionary Approach Benefits
Maximum level of technical solution reference, whichMaximum...
8
Main Technical and Economic Parameters per unit ofMain Technical and Economic Parameters per unit of
MIR.1200/AES-2006 D...
9
Main Technical and Economic Parameters per unit ofMain Technical and Economic Parameters per unit of
MIR.1200/AES-2006 D...
10
Design modes
(normal operation)
Main NPP operation mode is basic operation mode
rated at 100% power;
NPP equipment and ...
11
Main Technical Features ofMain Technical Features of
MIR.1200/AES-2006 DesignMIR.1200/AES-2006 Design
Maximum use of we...
12
Containment
Inner containment is a cylindrical
structure of prestressed reinforced
concrete with hemispherical dome.
In...
13
Hurricanes,
Tornadoes
Fujita Scale
F3 - F4
Earthquakes
0.25 g
Airplane crash
Floods
Outside explosions
30 kPa, 1 sSnow ...
14
Main Features of the MIR.1200/AES-2006 DesignMain Features of the MIR.1200/AES-2006 Design
(in comparison with the refe...
15
Design Layout PrinciplesDesign Layout Principles
Adjacent or neighboring location of the Nuclear Island structures to t...
16
NPP Main Buildings
Reactor Building
Turbine Building
Safety Building
Control Building
Steam Cell
Auxiliary Building
Fue...
17
Major Criterion for Safety Concept SelectionMajor Criterion for Safety Concept Selection
Ensuring compliance to safety ...
18
Safety System Structure and ParametersSafety System Structure and Parameters
Configuration and capacity of the safety s...
19
BDBA Management Systems
Core Catcher;
Hydrogen Removal System (with passive
recombiners);
System of primary loop overpr...
Hydrogen Removal System
21
Core CatcherCore Catcher
Placed in the reactor vault
Reactor vault protected against corium
thermomechanical interactio...
22
Vessel, cassette blocks and service area
MIR.1200MIR.1200 CORE CATCHERCORE CATCHER
Cassette blocks with OPIA filler mat...
23
DISTRIBUTION OF TEMPERATURE IN THE MIR.1200DISTRIBUTION OF TEMPERATURE IN THE MIR.1200
CORE CATHER DURYNG EX-VESSEL STA...
24
PHRS-SG and C-PHRSPHRS-SG and C-PHRS ((SchematicSchematic diagramdiagram))
1
2
3
4
5
6
7
1 – emergency heat removal
tan...
25
Radiation Safety of Population in the event of anRadiation Safety of Population in the event of an
accidentaccident
DBA...
26
Leningrad NPP-2 (Leningrad NPP-2 (AES-2006 Design)
27
LNPP-2 Development StatusLNPP-2 Development Status
PSAR and PSA-1 report have been developed;PSAR and PSA-1 report have...
28
Time Schedule for Unit #1 of LNPP-2Time Schedule for Unit #1 of LNPP-2
2006 2007 2008 2009 2010 2011 2012 2013
Unit 1
B...
29
LNPP-2 Construction
30
General ConclusionsGeneral Conclusions
The MIR.1200/AES-2006 design is result of an
evolution of the NPP designs with V...
31
Thank you for your attention!
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Key Features of MIR.1200 (AES-2006) design and current stage of Leningrad NPP-2 construction

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  • Dear colleges,
    My name is Igor Ivkov. I represent Saint-Petersburg Institute “ATOMENERGOPROEKT”.
  • The following presentation is proposed for your attention:
    Key Features of MIR.1200 Design (AES-2006)
  • AES-2006 is the short name for the modern NPP design based on the Russian designs of VVER-1000 NPP.
    Today this design is being implemented in four units of Leningradskaya NPP-2.
    During development of LNPP-2, the AES-91 design was used as reference.
    Earlier the AES-91 design was implemented in the two power units of Tianwan NPP in China.
  • History of AES-2006 project began from standard Russian NPP VVER-1000 named B-320.
    On its basis project АES91/99 has been developed. Two units based on this project have been constructed in China
    In 2006 we have begun works on the new project which has absorbed in itself all the best that has been made earlier.
    While developing new project we used some technical solutions of another Russian project VVER-640.
    Basically it concerns passive safety systems.
  • As it was said above, the AES-91 design was used as reference during development of AES-2006. It was implemented in two power units of Tianwan NPP in China.
    Next two slides are illustrating Tianwan NPP and its construction.
  • This slide illustrates construction and commissioning of Tianwan NPP
    Construction of hemispheric dome.
    Delivering of equipments.
