Transcript НТС РОСАТОМА Секция 1

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
3
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
m2/МW
6. Total structural volumes of two Unit plant buildings
and structures: not more than 500 m3/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 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
14
Double-loop VVER-1200
15
Reactor design arrangement
with neutron spectrum
regulation by movable
displacers
Displacers
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
Displacers
Fuel elements
Displacer channels
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, %
Arrangement, number of
circuits
1635/670
41
Integral
2 circuits, natural
circulation in first
circuit
1
Reactor
2
SG
3
PRZ
Reactor inlet/outlet pressure,
МPа
4
Water chemistry
Reactor inlet/outlet
temperature, °С
375/395
5
Pump
6
Water
accumulator
Core height/diameter
(+shields), m
4,2/2,6
7
Tank
8
Tank
9
Safety vessel
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
23.6
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
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
+
RCP
pump
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
10
10
15
15
15
10
-
-
+
+
+
+
2020
2025
2035
2035
2035
2025
2025
2030
2040
2040
2040
2030
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
Conceptual
design
PSKD-600
Conceptual
design
VVER–
SKD
VK-M
Conceptual
design
Conceptual
design
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
SUPER-VVER option
evolutionary
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
 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
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
NPP-2006
NPP-2010
EVOLUTION
(STC,
April
2010)
INNOVATION
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