klt-40s reactor plant for the floating cnpp fpu · klt-40s reactor plant for the floating cnpp fpu...
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KLT-40S Reactor Plant for the floating CNPP FPU
VVER RP Chief Designer Yury P. Fadeev
JSC “Afrikantov OKBM”
RUSSIA
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MAIN FIELDS OF OKBM ACTIVITY
MARINE REACTOR PLANTS FOR THE NAVY
MARINE REACTOR PLANTS FOR THE CIVIL FLEET
FAST REACTORS
HIGH-TEMPERATURE GAS-COOLED REACTORS FA
NUCLEAR FUEL HANDLING EQUIPMENT
UNIFIED EQUIPMENT FOR NPP
(PUMPS, FANS)
1945 FOUNDATION OF THE ENTERPRISE
UNIFIED EQUIPMENT FOR NPP
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RP design, manufacture,
complete supply
Upgrade
Author’s supervision during manufacture and operation
Lifetime and service time
extension
JSC “Afrikantov OKBM”
Creation of marine RPs
OKBM has participated in realization of reactor plant (RP) designs for nuclear ships since 1954.
Currently, four generations of RPs have been developed for
the civil nuclear fleet.
1 2 3 4
OK-900
(OK-900A)
OK-150 KLT-40
(KLT-40M, KLT-40S)
Four generations of marine RPs
RITM-200
INTRODUCTION
Disposal
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MARINE RPs
JSC “AFRIKANTOV OKBM” IS THE
CHIEF DESIGNER OF MARINE RPs FOR THE NUCLEAR
ICE-BREAKER FLEET.
9 NUCLEAR ICE-BREAKERS AND THE OCEAN
LIGHTER CARRIER “SEVMORPUT” ARE EQUIPPED
WITH JSC “AFRIKANTOV OKBM” REACTORS.
20 REACTORS WERE FABRICATED AND
OPERATED.
THE RUNNING TIME IS MORE THAN 340
REACTOR-YEARS.
6 NUCLEAR ICE-BREAKERS ARE OPERATED.
THE ACTUAL LIFE TIME OF THE NUCLER ICE-
BREAKER “ARKTIKA” RP IS 177,204 H, THE
SERVICE LIFE IS 34 YEARS.
SERVICE LIFE EXTENSION UP TO 200,000 H FOR NUCLEAR ICE-BREAKER RPs IS ENSURED.
THE WORLD-LARGEST NUCLEAR ICE-
BREAKER “50 LET POBEDY” WITH THE ОК-900А
RP DESIGNED BY JSC “AFRIKANTOV OKBM”
WAS PUT IN COMMISSION ON МARCH 23, 2007
AT MURMANSK OCEAN COMPANY (FSUE
“ATOMFLOT”).
THE FINAL DESIGN OF THE RITM-200 RP FOR
THE UNIVERSAL NEW GENERATION DUAL-
DRAFT NUCLEAR ICE-BREAKER WAS
DEVELOPED.
Since 1954
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REACTORS FOR SMALL AND MEDIUM POWER PLANTS
THERMAL POWER
16 – 54 MW
ELECTRIC POWER
3.5 – 10 MW
Unified reactor plants
featuring integral reactors
and 100% natural circulation
in the primary circuit for
land-based and floating
nuclear power plants
ABV KLT
THERMAL POWER
150 MW
ELECTRIC POWER
38.5 MW
Serial modular reactors for
nuclear icebreakers and sea
vessels
VBER
THERMAL POWER
300 – 1700 MW
ELECTRIC POWER
100 – 600 MW
Modular reactor based on marine
propulsion reactor technologies
for land-based and floating
nuclear power plants
RITM
THERMAL POWER
175 MW
ELECTRIC POWER
36 MW
Integral reactor with forced
circulation in the primary circuit for
the universal nuclear icebreaker
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FLOATING NPPs FOR THERMAL
AND ELECTRIC POWER SUPPLY TO
CUSTOMERS IN THE COASTAL
AREAS.
POWER GENERATION AND WATER
DESALINATION COMPLEXES
POWER SUPPLY TO UNDERWATER
DRILLING PLATFORMS AND TANKERS
AUTONOMOUS POWER SUPPLY TO
OFF-SHORE OIL RIGS
LAND-BASED STATIONS FOR
AUTONOMOUS POWER SUPPLY
TO HARD-TO-REACH AREAS
PURPOSE OF SMALL NUCLEAR POWER SOURCES
ICEBREAKERS, TRANSPORT VESSELS, FISHING FACTORY SHIPS,
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ADVANTAGES OF FLOATING NPPs
MANUFACTURED ON A TURNKEY BASIS
- READY-TO-OPERATE DELIVERY
- HIGH QUALITY MANUFACTURE
SIMPLIFIED SITE SELECTION
DOWN-SIZING OF INDUSTRIAL SITE
REDUCED CONSTRUCTION COST
CONSTRUCTION TIME REDUCED TO 3 YEARS
FULL SERVICE MAINTENANCE AND REPAIR IN EXISTING
SPECIALIZED FACILITIES
“GREEN LAWN” PRINCIPLE IS IMPLEMENTED
RIGHT AFTER COMPLETION OF OPERATION
DEPLOYMENT SITE CAN BE CHANGED
SERIAL PRODUCTION
CAN BE DISPOSED OF IN A SPECIAL FACILITY
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FLOATING NPP BASED ON FPU WITH TWO KLT- 40S RPs
THE DESIGN OF THE SMALL COGENERATION NUCLEAR POWER PLANT (CNPP) IS
PILOT.
