1 7-th INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCE VVER technology development prospects...

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7-th INTERNATIONAL 7-th INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCESCIENTIFIC AND TECHNICAL CONFERENCE

VVER technology VVER technology

development prospectsdevelopment prospectsV.A.Sidorenko

RSC “Kurchatov Institute”

MoscowMoscow, , 26-27 May 2010

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The nearest target objective:The nearest target objective: NPP - 20NPP - 2006 М06 М

((the same as NPPthe same as NPP-2010-2010 and NPP VVER-TOI and NPP VVER-TOI))

The declared program for NPP construction

up to 2020 has to be completed with these

versions.

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Main technical and economic objectives Main technical and economic objectives of NPP-of NPP-20102010

1. 1. Availability factor: not less than Availability factor: not less than 93%93%2. 2. Power consumption for auxiliaries: not higher than Power consumption for auxiliaries: not higher than

6,4%6,4%3. 3. EfficiencyEfficiency ( (grossgross)): : 37,4%37,4%4. 4. Containment shall be designed for 20 t plane crash Containment shall be designed for 20 t plane crash

(option: (option: 400 400 tt))5. 5. Surface to be occupied by two Unit plant including Surface to be occupied by two Unit plant including

circulating cooling water systems: not more than circulating cooling water systems: not more than 300 300 mm2/М2/МWW

6. 6. Total structural volumes of two Unit plant buildings Total structural volumes of two Unit plant buildings and structures: not more than and structures: not more than 500 500 mm3/М3/МWW

7. 7. Construction period from first concrete to energetic Construction period from first concrete to energetic start-up: not longer than 4start-up: not longer than 45 5 monthsmonths

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Reactor Department areas of optimizationReactor Department areas of optimization

1.1. Reactor thermal power increase up to Reactor thermal power increase up to 3300 - 3300 - 3400 М3400 МWW ( (th.th.) ) based on conservatism removalbased on conservatism removal

2.2. Steam generator upgradingSteam generator upgrading ( (improvement of improvement of separation characteristicsseparation characteristics))

3.3. Reduction of control rods based on the results Reduction of control rods based on the results of activities already performedof activities already performed

4.4. Full exclusion of circulating oil systems from Full exclusion of circulating oil systems from the reactor department, implementation of new the reactor department, implementation of new reactor coolant pumps (development is reactor coolant pumps (development is practically completedpractically completed))

5.5. Implementation of new vessel steelImplementation of new vessel steel

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Unit-wide modificationsUnit-wide modifications

1.1. Increase in Unit average annual thermal efficiency up Increase in Unit average annual thermal efficiency up to to 37,4% 37,4% due to optimization of steam turbine plant due to optimization of steam turbine plant thermodynamic cyclethermodynamic cycle

2.2. Implementation of a new line of header-platen type Implementation of a new line of header-platen type heat-exchange components heat-exchange components ((LPHLPH, , HPHHPH, , MSRMSR))

3.3. Transfer to secondary circuit deaerator-free diagramTransfer to secondary circuit deaerator-free diagram4.4. Development (or application) of low-speed turbine Development (or application) of low-speed turbine

with generator up to with generator up to 1300 - 1400 М1300 - 1400 МWW ( (ee))5.5. Increase in Unit maneuvering characteristics due to Increase in Unit maneuvering characteristics due to

implementation of heat accumulators, Unit implementation of heat accumulators, Unit participation in primary, secondary and daily participation in primary, secondary and daily regulationregulation

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6. 6. Renunciation of using Unit demineralizers and transfer to Renunciation of using Unit demineralizers and transfer to

small-duty Unit demineralizerssmall-duty Unit demineralizers

7. 7. Use of waste low-temperature heat for heating needsUse of waste low-temperature heat for heating needs

((implementation of heat pumpsimplementation of heat pumps))

8. 8. Optimization of secondary circuit feed water plant structure Optimization of secondary circuit feed water plant structure

including implementation of hydraulic clutches at electric including implementation of hydraulic clutches at electric

feed water pumps, feed water pump pipelinesfeed water pumps, feed water pump pipelines

