1
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
1945 FOUNDATION OF THE ENTERPRISE
MARINE REACTOR PLANTS FOR THE NAVY
FA
HIGH-TEMPERATURE GAS-COOLED REACTORS
MARINE REACTOR PLANTS FOR THE CIVIL FLEET
FAST REACTORS
UNIFIED EQUIPMENT FOR NPP
(PUMPS, FANS)
NUCLEAR FUEL HANDLING EQUIPMENT
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INTRODUCTION
OKBM has participated in realization of reactor plant (RP) designs for nuclear ships since 1954.
JSC “Afrikantov OKBM”
RP design, manufacture,
complete supply
Creation of marine RPs
Upgrade
Author’s supervision during
manufacture and operation
Lifetime and service time
extension
Disposal
Currently, four generations of RPs have been developed for
the civil nuclear fleet.
Four generations of marine RPs
2
1
OK-150
OK-900
(OK-900A)
4
3
KLT-40
(KLT-40M, KLT-40S)
RITM-200
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MARINE RPs
Since 1954
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
OPERATED.
WERE
FABRICATED
AND
 THE RUNNING TIME IS MORE THAN 340
REACTOR-YEARS.

6 NUCLEAR ICE-BREAKERS ARE OPERATED.
 THE ACTUAL LIFE TIME OF THE NUCLER ICEBREAKER “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 ICEBREAKER “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 DUALDRAFT
NUCLEAR
ICE-BREAKER
WAS
DEVELOPED.
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REACTORS FOR SMALL AND MEDIUM POWER PLANTS
ABV
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
KLT
THERMAL POWER
150 MW
ELECTRIC POWER
38.5 MW
Serial modular reactors for
nuclear icebreakers and sea
vessels
RITM
THERMAL POWER
175 MW
ELECTRIC POWER
36 MW
Integral reactor with forced
circulation in the primary circuit for
the universal nuclear icebreaker
5
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
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PURPOSE OF SMALL NUCLEAR POWER SOURCES
ICEBREAKERS,
FLOATING NPPs FOR THERMAL
AND ELECTRIC POWER SUPPLY TO
CUSTOMERS IN THE COASTAL
AREAS.
POWER GENERATION AND WATER
DESALINATION COMPLEXES
AUTONOMOUS POWER SUPPLY TO
OFF-SHORE OIL RIGS
TRANSPORT VESSELS, FISHING FACTORY SHIPS,
LAND-BASED STATIONS FOR
AUTONOMOUS POWER SUPPLY
TO HARD-TO-REACH AREAS
POWER SUPPLY TO UNDERWATER
DRILLING PLATFORMS AND TANKERS
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ADVANTAGES OF FLOATING NPPs
MANUFACTURED ON A TURNKEY BASIS
- READY-TO-OPERATE DELIVERY
- HIGH QUALITY MANUFACTURE
FULL SERVICE MAINTENANCE AND REPAIR IN EXISTING
SPECIALIZED FACILITIES
CONSTRUCTION TIME REDUCED TO 3 YEARS
SERIAL PRODUCTION
REDUCED CONSTRUCTION COST
SIMPLIFIED SITE SELECTION
DOWN-SIZING OF INDUSTRIAL SITE
DEPLOYMENT SITE CAN BE CHANGED
CAN BE DISPOSED OF IN A SPECIAL FACILITY
“GREEN LAWN” PRINCIPLE IS IMPLEMENTED
RIGHT AFTER COMPLETION OF OPERATION
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FLOATING NPP BASED ON FPU WITH TWO KLT- 40S RPs
8
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
UNDERWATER TRENCH
145X45
DEPTH, 9 M
SPENT FUEL
AND RADWASTE
STORAGE
REACTOR
PLANTS
STEAM-TURBINE
PLANTS
HYDRO ENGINEERING FACILITIES
HEAT
POINT
DEVICES FOR DISTRIBUTING
AND TRANSFERRING
ELECTRIC POWER TO CONSUMERS
1000 m3
1000 m3
HOT WATER
CONTAINERS
SALT WET
STORAGE CONTAINER
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MAIN ENGINEERING CHARACTERISTICS OF FPU
9
TYPE - SMOOTH-DECK NON-SELF-PROPELLED SHIP
LENGTH, m
WIDTH, m
BOARD HEIGHT, m
DRAUGHT, m
DISPLACEMENT, t
FPU SERVICE LIFE, YEARS
140,0
30,0
10,0
5,6
21 000
40
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KLT-40S REACTOR PLANT
LOCALIZING
VALVES
 THERMAL POWER
STEAM
LINES