THE FPU IS BEING CONSTRUCTED AT THE BALTIYSKY ZAVOD, ST. PETERSBURG, THE
RF.
RP EQUIPMENT SUPPLY IS BEING COMPLETED.
THE NPP STARTUP DATE IS 2013 (THE CITY OF VILYUCHINSK, KAMCHATKA REGION,
THE RF).
SUPPLY TO CONSUMERS IS AS FOLLOWS
ELECTRIC POWER 20…70 MW
HEAT 50…146 Gcal/h
FPU
with KLT-40S
RPs
Small CNPP
SPENT FUEL
AND RADWASTE
STORAGE REACTOR
PLANTS STEAM-TURBINE
PLANTS
UNDERWATER TRENCH
145X45
DEPTH, 9 M
HEAT
POINT DEVICES FOR DISTRIBUTING
AND TRANSFERRING
ELECTRIC POWER TO CONSUMERS
SALT WET
STORAGE CONTAINER
HOT WATER
CONTAINERS
1000 m3 1000 m3
HYDRO ENGINEERING FACILITIES
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MAIN ENGINEERING CHARACTERISTICS OF FPU
LENGTH, m
WIDTH, m
BOARD HEIGHT, m
DRAUGHT, m
140,0
30,0
10,0
5,6
DISPLACEMENT, t
FPU SERVICE LIFE, YEARS
21 000
40
TYPE - SMOOTH-DECK NON-SELF-PROPELLED SHIP
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KLT-40S REACTOR PLANT
THERMAL POWER 150 MW
PRIMARY OPERATIONAL PRESSURE 12.7 MPa
STEAM OUTPUT 240 t/h
STEAM PARAMETERS:
TEMPERATURE 290°С
PRESSURE (abs.), MPa 3.82 MPa
PERIOD OF CONTINUOS WORK 26 000 h
SERVICE LIFE 40 years
SPECIFIED LIFETIME 300 000 h
REFUELING INTERVAL ~ 2.5-3 ys
HEAD CORE LIFETIME OUTPUT 2.1 TW·h
FUEL ENRICHMENT < 20%
РЕАКТОР
CRDM
MAIN CIRCULATION
PUMP
STEAM
GENERATOR
REACTOR
LOCALIZING
VALVES
STEAM
LINES
HYDRAULIC
ACCUMULATOR HYDRAULIC
TANK
EXCHANGER OF i- iii
CIRCUITS
PRESSURIZER
CONTAINMENT INTERNAL PRESSURE
0.4 MPa
CONTAINMENT LEAK TIGHTNESS
volume/day 1%
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EXTERNAL ACTIONS ON THE RP
The RP is designed to withstand the external actions, i.e.
It withstands rolls and tilts in accordance with the requirements of the Russian Maritime Registry of Shipping.
It has the impact resistance of not less than 3 g.
The reactor is shut down, and containment is preserved in case of flood, including in case of turnover.
The PR withstands the crash of an aircraft with the mass of 10 t from the height of 50 m.
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KLT-40S RP FLOW DIAGRAM
PASSIVE
EMERGENCY
SHUTDOWN COOLING
SYSTEM
SYSTEM OF REACTOR
CAISSON FILLING WITH WATER
ACTIVE EMERGENCY CORE
COOLING SYSTEM
ACTIVE SYSTEM OF
LIQUID ABSORBER
INJECTION
PASSIVE EMERGENCY CORE
COOLING SYSTEM (HYDRAULIC
ACCUMULATORS)
PASSIVE SYSTEM OF
EMERGENCY PRESSURE
DECREASE IN THE
CONTAINMENT
(CONDENSATION SYSTEM)
ACTIVE SYSTEM OF
EMERGENCY SHUTDOWN
COOLING THROUGH PROCESS
CONDENSER
PASSIVE SYSTEM OF
EMERGENCY PRESSURE
DECREASE IN THE
CONTAINMENT (BUBBLING
SYSTEM)
RECIRCULATION SYSTEM
PUMPS
NEWLY INTRODUCED
SAFETY SYSTEMS
STEAM
GENERATOR
REACTOR MCP
PRESSURIZER
PSCS
METAL-
WATER
PROTECTION
TANK
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CORE REACTOR AND FA
FA Reactor
KLT-40S Cassette
Fuel rod
6.8 mm
CPS AR
BPR
Cover
Vessel
Block of CG
control rods
Cavity
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CORE REFUELING DIAGRAM
Refueling process safety is
ensured for all possible initial
events, in particular:
- SFA hanging-up during refueling; - SFA container hanging-up during transportation; - SFA and SFA cask falling; - refueling equipment deenergization; - SFA-storage cooling circuit depressurization; - SFA-storage deenergization; etc.
