1. Saint-Petersburg InstituteSaint-Petersburg Institute
“Atomenergoproekt”“Atomenergoproekt”
((JSCJSC SPAEPSPAEP))

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
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
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
References. Tianwan NPP in China
(AES-91/99 Design)
Units #1 and #2 are
under commercial
operation
since 2007

6. 6
Tianwan NPP Construction

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
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
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
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
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
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
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
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
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
NPP Main Buildings
Reactor Building
Turbine Building
Safety Building
Control Building
Steam Cell
Auxiliary Building
Fuel Storage Building

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
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
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. Hydrogen Removal System

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
Vessel, cassette blocks and service area
MIR.1200MIR.1200 CORE CATCHERCORE CATCHER
Cassette blocks with OPIA filler material
System of BDBA operation

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
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
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
Leningrad NPP-2 (Leningrad NPP-2 (AES-2006 Design)

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
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
LNPP-2 Construction

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.

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Thank you for your attention!