7 th INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCE VVER

7 -th INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCE VVER technology development prospects V. A. Sidorenko RSC “Kurchatov Institute” Moscow, 26 -27 May 2010 1

The nearest target objective: NPP - 2006 М (the same as NPP-2010 and NPP VVER-TOI) The declared program for NPP construction up to 2020 has to be completed with these versions. 2

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Main technical and economic objectives of NPP-2010 1. Availability factor: not less than 93% 2. Power consumption for auxiliaries: not higher than 6, 4% 3. Efficiency (gross): 37, 4% 4. Containment shall be designed for 20 t plane crash (option: 400 t) 5. Surface to be occupied by two Unit plant including circulating cooling water systems: not more than 300 m 2/МW 6. Total structural volumes of two Unit plant buildings and structures: not more than 500 m 3/МW 7. Construction period from first concrete to energetic start-up: not longer than 45 months 4

Reactor Department areas of optimization 1. Reactor thermal power increase up to 3300 3400 МW (th. ) based on conservatism removal 2. Steam generator upgrading (improvement of separation characteristics) 3. Reduction of control rods based on the results of activities already performed 4. Full exclusion of circulating oil systems from the reactor department, implementation of new reactor coolant pumps (development is practically completed) 5. Implementation of new vessel steel 5

Unit-wide modifications 1. 2. 3. 4. 5. Increase in Unit average annual thermal efficiency up to 37, 4% due to optimization of steam turbine plant thermodynamic cycle Implementation of a new line of header-platen type heat-exchange components (LPH, HPH, MSR) Transfer to secondary circuit deaerator-free diagram Development (or application) of low-speed turbine with generator up to 1300 - 1400 МW (e) Increase in Unit maneuvering characteristics due to implementation of heat accumulators, Unit participation in primary, secondary and daily regulation 6

6. Renunciation of using Unit demineralizers and transfer to small-duty Unit demineralizers 7. Use of waste low-temperature heat for heating needs (implementation of heat pumps) 8. Optimization of secondary circuit feed water plant structure including implementation of hydraulic clutches at electric feed water pumps, feed water pump pipelines 9. Optimization of Unit control algorithms 10. Optimization of safety system nomenclature and characteristics (safety system options upon Customer’s request) 7

Medium-term and more distant prospects are focused on new objectives that determine tasks both of evolutionary and innovative development of VVER technology 8

Principal task: forming optimum structure throughout all nuclear fuel cycle - closed fuel cycle build-up; - innovative development of fission reactors; § creation of efficient fast neutron breeders; § increased efficiency of fuel utilization in thermal neutron reactors. 9

Priority place of vessel-type light water reactors, bearers of traditional technology and large experience Major objectives: • more efficient use of uranium • reduction of investment risks • increase in thermodynamic efficiency 10

Considered areas of innovative development • Cooling with subcritical parameter water and possible neutron spectrum regulation • Use of vessel-type reactor technology with subcritical parameter boiling water cooling • Use of supercritical water in direct-flow single-circuit design • Use of supercritical water in double-circuit reactor plant • Steam-water cooling in reactor subcritical pressure region with fast neutron spectrum • Steam cooling in reactor supercritical pressure region with fast neutron spectrum 11

NPP installed electric capacity GW VTGR BR S-VVER-I S-VVER-E NPP-2010 NPP-2006 VVER-1000 VVER-440 RBMK Years Expected nuclear energy mix over the period up to 2050 S-VVER-I – Innovative Super-VVER; S-VVER-E - Evolutionary Super-VVER 12

Premise for review of proposals – possible practical implementation over the period from 2020 to 2025 13

Improved VVER for operation in closed fuel cycle • Natural uranium consumption in open cycle: 130 -135 t/GW(e) with conversion ration 0 f 0, 8 -0, 85 • Spectral regulation • Minimization of parasitic neutron absorption • Fuel burn-up optimization • Increase in thermal efficiency by optimizing steam generator design and increasing steam parameters • Provision of wide operating capabilities (maneuvering, campaign length up to 24 months, load factor higher than 90%) • Reduction of reactor plant loop number, creation of a standard 600 MW (e) loop • Industrial production of Unit modules, construction time reduction down to 3, 5 -4 years • Free Units arrangement by safety conditions • Implementation of improvements not included in NPP-2010 14

Double-loop VVER-1200 15

Reactor design arrangement with neutron spectrum regulation by movable displacers Displacers Fuel elements Displacer channels Thermal/electric capacity, МW Plant efficiency, % Arrangement, number of circuits 3500/1300 33 -34 Loop-type two circuits Reactor inlet/outlet pressure, МPa 16. 2/15. 9 Reactor inlet/outlet temperature, °С 287/328, 7 Core height/diameter (+shields), m 4, 57/3, 4 Vessel dimensions height/diameter, m 22/ 4. 5 Reactor plant design development phase FS Time required to complete R&D and to issue reactor plant engineering design, years 10 Need for pilot plant construction – 16

Single-circuit water-moderated water-cooled boiling reactor with hard neutron spectrum and high nuclear fuel breeding Thermal/electric capacity, MW 3000/ 1035 Plant efficiency, % 33 -34 Arrangement, number of circuits Reactor inlet/outlet pressure, МPа Reactor inlet/outlet temperature, °С Core height/diameter (+shields), m Vessel dimensions height/diameter, m Reactor plant design development phase 1 -circuit 8, 0/7, 3 287/288, 7 2, 4(+1)/ 4. 14(+0. 43) 21/5. 8 Conceptual design Time required to complete R&D and to issue reactor plant engineering design, years 10 Need for pilot plant construction + 17