Refueling
compartment
Apparatus
room
Storage tank Dry storage tanks
SFA (spent fuel assembly) transportation from the reactor to the storage tank
FFA (fresh fuel assembly) cassette transportation to the reactor
SFA transportation from the storage tank to the dry storage tank casks
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MAIN CIRCULATION PUMP
Parameter Value
High/low speed supply, m3/h 870/290
Consumed power, kW
155/11
Rotor rotation speed,
synchronous, rpm
3000/1000
Head , m 38/4
Service life, year 20
PUMP TYPE – CANNED, CENTRIFUGAL, SINGLE-STAGE, VERTICAL WITH TWO-SPEED (TWO-WINDING) MOTOR.
RELIABILITY PROVED BY
OPERATION EXPERIENCE OF
MORE THAN 1500 SHIP MCPs;
ELIMINATION OF PRIMARY
CIRCUIT LEAKAGES
ELIMINATION OF EXTERNAL
SYSTEMS OF THE PUMP
AGGREGATE (EXCEPT COOLING):
- lubrication system of radial-axial
bearing and motor;
- water supply system for seal unit;
- system of leakage discharge from
seal.
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STEAM GENERATOR
PRIMARY
CIRCUIT
INLET/OUTLET
STEAM OUTLET FEEDWATER
INLET FEEDWATER
HEADER
STEAM HEADER
SG COVER
ADAPTER
FEEDWATER
TUBES
HEAT-EXCHANGING
TUBES
STEAM GENERATOR TYPE –
VERTICAL RECUPERATIVE HEAT
EXCHANGER WITH COIL HEAT-
EXCHANGING SURFACE OF TITANIUM
ALLOYS AND FORCED CIRCULATION
OF WORKING FLUIDS
MODULAR DESIGN WITH POSSIBILITY
OF FLOW-LINE PRODUCTION
AUTOMATED ON-LINE DETECTION OF
INER-CIRCUIT LEAKAGES BY
SECONDARY CIRCUIT STEAM ACTIVITY
REPAIRABILITY WITHOUT OPENING
PRIMARY CIRYUT CAVITIES
DEPRESSURIZATION CAPACITY AT
PRIMARY CIRCUIT LEAKAGE NOT
MORE THAN Deq.=40 mm
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SAFETY CONCEPT OF KLT-40S RP
The safety concept of the KLT-40S reactor plant is based on modern
defence-in-depth principles combined with developed properties of
reactor plant self-protection and wide use of passive systems and self-
actuating devices
Properties of intrinsic self-protection are intended for power density
self-limitation and reactor self-shutdown, limitation of primary coolant
pressure and temperature, heating rate, primary circuit depressurization
scope and outflow rate, fuel damage scope, maintaining of reactor
vessel integrity in severe accidents and form the image of a “passive
reactor”, resistant for all possible disturbances.
The KLT-40S RP design was developed in conformity with Russian
laws, norms and rules for ship nuclear power plants and safety
principles developed by the world community and reflected in IAEA
recommendations.
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SAFETY LEVELS
1
2
3
4
5
1 – FUEL COMPOSITION
2 – FUEL ELEMENT CLADDING
3 – PRIMARY CIRCUIT
4 – RP CONTAINMENT
5 – PROTECTIVE ENCLOSURE
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SYSTEMS OF REACTOR EMERGENCY SHUTDOWN
1 Reactor
2 CPS drive mechanisms
3 System of liquid absorber injection
4 Electric power circuit-breaker by pressure
Electric power circuit-breakers by pressure provide de-energizing of CPS drive mechanisms (reactor shutdown):
by pressure increase in the primary circuit
by pressure increase in the containment
System of liquid
absorber injection
Electromechanical
system of
reactivity control
4 from CSS
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Reactor Emergency Heat Removal Systems
Hydraulically
operated air
distributors
Opening of
pneumatically-
driven valves of
ECCS passive
channels by
primary circuit
overpressure
(cooldown)
There are two autonomous passive channels for
heat removal from the core.
Duration of operation without water makeup is
-for two channels, 24 h;
- for one channel, 12 h.