150 MW
 PRIMARY OPERATIONAL PRESSURE 12.7 MPa
 STEAM OUTPUT
240 t/h
CRDM
 STEAM PARAMETERS:
MAIN CIRCULATION
PUMP
STEAM
GENERATOR
РЕАКТОР
REACTOR
EXCHANGER OF i- iii
CIRCUITS
HYDRAULIC
TANK
HYDRAULIC
ACCUMULATOR
 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%
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 SYSTEM OF
EMERGENCY PRESSURE
DECREASE IN THE
CONTAINMENT
(CONDENSATION SYSTEM)
PASSIVE EMERGENCY CORE
COOLING SYSTEM (HYDRAULIC
ACCUMULATORS)
PSCS
ACTIVE SYSTEM OF
LIQUID ABSORBER
INJECTION
PASSIVE
EMERGENCY
SHUTDOWN COOLING
SYSTEM
ACTIVE EMERGENCY CORE
COOLING SYSTEM
REACTOR
MCP
ACTIVE SYSTEM OF
EMERGENCY SHUTDOWN
COOLING THROUGH PROCESS
CONDENSER
RECIRCULATION SYSTEM
PUMPS
STEAM
GENERATOR
PASSIVE SYSTEM OF
EMERGENCY PRESSURE
DECREASE IN THE
CONTAINMENT (BUBBLING
SYSTEM)
SYSTEM OF REACTOR
CAISSON FILLING WITH WATER
METALWATER
PROTECTION
TANK
PRESSURIZER
NEWLY INTRODUCED
SAFETY SYSTEMS
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CORE REACTOR AND FA
Reactor
FA
CPS AR
Cover
Vessel
Fuel rod
6.8 mm
Block of CG
control rods
BPR
KLT-40S Cassette
Cavity
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CORE REFUELING DIAGRAM
Refueling process safety is
ensured for all possible initial
events, in particular:
- SFA hanging-up
refueling;
Refueling
compartment
during
- SFA container hanging-up
during transportation;
- SFA and SFA cask falling;
Apparatus
room
refueling
deenergization;
equipment
- SFA-storage cooling circuit
depressurization;
- SFA-storage deenergization;
etc.
Dry storage tanks
Storage tank
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
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.
Parameter
High/low speed supply, m3/h
Value
870/290
Consumed power, kW
155/11
Rotor rotation speed,
synchronous, rpm
Head , m
Service life, year
3000/1000
38/4
20
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STEAM GENERATOR
STEAM OUTLET
 STEAM GENERATOR TYPE –
VERTICAL RECUPERATIVE HEAT
FEEDWATER
EXCHANGER WITH COIL HEATHEADER
EXCHANGING SURFACE OF TITANIUM
STEAM HEADER
ALLOYS AND FORCED CIRCULATION
OF WORKING FLUIDS
SG COVER
 MODULAR DESIGN WITH POSSIBILITY
ADAPTER
OF FLOW-LINE PRODUCTION
FEEDWATER
 AUTOMATED ON-LINE DETECTION OF
TUBES
INER-CIRCUIT LEAKAGES BY
SECONDARY CIRCUIT STEAM ACTIVITY
 REPAIRABILITY WITHOUT OPENING
PRIMARY CIRYUT CAVITIES
 DEPRESSURIZATION CAPACITY AT
PRIMARY CIRCUIT LEAKAGE NOT
PRIMARY
MORE THAN Deq.=40 mm
CIRCUIT
16
FEEDWATER
INLET
INLET/OUTLET
HEAT-EXCHANGING
TUBES
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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 selfactuating 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
5
4
3
1
1 – FUEL COMPOSITION
2 – FUEL ELEMENT CLADDING
3 – PRIMARY CIRCUIT
4 – RP CONTAINMENT
5 – PROTECTIVE ENCLOSURE
2
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SYSTEMS OF REACTOR EMERGENCY SHUTDOWN
4
19
from CSS
System of liquid
absorber injection
Electromechanical
system of
reactivity control
1 Reactor
2 CPS drive mechanisms
3 System of liquid absorber injection
4 Electric power circuit-breaker by pressure
 Electric power circuitbreakers by pressure provide
de-energizing of CPS drive
mechanisms (reactor
shutdown):
 by pressure increase in the
primary circuit
 by pressure increase in the
containment
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Reactor Emergency Heat Removal Systems
1 Reactor
2 Steam generator
3 Main circulation pump
4 Emergency heat removal system
5 Purification and cooling system
6 Process condenser
6
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.