Single-circuit VVER-SKD with double-inlet core Thermal/electric capacity, MW Plant efficiency, % Arrangement, number of circuits Reactor inlet/outlet pressure, MPa Reactor inlet/outlet temperature, °С Core height/diameter (+shields), m Vessel dimensions height/diameter/thickness, m Reactor plant design development phase 3830/ 1700 44 Loop-type 1 circuit 25/24 290/540 3. 76(+0. 5)/ 3, 37(+0, 5) 15, 0/4, 8/0, 335 Conceptual design Time required to complete R&D and to issue reactor plant engineering design, years * 15 Need for pilot plant construction + 18

Double-circuit integral VVER-SKDI with single-pass core and natural coolant circulation Thermal/electric capacity, MW Plant efficiency, % 1 Reactor 2 SG 3 PRZ 4 Water chemistry 5 Pump 6 Water accumulator 7 Tank 8 Tank 9 Safety vessel Arrangement, number of circuits Reactor inlet/outlet pressure, МP а 1635/670 41 Integral 2 circuits, natural circulation in first circuit 23. 6 Reactor inlet/outlet temperature, °С 375/395 Core height/diameter (+shields ), m (+shields), 4, 2/2, 6 Vessel dimensions height/diameter, m Reactor plant design development phase 10 Bubbler Time required to complete R&D and to issue reactor plant engineering design, years 11 Containment Need for pilot plant construction 23, 5/4, 96 Conceptual design 15 +

Double-circuit fast neutron reactor cooled with steam-water mixture (PVER) Thermal/electric capacity, MW Plant efficiency, % Arrangement, number of circuits Steam generator Electric Turbine generator Core Condenser Jet Reactor RCP pump 1750/650 37, 1 Loop-type 2 circuits Reactor inlet/outlet pressure, МPа 16. 3/16. 0 Reactor inlet/outlet temperature, °С 347/368 Core height/diameter (+shields), m 1. 5(+0. 5)/ 3(+0. 2) Vessel dimensions height/diameter, m 10. 9/4. 25 Reactor plant design development phase Concept. design Time required to complete R&D and to issue reactor plant engineering design, years 10 Need for pilot plant construction + 20 Feedwater pump

Double-circuit fast reactor with steam supercritical pressure coolant (PSKD) Thermal/electric capacity, MW 1470/ 590 Plant efficiency, % 40. 2 Arrangement, number of circuits SCP Steam Loop-type 2 circuits Reactor inlet/outlet pressure, МPа 24. 5/24. 2 Reactor inlet/outlet temperature, °С 388/500 generator Electric Turbine generator Core height/diameter (+shields), m Vessel dimensions height/diameter, m Core Condenser RCP Reactor plant design development phase 1. 5(+0. 5)/ 3(+0. 2) 10. 5/4. 55 Conceptual design Time required to complete R&D and to issue reactor plant engineering design, years 15 Need for pilot plant construction +21 Reactor Feedwater pump

Development status, planned deadlines and implementation phases Reactor option name VVER-E Reactor plant design development phase FS Time required to complete R&D and to issue reactor plant engineering design, years Need for pilot plant construction Possible date of pilot Unit start-up, year Possible date of mass implementation start, year PVER-650 Conceptual design VVER– SKDI PSKD-600 VVER– SKD VK-M Conceptual design 10 10 15 15 15 10 - - + + 2020 2025 2035 2025 2030 2040 2030 22

Assessment of proposals – Prospect of BWR experience use (? ) – Transfer to «fast» neutron spectrum: area of optimum breeder option selection – Transfer to supercritical water pressure: independent promising area 23

Proposed areas for SUPER-VVER development It is proposed to focus on two research and development areas: • area of evolutionary development involving upgrading and improvement of traditional VVER technology • area of innovative development involving transfer to heat removal with supercritical parameter water 24

Phases of evolutionary SUPER-VVER creation • 2009 -2011: draft proposals for innovative core design and establishment of R&D program for NPP with evolutionary SUPER-VVER option; • 2011 -2015: performance of pre-design and basic R&D for NPP with evolutionary SUPER-VVER option (materials, codes, databases, benchmarks, bench base); • 2012 -2016: design of NPP with evolutionary SUPERVVER option (conceptual design, draft proposal, FS, working documentation); • 2016 -2021: construction of pilot NPP with evolutionary SUPER-VVER option 25

Phases of innovative SUPER-VVER creation § 2009 -2011: study of generalized fundamental problems of new generation VVER-SKD, draft proposals for ASSS with innovative SUPER-VVER reactor plant, establishment of requirements and R&D program for NPP with innovative SUPER-VVER option; 2012 -2019: performance of pre-design and basic R&D for NPP with innovative SUPER-VVER option (materials, codes, databases, benchmarks, bench base, experimental investigations); § 2017 -2021: design of NPP with innovative SUPER-VVER option (conceptual design, draft proposal, engineering design, FS, working documentation); § 2022 -2026: construction of pilot NPP with innovative SUPERVVER option. 26

Major R&D areas Ø Neutron-physics calculations and experiments Ø Thermo-hydraulic calculations and experiments Ø Material study-related problems in their integrality Ø Dynamics of processes in nuclear power facility and stability analysis Ø Water preparation Ø New technical solutions, scaled experiments 27

Main work scope for 2 -3 years Performance of basic R&D which will allow: • for evolutionary area: establishing draft proposals for core, reactor plant and NPP design • for innovative area: studying generalized fundamental problems of VVER-SKD creation, selecting NSSS constructiondesign aspects and laying scientific and technical groundwork for transfer to purposeful R&D and specific design 28

UPGRADING VVER Super VVER (STC, April 2010) NPP-2006 NPP-2010 EVOLUTION INNOVATION 29