1 Reactor
2 Steam generator
3 Main circulation pump
4 Emergency heat removal system
5 Purification and cooling system
6 Process condenser
6
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EMERGENCY CORE COOLING SYSTEMS
1 Reactor
2 Steam generator
3 Main circulation pump
4 ECCS hydroaccumulator
5 ECCS tank
6 Recirculation system
1
2
3
4
5
6
A combination of passive and active core cooling subsystems is utilized in case of PR
depressurization (LOCA).
ECCS tank capacity is 2×10 m3.
GA water volume is 2×4 m3.
The time margin in the passive mode before core drainage starts is approximately 3 h.
4
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SYSTEM OF EMERGENCY PRESSURE DECREASE IN CONTAINMENT
The passive
emergency
pressure decrease
system
(preservation of
safety barrier –
containment)
consists of two
channels.
Operation duration
– 24 h.
At LOCA the steam-
water mixture is
localized within the
containment of the
damaged RP
Conditioning system
blower
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ANALYSIS OF POSTULATED SEVERE ACCIDENT
MELT CONFINEMENT IN KLT-40S RP REACTOR VESSEL
Reactor
caisson
Reactor
vessel
Core melt
Melt volume, m3 - 0.885
Melt surface diameter, m - 1.918
Melt height, m - 0.471
Heat output, MW - 0.79
Results of severe accident
preliminary analysis
Reactor vessel submelting does not
occur
Reliable heat removal is provided from
the outer surface of reactor vessel bottom
Reactor mechanical properties are
maintained at the level sufficient to ensure
load bearing capacity despite appeared
temperature difference
Radiation dose for population in case of
beyond design accident with severe core
damage does not exceed 5 mSv
Cooling water
supply
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ANALYSIS OF HYDROGEN SAFETY IN SEVERE ACCIDENTS
Arrangement of hydrogen recombiners (afterburners) in equipment and reactor compartments of KLT-40S RP
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POPULATION RADIATION DOSE RATE UNDER NORMAL OPERATION CONDITIONS AND
DESIGN-BASIS ACCIDENTS DOES NOT EXCEED 0.01% OF NATURAL RADIATION
BACKGROUND
NO COMPULSORY EVACUATION PLANNING AREA
THE PERFORMED ANALYSIS OF REFUELING COMPLEX AND REFUELING PROCESS OF
NUCLEAR POWER PLANTS OF FLOATING POWER UNIT REACTORS CONSIDERING
ENGINEERING MEANS OF NUCLEAR SAFETY PROVISION SHOWS NO POSSIBILITY OF
NUCLEAR OR RADIATION ACCIDENT OCCURRENCE
1 km
PROTECTIVE ACTION
PLANNING AREA
BUFFER AREA
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Innovation reactor plants based on nuclear shipbuilding
technologies for medium and small -size NPP of the VBER
type, RITM-200 and ABV-6
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GOALS AND PURPOSES OF DEVELOPMENT
CREATION OF A MEDIUM-SIZE REACTOR PLANT ON THE BASIS OF
SHIP NUCLEAR REACTOR INDUSTRY AND A COMPETITIVE POWER
UNIT FOR A REGIONAL SECTOR OF POWER INDUSTRY
SUBSTITUTION OF HEAT POWER PLANTS BY UNITS OF SIMILAR
POWER LEVEL KEEPING POWER GRID STRUTURES
RF REGIONAL POWER INDUSTRY
MORE THAN A HALF OF RF ELECTRICAL POWER SYSTEM OUTPUT IS
GENERATED BY HEAT POWER PLANTS
BASIC FUEL OF HEAT POWER PLANTS – NATURAL GAS, COAL
UNIT CAPACITY OF HEAT POWER PLANT UNITS ~200-300 MW (e)
NUMBER OF UNITS – MORE THAN 450
OTHER APPLICATION AREAS - DISTRICT HEATING, DESALINATION
AND INDUSTRIAL PRODUCTION OF POTABLE WATER
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MAXIMUM USE OF VERIFIED TECHNICAL DECISIONS BASED ON
EXPERIENCE IN MARINE AND VVER REACTOR CONSTRUCTION
TECHNICAL DECISIONS PROVEN BY MARINE NPP OPERATION
MODULAR LAYOUT
CANNED MAIN CIRCULATION PUMPS
ONCE-THROUGH STEAM GENERATOR WITH TITANIUM
TUBE SYSTEM
LEAK-TIGHT PRIMARY CIRCUIT, CLOSED SYSTEM
OF PRIMARY COOLANT PURIFICATION
VVER TECHNOLOGIES
TVSA-BASED CORE AND FUEL CYCLE
BORON CONTROL SYSTEM
WATER CHEMISTRY
RP POWER RANGE BASED ON UNIFIED DECISIONS FOR FOUR-LOOP VBER-300
RP
VBER RP DESIGN CONCEPT
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TARGET REQUIREMENTS FOR VBER POWER UNITS
Target technical parameters of the power units comply with AES-2006 (Generation 3+)
requirements
Requirements Target requirements
1. Duration of head unit construction (from first concrete), months. ≤ 48
2. Design service life of main equipment, year 60
3. Design service life of SG, MCP, CPS drive mechanisms, valves,