Hydraulically
operated air
distributors
Opening of
pneumaticallydriven valves of
ECCS passive
channels by
primary circuit
overpressure
(cooldown)
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EMERGENCY CORE COOLING SYSTEMS
4
1 Reactor
2 Steam generator
3 Main circulation pump
4 ECCS hydroaccumulator
5 ECCS tank
6 Recirculation system
4
5
3
6
2
1
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.
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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 steamwater 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
Melt volume, m3
Melt surface diameter, m
Melt height, m
Heat output, MW
Reactor
vessel
- 0.885
- 1.918
- 0.471
- 0.79
Results of severe accident
preliminary analysis
Core melt
 Reactor vessel submelting does not
occur
Reactor
caisson
 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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RADIATION AND ENVIRONMENTAL SAFETY
PROTECTIVE ACTION
PLANNING AREA
BUFFER AREA
1 km
 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
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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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VBER RP DESIGN CONCEPT
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
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TARGET REQUIREMENTS FOR VBER POWER UNITS
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Target technical parameters of the power units comply with AES-2006 (Generation 3+)
requirements
Requirements
1. Duration of head unit construction (from first concrete), months.
Target requirements
≤ 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
10. Protective action planning area
Limited by NPP site
Not more than 1 km from site
boundary
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COMPETITIVE ADVANTAGES OF VBER REACTORS AS COMPARED
WITH LOOP-TYPE PRESSURIZED-WATER REACTORS
Criterion type
30
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”, onethrough SG, minimization of systems functioning at normal operation –
system of purification and cooling and pressure compensation)
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COMPETITIVE ADVANTAGES OF VBER REACTORS AS COMPARED
WITH LOOP-TYPE PRESSURIZED-WATER REACTORS(CONTINUED)
Criterion type
31
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
THREE-LOOP RP
N=250 МW(e)
FIVE-LOOP RP
FOUR-LOOP RP
N=460 МW(e)
N=300 МW(e)
TWO-LOOP RP
SIX-LOOP RP
N=150 МW(e)
N=600 МW(e)
UNIFIED TECHNICAL
SOLUTIONS
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COMPACTNESS OF VBER RP
VVER-300
VBER-300
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REACTOR MODULE. INTEGRATED VESSEL
Steam generator
vessel
INTERGRATED VESSEL – SCALED
ANALOG OF MARINE REACTOR
VESSEL SYSTEM
Hydrochamber
“SCALED FACTOR"
Reactor
vessel
THE VESSEL DID NOT REQUIRE
CHANGE OF PRINCIPLES OF
STATED “MARINE
TECHNOLOGY”
Two-vessel block
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FUEL ASSEMBLY
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
TOP
NOZZLE
SPACING
GRID
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
STIFFENING
ANGLE
GFE
GUIDE CHANNELS FOR AE
STIFFENING
ANGLE
Number of FAs, pcs
Average linear load of fuel element, W/cm
98.0
Maximum linear load, W/cm
254
Fuel cycles
BOTTOME
NOZZLE
85
3х2 years,
4х1.5 year
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MAIN CIRCULATION ELECTRIC PUMP
Radial-axial bearing
Magnetic
conductor
of stator
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)
Pump casing
Stator cooler
Rotor
- lubrication system of radial-axial bearing and
motor;
- water supply system for seal unit;
- system of leakage discharge from seal.