9. 9. Optimization of Unit control algorithmsOptimization of Unit control algorithms

10.10.Optimization of safety system nomenclature and Optimization of safety system nomenclature and

characteristicscharacteristics ( (safety system options upon Customer’s safety system options upon Customer’s

requestrequest) )

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Medium-term and more distant Medium-term and more distant

prospects are focused on new prospects are focused on new

objectives that determine tasks objectives that determine tasks

both of evolutionary and innovative both of evolutionary and innovative

development of VVER technologydevelopment of VVER technology

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Principal task:Principal task: forming forming optimum structure optimum structure throughout all nuclear fuel cyclethroughout 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.

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Priority place of vessel-type light water Priority place of vessel-type light water reactors, bearers of traditional reactors, bearers of traditional

technology and large experiencetechnology and large experience

Major objectives::

• more efficient use of uranium

• reduction of investment risks

• increase in thermodynamic efficiency

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Considered areas of innovative development Considered areas of innovative development

• Cooling with subcritical parameter water and possible neutron Cooling with subcritical parameter water and possible neutron spectrum regulationspectrum regulation

• Use of vessel-type reactor technology with subcritical parameter Use of vessel-type reactor technology with subcritical parameter boiling water coolingboiling water cooling

• Use of supercritical water in direct-flow single-circuit designUse of supercritical water in direct-flow single-circuit design

• Use of supercritical water in double-circuit reactor plantUse of supercritical water in double-circuit reactor plant

• Steam-water cooling in reactor subcritical pressure region with Steam-water cooling in reactor subcritical pressure region with fast neutron spectrumfast neutron spectrum

• Steam cooling in reactor supercritical pressure region with fast Steam cooling in reactor supercritical pressure region with fast neutron spectrumneutron spectrum

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SS--VVERVVER--II – Innovative Super-VVER; SS--VVERVVER--EE - Evolutionary Super-VVER

NP

P in

sta

lled

ele

ctri

c ca

pa

city

Expected nuclear energy mix over the period up to 2050

Years

VTGR

GW

RBMK VVER-440

BR

S-VVER-I

S-VVER-E NPP-2010NPP-2006VVER-1000

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Premise for review of proposalsPremise for review of proposals – –

possible practical implementation possible practical implementation

over the period from over the period from 20202020 to to 20252025

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Improved VVER for operation in closed fuel cycleImproved VVER for operation in closed fuel cycle

• Natural uranium consumption in open cycle: 130-135 t/GW(e) with conversion ration 0f 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

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Double-loop VVERDouble-loop VVER-1200-1200

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Reactor design arrangement with neutron spectrum regulation by

movable displacers

Thermal/electric capacity, МW 3500/1300

Plant efficiency, % 33-34

Arrangement, number of circuits

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

–

Displacers

Displacers

Fuel elements

Displacer channels

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Single-circuit water-moderated water-cooled boiling reactor with hard Single-circuit water-moderated water-cooled boiling reactor with hard neutron spectrum and high nuclear fuel breeding neutron spectrum and high nuclear fuel breeding

Thermal/electric capacity, MW3000/1035

Plant efficiency, % 33-34


1-circuit

Reactor inlet/outlet pressure, МPа

8,0/7,3


287/288,7


2,4(+1)/4.14(+0.43)


21/5.8


Conceptual design


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Need for pilot plant construction +

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Thermal/electric capacity, MW

3830/1700

Plant efficiency, % 44


Loop-type 1 circuit

Reactor inlet/outlet pressure, MPa

25/24


290/540


3.76(+0.5)/3,37(+0,5)

Vessel dimensions height/diameter/thickness, m

15,0/4,8/0,335


Conceptual design

Time required to complete R&D and to issue reactor plant engineering design, years *

15


+

Single-circuit VVER-SKD with double-inlet coreSingle-circuit VVER-SKD with double-inlet core