    Testing of the spray system
  • The benefits of the evolutionary approach are obvious:
    Design timeframe decrease due to no need for lengthy and costly research and development
    Opportunity for gradual implementation of new solutions
  • On the following two slides you can see primary technical and economic parameters of a power unit of LNPP-2.
    These parameters fully comply with the requirements specifications for AES-2006 and LNPP-2.
  • Another technical and economic parameters of a LNPP-2.
    Let me note especially rated seismic loads. They allow to implement this design practically for any site in the world.
  • The basic operating mode of the NPP is work in a base mode on 100 % of capacity;
    The equipment and atomic power station systems possible to work in maneuverable modes with regulation of capacity;
    Regulation of capacity may be in a range of 20-100 % from rated power.
  • The main features of AES-2006 design are following:
    Double containment
    Four trains of active safety systems
    Maximum use of well-proven solutions and equipment
    Special engineering measures for BDBA management (core catcher, H2 recombiners, passive heat removal systems and other).
  • Inner containment is a cylindrical structure of prestressed reinforced concrete with hemispherical dome.
    Inner surface of containment is provided with welded lining.
    Outer containment is a cylindrical structure of reinforced concrete with hemispherical dome.
    All the pipelines penetrating the containment are equipped with localizing valves.
    Design pressure: 0.5 МPa
    Design temperature: 150 С
    Inner containment diameter : 44 m
  • The containment is designed so that to provide protection as from internal (such is Lose Of Coolant Accident included MPA) and from external impacts.
    One of the main safety features of the AES-2006 design is protection against outer impacts including:
    Earthquakes [erskweik]
    Wind loads
    Aircraft crash
    Outside explosions
    Snow loads and icing
    Floods
  • Let us consider the Main Features of the AES-2006 Design
    The most important differences of the AES-2006 design from the Referent NPP are represented on this slide.
    The new solutions pertain [ petein] to introduction of passive BDBA management systems controls, pit-tanks placement inside the containment and other design aspects.
  • Main Design Layout Principles are presented on this slide.
    Some of this is :
    Adjacent or neighboring location of the Nuclear Island structures to the Reactor Building;
    Physical division of the buildings into safety trains with fire barriers
    Decreased utilities network between the structures due to optimization of their relative positions;
    Upgraded plant physical protection due to dispersed placement of back-up equipment in various structures;
    Capabilities of controlling an access control to the Nuclear Island buildings;
    Optimized systems layout for better workflow and lower construction costs
  • Use of the given principles has allowed to design more compact power unit
    The main building of NPP are shown on this slide. You can see placements of reactor building, safety building, steam cell, control building, turbine building and other.
  • The Main Criterion for Choice of safety concept was to ensure fulfillment of safety requirements with providing of increasing marketing potential of the project .
  • In selection of the design safety structure and parameters the configuration and capacity of the referent NPP systems were extensively utilized with necessary adjustments.
    The goal of the modifications was to enhance safety at increased project marketing capacity.
    The necessity for modifications was justified by deterministic and probabilistic analyses.
    The safety solutions incorporated in the design resulted in very good probability parameters.
    These results meet in full modern requirements for perspective [pe:spektive] design of NPPs.
  • The main BDBA Management Systems are listened on this slide.
    Those of them, which are lacking [leking] in the referent NPP design, are marked by yellow color.
  • The main equipment of hydrogen removal system is PARs.
    This slide presented 3d model of containment. Placement of PARs has been marked red.
    Quantity of the equipment and placement was defined according calculation of hydrogen release
    and distribution during DBA and SA.
    On the photo you see real equipment in same room in containment.
  • Another important innovation of the design is a molten core catcher. This device is designed to abate consequences of severe accidents and was originally implemented in the Tainwan NPP design.
    The molten core catcher is positioned in the concrete shaft below the reactor body.
  • This slide shows the design of LNPP-2 CC. You can see the lower plate, tow-layer vessel, cassette blocks and service area.
  • The various severe accident scenarios for ex-vessel stage were modeled for CC justification. This slide shows the results of numerical modeling for one of them - leak Drep 346 mm (representative diameter of leak) from primary circuit accompanied by emergency active systems failure. This scenario was the most disadvantageous of all the scenarios taken for analysis.
    1. You can see the СС temperature condition at different phases ex-vessel stage of severe accident. At the first stage the empty volume on the CC bottom filled by metallic corium.
    2. The second portion of the corium consisting mainly of oxides displaces metal melt moves to the upper layer.
    3. The sacrificial material gradually melts. The density of the oxide layer decreases.
    4. When the density of the melt reduce to a certain value the inversion of the melt occurs.
    5. After the inversion cooling of melt surface with water begins followed by a formation of crusts. The average temperature of melt begins to decrease gradually.