Parameter
Value
NOMINAL SUPPLY, m3/h
5560
POWER CONSUMPTION, МWt
1.360
SYNCHRONOUS ROTOR SPEED, S-1
(RPM)
Radial
bearing
Impeller
HEAD AT NOMINAL SUPPLY, m
Guide vanes
MCP DIMENSIONS, mm
50 (3000)
52
3870×1215
MASS OF ELECTRIC PUMP, t
21
SERVICE LIFE, years
30
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STEAM GENERATOR
Steam nozzle
SG cover
Makeup
water
nozzle
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
Parameter
SG module
From
reactor
NUMBER OF STEAM GENERATING MODULES
55
NUMBER OF HEAT-EXCHANGING TUBES IN
MODULE
90
NUMBER OF HEAT-EXCHANGING TUBES IN SG
To
reactor
DIMENSIONS OF TUBES, mm
TUBE SYSTEM MATERIAL
TUBE SYSTEM MASS, t
SG casing
Value
SERVICE LIFE, years
4950
10×1.4
Titanium
alloy
58.5
30
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REFUELING SYSTEM
Refueling
machine
38
REFUELING MACHINE
ENSURES
Refueling
machine in the
FAs loadingunloading
position
SFA
storage pool
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
BE STORED AND PROCESSED
REDUCED by 1500 m3
FFA
transportation
container TK-13
or cask
TO
AUXILIARY EQUIPMENT WITH THE
TOTAL MASS OF ~50 t
ELIMINATED
AREA TO BE FACED WITH
STAINLESS STEEL
REDUCED BY ~900 m2
Core
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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40
VBER-300 REACTOR PLANT CONTAINMENT
Outer concrete
protective enclosure
- crash of aircraft of 20 t mass;
- air shock wave of 30 kPa;
- leak-tightness of 10% volume/day.
Inner metal
containment
- inner pressure of 0.4 MPa;
- leak-tightness of 0.2 % volume/day.
Main equipment and systems of the
reactor plant are arranged in a
containment of 30 m diameter.
Transportation lock
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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.
ОКБМ
42
SYSTEMS OF REACTOR EMERGENCY SHUTDOWN
System of liquid
absorber injection
From makeup system
and boron control
system
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
ОКБМ
43
EMERGENCY CORE COOLING SYSTEMS
Passive emergency core
cooling system (24 h)
Makeup
system
4
5
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
6
3
2
7
1
Recirculation and
repair cooldown
system
ОКБМ
44
REACTOR EMERGENCY HEAT REMOVAL SYSTEMS
Passive emergency
heat removal system
(72 hrs)
1 Reactor
2 Steam generator
3 Main circulation pump
4 Emergency heat removal system
5 Purification and cooling down system
6 Process condenser
6
Purification and
cooling down system
Process condenser
ОКБМ
45
POWER UNIT STRENGTH
SEISMIC STABILITY
 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.
ОКБМ
46
POWER UNIT STRENGTH
SEISMIC STABILITY
- компонента Х
- компонента Y
- компонента Z
5
Перегрузка, ед.g
4
3
2
1
0
0
5
10
15
20
25
30
35
Частота, Гц
Overloading spectrum
0
50
100
Stress distribution in the
integrated vessel under seismic
impact, MPa
ОКБМ
47
POWER UNIT STRENGHT
AIRCRAFT CRASH
VNIIEF and OKВM estimated
containment strength in case of
aircraft crash.
0.6
Перегрузка, ед.g
0.4
0.2
0.0
-0.2
-0.4
0.0
0.1
0.2
0.3
0.4
0.5
0.6
0.7
The
overloading
effecting
the
power
unit
attachment
points is less
than
under
seismic effect.