Double-circuit integral VVERDouble-circuit integral VVER--SKDISKDI with single-pass core and natural with single-pass core and natural coolant circulationcoolant circulation

Thermal/electric capacity, Thermal/electric capacity, MWMW 1635/6701635/670

Plant efficiencyPlant efficiency, %, % 4141

ArrangementArrangement, , number of number of circuitscircuits

IntegralIntegral2 2 circuitscircuits, , natural natural circulation in first circulation in first

circuitcircuit

Reactor inlet/outlet pressureReactor inlet/outlet pressure, , ММPPаа

23.623.6

Reactor inlet/outlet Reactor inlet/outlet temperaturetemperature, °С, °С 375/395375/395

Core height/diameterCore height/diameter (+(+shieldsshields), ), mm

4,2/2,64,2/2,6

Vessel dimensions Vessel dimensions heightheight//diameterdiameter, , mm

23,5/4,9623,5/4,96

Reactor plant design Reactor plant design development phasedevelopment phase Conceptual designConceptual design

Time required to complete Time required to complete R&D and to issue reactor R&D and to issue reactor plant engineering design, plant engineering design, yearsyears

1515

Need for pilot plant Need for pilot plant constructionconstruction ++

1 Reactor

2 SG

3 PRZ

4 Water chemistry

5 Pump

6 Water accumulator

7 Tank

8 Tank

9 Safety vessel

10 Bubbler

11 Containment

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Double-circuit fast neutron reactor cooled with steam-water Double-circuit fast neutron reactor cooled with steam-water mixturemixture ( (PVERPVER))


1750/650

Plant efficiency, % 37,1


Loop-type 2 circuits


16.3/16.0


347/368


1.5(+0.5)/3(+0.2)


10.9/4.25


Concept. design


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Core

Reactor Jet

pump

Steam

generator

RCP

Feedwater pump

Turbine Electric

generator

Condenser

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Double-circuit fast reactor with steam supercritical pressure coolant Double-circuit fast reactor with steam supercritical pressure coolant (PSKD)(PSKD)


1470/590

Plant efficiency, % 40.2


Loop-type 2 circuits


24.5/24.2


388/500


1.5(+0.5)/3(+0.2)


10.5/4.55


Conceptual design


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Core

Reactor

SCP Steam

generator

RCP

Feedwater pump

Turbine Electric

generator

Condenser

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Development status, planned deadlines and implementation Development status, planned deadlines and implementation phasesphases

Reactor option name VVER-E PVER-650 VVER–SKDI

PSKD-600 VVER–SKD

VK-M


FS Concep-tual design

Concep-tual design

Concep-tual design

Concep-tual design

Concep-tual design


10 10 15 15 15 10


- - + + + +

Possible date of pilot Unit start-up, year 2020 2025 2035 2035 2035 2025

Possible date of mass implementation start, year

2025 2030 2040 2040 2040 2030

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Assessment of proposalsAssessment 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

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Proposed areas for SUPER-VVER Proposed areas for SUPER-VVER developmentdevelopment

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

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Phases of evolutionary SUPER-VVER creationPhases 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 SUPER-VVER option (conceptual design, draft proposal, FS, working documentation);

• 2016-2021: construction of pilot NPP with evolutionary SUPER-VVER option

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Phases of innovative SUPER-VVER creationPhases 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 SUPER-VVER option.

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Major R&D areas Major R&D areas

Neutron-physics calculations and experiments

Thermo-hydraulic calculations and experiments

Material study-related problems in their integrality

Dynamics of processes in nuclear power facility and

stability analysis

Water preparation

New technical solutions, scaled experiments

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Main work scope for 2-3 yearsMain 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 construction-design aspects and laying scientific and technical groundwork for transfer to purposeful R&D and specific design

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NPP-2006NPP-2006 NPP-2010NPP-2010

EVOLUTIONEVOLUTION

INNOVATIONINNOVATION

UPGRADING

(STC, April 2010)

1 7-th INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCE VVER technology development prospects...

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