year 30
4. Capacity factor (average over service life) 0.9
5. Availability factor average over service life), % 92
6. Periodicity of technical examinations Once every eight years
7. Probability of severe core damage Not more than 10-6 for reactor per year
8. Probability of ultimate accidental release Not more than 10-7 for reactor per year
9. Buffer area Limited by NPP site
10. Protective action planning area Not more than 1 km from site
boundary
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WITH LOOP-TYPE PRESSURIZED-WATER REACTORS
Criterion type Characteristics
Economics
Compactness of equipment and primary circuit systems
Simplification of RP systems
Application of canned MCP
Safety
Exclusion of most dangerous accidents of large and medium leakages at
primary circuit depressurization
Effective localization of steam generator leakages
Decrease of annual collective dose at equipment repair and maintenance
Small power disturbances at steam line breakdown
Serviceability
High maneuverability due to application of one-through SG
Stable water chemistry and gas mode due to leak-tight primary circuit
(no off gases, makeups, reduction of sampling);
High degree of control automation (application of “self-regulation”, one-
through SG, minimization of systems functioning at normal operation –
system of purification and cooling and pressure compensation)
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31 COMPETITIVE ADVANTAGES OF VBER REACTORS AS COMPARED
WITH LOOP-TYPE PRESSURIZED-WATER REACTORS(CONTINUED)
Criterion type Characteristics
Consistency
Application of mastered fuel – FA of unified design based on TVSA
integrating all innovation solutions for fuel use efficiency
Operation experience of analogs >6500 years
Long-term experience of analogs design and fabrication
Usage of previous R&D results
Manufacturability
Factory-assembled modules
Suitability of reactor unit design for application of modular technology
of construction and mounting in combination with installation in the
open
Radwaste
handling
Minimal quantity of liquid radwaste due to absence of leakages and
minimal water exchange during campaign
Flexibility for
market demands
Power range of 100-600 MW (e) based on unified solutions
Possibility to create floating NPP
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POWER RANGE OF VBER RP
N=460 МW(e)
FIVE-LOOP RP
FOUR-LOOP RP
SIX-LOOP RP
N=600 МW(e)
N=250 МW(e)
THREE-LOOP RP
TWO-LOOP RP
N=150 МW(e)
UNIFIED TECHNICAL
SOLUTIONS
N=300 МW(e)
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COMPACTNESS OF VBER RP
VBER-300
VVER-300
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INTERGRATED VESSEL – SCALED
ANALOG OF MARINE REACTOR
VESSEL SYSTEM
Reactor
vessel
Hydrochamber
Two-vessel block
REACTOR MODULE. INTEGRATED VESSEL
Steam generator
vessel
“SCALED FACTOR"
THE VESSEL DID NOT REQUIRE
CHANGE OF PRINCIPLES OF
STATED “MARINE
TECHNOLOGY”
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FUEL ASSEMBLY
STIFFENING
ANGLE
TOP
NOZZLE
SPACING
GRID
BOTTOME
NOZZLE
GUIDE CHANNELS FOR AE
GFE STIFFENING
ANGLE
IN VBER RP CORES THERE ARE USED FAS OF A SKELETON
DESIGN, WITHOUT A WRAPPER, OF A VVER-1000 TVS-A TYPE
WITH PROVED HIGH PERFORMANCE
MAXIMUM BURNUP FRACTION IN FUEL ELEMENTS OF A PILOT
TVSA FOR 6-YEAR OPERATION AT THE 1ST UNIT OF KALININ NPP
WAS 66 MW·DAY/KGU. THE TEST RESULTS ARE POSITIVE
THE USEFUL QUALITIES OF THE FA ARE HIGHLY COMPETITIVE
WITH THOSE OF THE BEST FUEL DEVELOPMENTS FOR PWR
Number of FAs, pcs 85
Average linear load of fuel element, W/cm 98.0
Maximum linear load, W/cm 254
Fuel cycles 3х2 years,
4х1.5 year
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MAIN CIRCULATION ELECTRIC PUMP
Parameter Value
NOMINAL SUPPLY, m3/h 5560
POWER CONSUMPTION, МWt 1.360
SYNCHRONOUS ROTOR SPEED, S-1
(RPM)
50 (3000)
HEAD AT NOMINAL SUPPLY, m 52
MCP DIMENSIONS, mm 3870×1215
MASS OF ELECTRIC PUMP, t 21
SERVICE LIFE, years 30
PUMP TYPE -AXIAL, SINGLE-STAGE, WITH CANNED MOTOR
RELIABILITY PROVED BY OPERATION
EXPERIENCE OF MORE THAN 1500 SHIP MCPs;
ELIMINATION OF PRIMARY CIRCUIT LEAKAGES
ELIMINATION OF EXTERNAL SYSTEMS OF THE
PUMP AGGREGATE (EXCEPT COOLING)
- lubrication system of radial-axial bearing and
motor;
- water supply system for seal unit;
- system of leakage discharge from seal.