    The accident comes into stage of long-term melt retention and cooling.
  • Schematic diagram of passive heat removal systems is presented on this picture. The systems include
    emergency heat removal tanks with heat-exchangers located inside the tanks and condensers in the upper part of the containment.
  • Some words about radiating safety for population during accidents. The project is developed thus that:
    During DBA:
    Dose incurred by population will not exceed the operational dose limit established for normal NPP operation;
    Radius of sanitary protection area doesn’t exceed 0.8 km.
    During Severe accidents:
    Evacuation of people living (near) in close vicinity to the NPP is excluded;
    Radius of area where protection measures for population are planned doesn’t exceed 3 km.
  • As it was said above, two units of LAES-2 now under construction.
    The NPP location is presented on this slide.
  • This slide demonstrates the current status of the LNPP-2
    PSAR and PSA-1 report have been developed;
    LNPP-2 detailed design is under development;
    Licenses have been obtained from Russian Technical Supervisory Authority for placement of Units #1, #2, #3, #4 and for construction of power Units #1 and #2
    First concrete batch was poured into the foundation of the reactor building of Units #1 and #2 (2008 and 2009);
    Construction works are in progress at the site for Units #1 and #2
  • Time schedule and licensing stages for Unit #1 of LNPP-2 are presented on this slide.
    Today detailed design, FSAR and PSA-2 reports is under development
  • The current stage of the LNPP-2 construction is illustrated on this slide.
    Containment construction
    Cooling stack construction
    Delivering and placement the vessel of core catcher
  • As conclusions let me to establish the following facts:
    The AES-2006 design is a result of an evolutionary development of NPPs with VVER designs and conforms to active Russian and International safety standards.
    The benefits of this evolutionary approach are reduction in design time and cost, easy reference of engineering solutions, enhanced project marketing
    New engineering solutions incorporated in the design provide for upgraded safety parameters and conformance to all requirements specifications.
  • Key Features of MIR.1200 (AES-2006) design and current stage of Leningrad NPP-2 construction

    1. 1. Saint-Petersburg InstituteSaint-Petersburg Institute “Atomenergoproekt”“Atomenergoproekt” ((JSCJSC SPAEPSPAEP))
    2. 2. 2 Key Features of MIR.1200Key Features of MIR.1200 (AES-2006)(AES-2006) design and current stage ofdesign and current stage of Leningrad NPP-2Leningrad NPP-2 constructionconstruction Presented by:Presented by: I. IvkovI. Ivkov Saint Petersburg Institute “Atomenergoproekt”Saint Petersburg Institute “Atomenergoproekt” ((JSCJSC SPbAEPSPbAEP))
    3. 3. 3 MIR.1200/AES-2006 DesignDesign MIR.1200/AES-2006MIR.1200/AES-2006 is abbreviated name of evolving NPPis abbreviated name of evolving NPP design developed on the basis of the VVER-1000 Russiandesign developed on the basis of the VVER-1000 Russian design with gross operation life of 480 reactor-years.design with gross operation life of 480 reactor-years. Now theNow the AES-2006AES-2006 design is being implemented in four Unitsdesign is being implemented in four Units of Leningrad NPP-2of Leningrad NPP-2 (LNPP-2)(LNPP-2).. TheThe AES-91AES-91/99/99 was used as reference during development ofwas used as reference during development of thethe AES-2006AES-2006 design for LNPP-2; this design wasdesign for LNPP-2; this design was implemented in two Units of Tianwan NPP (China).implemented in two Units of Tianwan NPP (China).
    4. 4. 4 Evolutionary Development of NPP Designs (with VVER reactors) B - 3 2 0 A E S - 9 1 /9 9 V V E R - 6 4 0 A E S - 2 0 0 6
    5. 5. 5 References. Tianwan NPP in China (AES-91/99 Design) Units #1 and #2 are under commercial operation since 2007
    6. 6. 6 Tianwan NPP Construction
    7. 7. 7 Evolutionary Approach BenefitsEvolutionary Approach Benefits Maximum level of technical solution reference, whichMaximum level of technical solution reference, which promotes the NPP competitiveness in the Worldpromotes the NPP competitiveness in the World markets.markets. Potential for gradual implementation of new solutionsPotential for gradual implementation of new solutions without significant design re-work.without significant design re-work. No need for lengthy and costly R&D for justificationNo need for lengthy and costly R&D for justification of new technical solutions and licensing of a designof new technical solutions and licensing of a design as a whole.as a whole.