Rotor
Magnetic
conductor
of stator
Pump casing
Radial-axial bearing
Radial
bearing Guide vanes
Impeller
Stator cooler
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Parameter Value
NUMBER OF STEAM GENERATING MODULES 55
NUMBER OF HEAT-EXCHANGING TUBES IN
MODULE
90
NUMBER OF HEAT-EXCHANGING TUBES IN SG 4950
DIMENSIONS OF TUBES, mm 10×1.4
TUBE SYSTEM MATERIAL Titanium
alloy
TUBE SYSTEM MASS, t 58.5
SERVICE LIFE, years 30
STEAM GENERATOR TYPE - ONCE-THROUGH, MODULAR, COILED, WHERE SECONDARY FLUID ARRANGED INSIDE TUBES
THE DESIGN WAS IMPROVED AS COMPARED WITH ICE-BREAKER STEAM GENERATORS (FEED WATER SUPPLY ASSEMBLIES AND SG COVER JUNCTIONS WERE OPTIMIZED, NUMBER OF STEEL-TITANIUM ADAPTING PIPES AND WELDS WAS DECREASED, ELECTRON-BEAM WELDING WAS USED)
THE MODULAR DESIGN OF THE STEAM GENERATOR PERMITS ITS SERIES PRODUCTION
TUBE SYSTEM METAL CONDITION IS CONTROLLED BY THE METHOD USING MODULE-WITNESSES IN THE FORM OF REMOVABLE STEAM-GENERATING MODULES
AUTOMATED ON-LINE DETECTION OF INER-CIRCUIT LEAKAGES BY SECONDARY CIRCUIT STEAM ACTIVITY
REPAIRABILITY WITHOUT OPENING PRIMARY CIRYUT CAVITIES
CAPABILITY OF HIGH-MANEUVERABLE MODES
DEPRESSURIZATION DIMENSIONS AT PRIMARY CIRCUIT LEAKAGE NOT MORE THAN DEQ.=40 MM
From
reactor
To
reactor
STEAM GENERATOR
Makeup
water
nozzle Steam nozzle
SG cover
SG module
SG casing
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REFUELING SYSTEM
Refueling
machine
SFA
storage pool
FFA
transportation
container TK-13
or cask
Core
Refueling
machine in the
FAs loading-
unloading
position
REFUELING MACHINE
ENSURES
SFA TRANSPORTATION
IN THE REFUELING TUBE
FILLED WITH WATER
(SIMILAR TO AST-500)
FA EXPRESS
LEAKAGE TEST DURING
REFUELING
ADVANTAGES OF THIS REFUELING
METHOD
ABSENCE OF THE
TRANSPORTATION CORRIDOR
BORATED WATER VOLUMES TO
BE STORED AND PROCESSED
REDUCED by 1500 m3
AUXILIARY EQUIPMENT WITH THE
TOTAL MASS OF ~50 t ELIMINATED
AREA TO BE FACED WITH
STAINLESS STEEL
REDUCED BY ~900 m2
CONSTRUCTION AND
CONSTRUCTION-MOUNTING
ACTIVITIES REDUCED
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TECHNOLOGY OF EQUIPMENT MODULE FABRICATION AND MOUNTING
MODULE TECHNOLOGY:
-“factory-made”
-- increase of fabrication and
mounting quality
- reduction of power unit
construction costs and terms.
MODULES OF PURIFICATION AND
COOLDOWN SYSTEM EQUIPMENT
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VBER-300 REACTOR PLANT CONTAINMENT
Inner metal
containment
- inner pressure of 0.4 MPa;
- leak-tightness of 0.2 % volume/day.
Outer concrete
protective enclosure
- crash of aircraft of 20 t mass;
- air shock wave of 30 kPa;
- leak-tightness of 10% volume/day.
Transportation lock
Main equipment and systems of the
reactor plant are arranged in a
containment of 30 m diameter.
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SAFETY CONCEPTION OF VBER RP
The safety concept of the VBER reactor plant is based on modern
defence-in-depth principles combined with developed properties of
reactor plant self-protection and wide use of passive systems.