    8. 8. 8 Main Technical and Economic Parameters per unit ofMain Technical and Economic Parameters per unit of MIR.1200/AES-2006 DesignMIR.1200/AES-2006 Design # Parameter and Unit Meaure 1 Installed nominal output per one power unit, MWe 1198 2 Irreplaceable equipment lifetime, years 60 3 Efficiency, % (gross) 37.46 4 Efficiency, % (net) 34.8 5 Own power consumption, % 7.48 6 Installed output utilization factor per Unit 0.9 7 Specific number for operating personnel per two power units on condition of service maintenance, man/MW 0.35 8 Annual average power output from two power units in the base operation mode, mil. KW*h 16364
    9. 9. 9 Main Technical and Economic Parameters per unit ofMain Technical and Economic Parameters per unit of MIR.1200/AES-2006 DesignMIR.1200/AES-2006 Design ((cont’cont’)) # Parameter and Unit Measure 9 Coolant flow through the reactor, cubic meter/h 86000 10 Coolant temperature at the entry to the reactor, C 298.2 11 Coolant temperature at the exit from the reactor, C 328.9 12 Coolant pressure at the entry to the reactor, MPa 16.2 13 Seismic loads: •SSE/OBE, points •SSE/OBE, acceleration 8/7 0.25 g/0.12 g 14 Air-shock wave produced by an outside explosion, KPa 30
    10. 10. 10 Design modes (normal operation) Main NPP operation mode is basic operation mode rated at 100% power; NPP equipment and systems provide for possible NPP operation in power regulation maneuver modes; Load regulation is within a range of 20 -100% Nnom.
    11. 11. 11 Main Technical Features ofMain Technical Features of MIR.1200/AES-2006 DesignMIR.1200/AES-2006 Design Maximum use of well-provenMaximum use of well-proven technical solutions andtechnical solutions and equipmentequipment Double containment Four trains of active safety systems (4x100%, 4x50%) Special engineering measures for BDBA management (core catcher, H2 PARs, PHRS) based mainly on passive principles.
    12. 12. 12 Containment Inner containment is a cylindrical structure of prestressed reinforced concrete with hemispherical dome. Inner surface of containment is provided with welded lining. Outer containment is a cylindrical structure of reinforced concrete with hemispherical dome. All the pipelines penetrating the containment are equipped with localizing valves. Design pressure: 0.5 МPa Design temperature: 150 С Inner containment diameter : 44 m
    13. 13. 13 Hurricanes, Tornadoes Fujita Scale F3 - F4 Earthquakes 0.25 g Airplane crash Floods Outside explosions 30 kPa, 1 sSnow load 4.3 kPa Protection from Outer ImpactsProtection from Outer Impacts
    14. 14. 14 Main Features of the MIR.1200/AES-2006 DesignMain Features of the MIR.1200/AES-2006 Design (in comparison with the referent NPP)(in comparison with the referent NPP) Introduction of passive BDBAIntroduction of passive BDBA management systemsmanagement systems ((PHRS-C and PHRS-SGPHRS-C and PHRS-SG)) Optimized schematic approachesOptimized schematic approaches Borated water storage tanks (pit-tanks)Borated water storage tanks (pit-tanks) placed inside containmentplaced inside containment Enhanced autonomy of the plant fromEnhanced autonomy of the plant from outer power sourcesouter power sources Water cooled generatorWater cooled generator Adjustable and repairable innerAdjustable and repairable inner containment tensioner systemcontainment tensioner system
    15. 15. 15 Design Layout PrinciplesDesign Layout Principles Adjacent or neighboring location of the Nuclear Island structures to theAdjacent or neighboring location of the Nuclear Island structures to the Reactor Building;Reactor Building; Physical division of the buildings into safety trains with fire barriersPhysical division of the buildings into safety trains with fire barriers Decreased utilities network between the structures due to optimization ofDecreased utilities network between the structures due to optimization of their relative positions;their relative positions; Upgraded plant physical protection due to dispersed placement of back-upUpgraded plant physical protection due to dispersed placement of back-up equipment in various structures;equipment in various structures; Capabilities of controlling an access control to the Nuclear IslandCapabilities of controlling an access control to the Nuclear Island buildings;buildings; Optimized systems layout for better workflow and lower constructionOptimized systems layout for better workflow and lower construction costs.costs.