Properties of intrinsic self-protection are intended for power density
self-limitation and reactor self-shutdown, limitation of primary coolant
pressure and temperature, heating rate, primary circuit depressurization
scope and outflow rate, fuel damage scope, maintaining of reactor
vessel integrity in severe accidents and form the image of a “passive
reactor”, resistant for all possible disturbances.
The VBER RP design was developed in conformity with Russian laws,
norms and rules for ship nuclear power plants and safety principles
developed by the world community and reflected in IAEA
recommendations.
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SYSTEMS OF REACTOR EMERGENCY SHUTDOWN
System of liquid
absorber injection
Electromechanical
system of reactivity
control
1 Reactor
2 CPS drive mechanisms
3 System of liquid absorber injection
4 From makeup system and boron control system
5 Electric power circuit-breaker by pressure
From makeup system
and boron control
system
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EMERGENCY CORE COOLING SYSTEMS
1 Reactor
2 Steam generator
3 Main circulation pump
4 ECCS first-stage hydraulic accumulator
5 ECCS second-stage hydraulic accumulator
6 Makeup system
7 Recirculation system
1
2
3
4
5
6
7
Passive emergency core
cooling system (24 h)
Recirculation and
repair cooldown
system
Makeup
system
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44
REACTOR EMERGENCY HEAT REMOVAL SYSTEMS
1 Reactor
2 Steam generator
3 Main circulation pump
4 Emergency heat removal system
5 Purification and cooling down system
6 Process condenser
Passive emergency
heat removal system
(72 hrs)
Process condenser
Purification and
cooling down system
6
ОКБМ
45
VNIIEF and OKBM estimated reactor unit strength under
seismic impacts of maximum magnitude 8 as per MSK-64 scale.
Maximum stresses in the nozzle do not exceed 100 MPa (in weld
- 50 MPa) under seismic impact. In view of operation loads, the
total stress is 150 МPa, which is less than the allowable one,
equal to 370 МPa.
POWER UNIT STRENGTH
SEISMIC STABILITY
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46
0 50 100 Stress distribution in the
integrated vessel under seismic
impact, MPa
SEISMIC STABILITY
POWER UNIT STRENGTH
0 5 10 15 20 25 30 35
0
1
2
3
4
5
Пер
егр
узк
а, е
д.g
Частота, Гц
- компонента Х
- компонента Y
- компонента Z
Overloading spectrum
ОКБМ
47
AIRCRAFT CRASH
VNIIEF and OKВM estimated
containment strength in case of
aircraft crash.
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7
-0.4
-0.2
0.0
0.2
0.4
0.6
Пер
егрузк
а, е
д.g
Время, сек
The overloading effecting the power unit attachment points is less than under seismic effect.
POWER UNIT STRENGHT
ОКБМ
48
HYPOTHETICAL ACCIDENT OF GUILLOTINE RUPTURE OF MAIN NOZZLE
SG
Reactor
STRENGTH ANALYSES OF THE
DEVICE PERFORMED BY OKBM
AND VNIIEF SHOW THAT
PRIMARY COOLANT OUTFLOW
DOES NOT EXCEED THE
EQUIVALENT DIAMETER DN =
100 MM
DN < 100 mm Limiting device
ОКБМ
49
POSTULATED SEVERE ACCIDENT ANALYSIS
Combination of design decisions and management measures of two categories:
- aimed at prevention of core damage;
- aimed at limitation of damage rate and consequences of severe accident.
Melt confinement in reactor vessel is the basis for VBER-300 safety concept, that corresponds completely to severe accident management concepts in new generation middle-size RP designs
LIMITATION OF SEVERE ACCIDENT CONSEQUENCIES
Time margin before the core overheating start is 24 h minimum owing to passive ECCS and EHRS operation.
The scenario of core melting under high pressure is eliminated due to passive systems operation.
Favorable conditions for core melt confinement inside the reactor vessel: reduced power density, large time margin before melting start, low thermal fluxes from melt at the bottom.
Special emergency reactor vessel cooling system (reactor cavity filling with water) is provided for.
System for suppression of hydrogen, generating in the course of severe accident, eliminates the possibility of hydrogen detonation in the containment.
Sufficient containment strength margin in view of hydrogen burning.