    16. 16. 16 NPP Main Buildings Reactor Building Turbine Building Safety Building Control Building Steam Cell Auxiliary Building Fuel Storage Building
    17. 17. 17 Major Criterion for Safety Concept SelectionMajor Criterion for Safety Concept Selection Ensuring compliance to safety standards with a reasonable margin and unconstrained increasing project marketing potential
    18. 18. 18 Safety System Structure and ParametersSafety System Structure and Parameters Configuration and capacity of the safety systems wereConfiguration and capacity of the safety systems were selected to conform to deterministic and probabilistic criteriaselected to conform to deterministic and probabilistic criteria based on the safety system structure of the standard designbased on the safety system structure of the standard design of NPP with VVER.of NPP with VVER. Configuration and capacity of certain systems underwentConfiguration and capacity of certain systems underwent modification as compared to the reference plant;modification as compared to the reference plant; modifications are aimed at enhancing safety and projectmodifications are aimed at enhancing safety and project attractiveness.attractiveness. MIR-1200MIR-1200//AES-2006 probability parameters:AES-2006 probability parameters: Reactor core meltdown probability isReactor core meltdown probability is 5.5.88*10*10-7-7 1/1/year;year; Total limiting accident release frequency is 2.0*10-8 1/year
    19. 19. 19 BDBA Management Systems Core Catcher; Hydrogen Removal System (with passive recombiners); System of primary loop overpressure protection; Passive Heat Removal System via Steam Generators; Passive Heat Removal System from Containment.
    20. 20. Hydrogen Removal System
    21. 21. 21 Core CatcherCore Catcher Placed in the reactor vault Reactor vault protected against corium thermomechanical interaction Reception and accommodation of solid and liquid corium components Heat transfer from corium to cooling water Molten core subcriticality Decreased hydrogen and radionuclides transfer into the containment
    22. 22. 22 Vessel, cassette blocks and service area MIR.1200MIR.1200 CORE CATCHERCORE CATCHER Cassette blocks with OPIA filler material System of BDBA operation
    23. 23. 23 DISTRIBUTION OF TEMPERATURE IN THE MIR.1200DISTRIBUTION OF TEMPERATURE IN THE MIR.1200 CORE CATHER DURYNG EX-VESSEL STAGE OF BDBACORE CATHER DURYNG EX-VESSEL STAGE OF BDBA (HEFEST-CC calculations)(HEFEST-CC calculations) Break Drep=346 mm accompanied by emergency active systems failure Time=7825 Time=10122 Time=14081 Time=60000
    24. 24. 24 PHRS-SG and C-PHRSPHRS-SG and C-PHRS ((SchematicSchematic diagramdiagram)) 1 2 3 4 5 6 7 1 – emergency heat removal tanks (EHRT) 2 – steam lines 3 – condensate pipelines 4 – PHRS-SG valves 5 – heat exchangers / C-PHRS condensers 6 – steam generators 7 – cutoff valves
    25. 25. 25 Radiation Safety of Population in the event of anRadiation Safety of Population in the event of an accidentaccident DBA:  Dose incurred by population will not exceed the operational dose limit established for normal NPP operation;  Radius of sanitary protection area doesn’t exceed 0.8 km. Severe accidents:  Evacuation of people living in close vicinity to the NPP is excluded;  Radius of area where protection measures for population are planned doesn’t exceed 3 km.
    26. 26. 26 Leningrad NPP-2 (Leningrad NPP-2 (AES-2006 Design)
    27. 27. 27 LNPP-2 Development StatusLNPP-2 Development Status PSAR and PSA-1 report have been developed;PSAR and PSA-1 report have been developed; LNPP-2 detailed design is under development;LNPP-2 detailed design is under development; Licenses have been obtained from Russian TechnicalLicenses have been obtained from Russian Technical Supervisory Authority for placement of Units #1, #2, #3, #4Supervisory Authority for placement of Units #1, #2, #3, #4 and for construction of power Units #1 and #2and for construction of power Units #1 and #2 First concrete batch was poured into the foundation of theFirst concrete batch was poured into the foundation of the reactor building of Units #1 and #2 (2008 and 2009);reactor building of Units #1 and #2 (2008 and 2009); Construction works are in progress at the site for Units #1Construction works are in progress at the site for Units #1 and #2and #2
    28. 28. 28 Time Schedule for Unit #1 of LNPP-2Time Schedule for Unit #1 of LNPP-2 2006 2007 2008 2009 2010 2011 2012 2013 Unit 1 Basic Design Detailled Design Commissioning License for Construction License for Operation License for Deployment
    29. 29. 29 LNPP-2 Construction
    30. 30. 30 General ConclusionsGeneral Conclusions The MIR.1200/AES-2006 design is result of an evolution of the NPP designs with VVER reactors. This design conforms to all current Russian and International safety standards and the IAEA requirements. The benefits of this evolutionary approach are reduction in design time and cost, reference for applied engineering approaches, enhanced project attractiveness. The constructing units #1 and #2 of Leningrad NPP-2 in Russia are leading units of this design.
    31. 31. 31 Thank you for your attention!

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