ОКБМ
SAFETY IN POSTULATED SEVERE ACCIDENT
ОКБМ
50
POSTULATED SEVERE ACCIDENT ANALYSIS
MELT CONFINEMENT IN VBER-300 REACTOR VESSEL
Cooling water
supply
Reactor
caisson
Reactor
vessel
Core melt
Melt volume, m3 - 8.4
Reactor vessel diameter, m - 3.8
Melt height, m - 1.25
Heat output, MW - 4.6
Volume power density, kW/m3 - 548
Average heat flux on bottom (outer surface),
kW/m2 - 135
Melt temperature, °С - 2450
Vessel bottom temperature, °C:
- inner - 1300
- outer - 160
Results of severe accident preliminary analysis
Reactor vessel submelting does not occur
Reliable heat removal is provided from the outer surface of reactor vessel bottom
Reactor mechanical properties are maintained at the level sufficient to ensure load bearing
capacity despite appeared temperature difference
ОКБМ
51
VBER-300 RADIATION SAFETY
The achieved level of VBER-300 RP radiation safety meets the contemporary requirements for the new generation reactors
Industrial site of the
nuclear
cogeneration plant
Buffer area
1 km
Protective Action
Planning Area
Radiation dose for population in case
of beyond design accident with
severe core damage does not exceed
5 mSv
Population dose rate:
- During normal operation – 0.01%
- During maximum design-basis accident - 5%
of natural radiation background
ОКБМ
52
Steam generator (SG) (4 pcs.)
Core
RITM-200 REACTOR PLANT (RP)
RCCP (4 pcs.)
Common SG header
CG drive
(12 pcs.)
CRDM
(6 pcs.)
The intrinsic power consumption and amount of
radwaste generated during operation and
maintenance were minimized.
Thermal power 175 MW
Operational primary circuit pressure 15.7 MPa
Steam capacity 248 t/h
Steam parameters:
Temperature 295 C
Pressure, (abs) 3.82MPa
Continuous operation period 26 000 h
Assigned service life 40 years
Assigned running time 320 000 h
Core generating capacity 7.0 TW·h
Fuel enrichment < 20%
ОКБМ
53 RITM-200 REACTOR PLANT (RP)
Hydraulic accumulator
Steam generator unit (SGU)
Shield tank
RCCP
Pressurizer
Biological shielding
ОКБМ
54 KLT-40S RP AND RITM-200 RP COMPARED
RITM-200 KLT-40S
The RP mass in containment is 1870 t.
The RP dimensions in containment
are 12 х 7.9 х 12 m.
The RP mass in containment is 1100 t.
The RP dimensions in containment
are 6 х 6 х 15.5 m.
ОКБМ
55
REACTOR TYPE INTEGRAL PWR
WITH NATURAL
COOLANT
CIRCULATION
THERMAL POWER, MW 45
OPERATIONAL PRIMARY
PRESSURE, MPa 15.7
STEAM CAPACITY, t/h 55
STEAM PARAMETERS:
Temperature, °C 290
Pressure, MPa 3.14
CONTINUOUS OPERATION, h 16 000
SERVICE LIFE, years 50
REFUELING INTERVAL, years 10
CORE GENERATING CAPACITY, TW·h 3.1
FUEL ENRICHMENT, % < 20
ABV-6M REACTOR PLANT (RP)
REACTOR COVER
UNDER
BIOLOGICAL
SHIELDING
BUILT-IN STEAM
GENERATOR
UNITS PROTECTIVE
TUBE
ASSEMBLY
REACTOR
VESSEL
FAs IN THE
CORE
ОКБМ
56
CRDM
VALVES
PCDS
COOLER
PCDS
PUMP
REACTOR
PRESSURIZE
R
FLOATING CO-GENERATION NPP WITH THE ABV-6M RP
SGA MASS, t
200
LENGTH, m 5
WIDTH, m 3.6
HEIGHT, m 4.5
MAXIMUM LENGTH, m 97…140
BEAM, m 16…21
SIDE HEIGHT, m 10
DRAFT, m 2.5…2.8
DISPLACEMENT, t from 8700
The main RP equipment is
arranged on the shield tank as a
single steam generating aggregate
(SGA)
The aggregate can be shipped by
rail
ОКБМ
57
STATIONARY NPP WITH THE ABV-6M RP
ДЛИНА 67м
ШИРИНА 47м
ВЫСОТА 30 М
TURBO-
GENERATOR 2
REACTOR
MODULE 2
STORAGE
POOL
REACTOR
MODULE 1
TURBO-
GENERATOR
1
ALL STRUCTURES IN THE MAIN BUILDING
ARE DESIGNED TO WITHSTAND SEISMIC
RESISTANCE CATEGORY I LOADS WITH
ACCOUNT OF AN AIRCRAFT CRASH, AIR
SHOCK WAVE AND MAGNITUDE 7
EARTHQUAKE.
REACTOR MODULE MASS 600 t
LENGTH 13 m
DIAMETER 8.5 m
THE LAND-BASED OPTION OF THE ABV-
6M RP IS A SINGLE MODULE
COMPLETELY PREPARED FOR
OPERATION AT THE MANUFACTURER
PLANT
THE STRONG HULL OF THE MODULE
FUNCTIONS AS A CONTAINMENT MODULE BEING
TRANSPORTED TO THE
CONSTRUCTION SITE
LENGTH 67 m
WIDTH 47 m
HEIGHT 30 m
ОКБМ
58
THANK YOU FOR YOUR
ATTENTION