Время, сек
ОКБМ
48
HYPOTHETICAL ACCIDENT OF GUILLOTINE RUPTURE OF MAIN NOZZLE
Limiting device
DN < 100 mm
SG
STRENGTH ANALYSES OF THE
DEVICE PERFORMED BY OKBM
AND VNIIEF SHOW THAT
PRIMARY COOLANT OUTFLOW
DOES NOT EXCEED THE
EQUIVALENT DIAMETER DN =
100 MM
Reactor
ОКБМ
49
POSTULATED SEVERE ACCIDENT ANALYSIS
SAFETY IN POSTULATED SEVERE ACCIDENT
 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
POSTULATED SEVERE ACCIDENT ANALYSIS
50
MELT CONFINEMENT IN VBER-300 REACTOR VESSEL
Cooling water
supply
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
3
Volume power density, kW/m
- 548
Average heat flux on bottom (outer surface),
kW/m2
- 135
Melt temperature, °С
- 2450
Vessel bottom temperature, °C:
- inner
- 1300
- outer
- 160
Reactor
caisson
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
Buffer area
Protective Action
Planning Area
1 km
Industrial site of the
nuclear
cogeneration plant
Population dose rate:
- During normal operation – 0.01%
- During maximum design-basis accident - 5%
of natural radiation background
Radiation dose for population in case
of beyond design accident with
severe core damage does not exceed
5 mSv
The achieved level of VBER-300 RP radiation safety meets the contemporary
requirements for the new generation reactors
ОКБМ
52
RITM-200 REACTOR PLANT (RP)
CRDM
(6 pcs.)
CG drive
(12 pcs.)
Common SG
header
Steam
generator (SG)
(4 pcs.)
Thermal power
Operational primary
circuit pressure
Steam capacity
Steam parameters:
Temperature
Pressure, (abs)
Continuous operation period
Assigned service life
Assigned running time
Core generating capacity
Fuel enrichment
175 MW
15.7 MPa
248 t/h
295 C
3.82MPa
26 000 h
40 years
320 000 h
7.0 TW·h
< 20%
RCCP
(4 pcs.)
Core
The intrinsic power consumption and amount of
radwaste generated during operation and
maintenance were minimized.
ОКБМ
RITM-200 REACTOR PLANT (RP)
53
Steam generator unit
(SGU)
Biological
shielding
RCCP
Hydraulic accumulator
Shield
tank
Pressurizer
ОКБМ
KLT-40S RP AND RITM-200 RP COMPARED
KLT-40S
The RP mass in containment is 1870 t.
The RP dimensions in containment
are 12 х 7.9 х 12 m.
54
RITM-200
The RP mass in containment is 1100 t.
The RP dimensions in containment
are 6 х 6 х 15.5 m.
ОКБМ
55
ABV-6M REACTOR PLANT (RP)
REACTOR COVER
UNDER
BIOLOGICAL
SHIELDING
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
Pressure, MPa
PROTECTIVE
TUBE
ASSEMBLY
BUILT-IN STEAM
GENERATOR
UNITS
REACTOR
VESSEL
CONTINUOUS OPERATION, h
290
3.14
16 000
SERVICE LIFE, years
50
REFUELING INTERVAL, years
10
CORE GENERATING CAPACITY, TW·h
3.1
FUEL ENRICHMENT, %
< 20
FAs IN THE
CORE
ОКБМ
FLOATING CO-GENERATION NPP WITH THE ABV-6M RP
56
The main RP equipment is
arranged on the shield tank as a
single steam generating aggregate
(SGA)
CRDM
VALVES
PCDS
PUMP
The aggregate can be shipped by
rail
PCDS
COOLER
REACTOR
SGA MASS, t
200
LENGTH, m
WIDTH, m
HEIGHT, m
PRESSURIZE
R
5
3.6
4.5
MAXIMUM LENGTH, m
BEAM, m
SIDE HEIGHT, m
DRAFT, m
DISPLACEMENT, t
97…140
16…21
10
2.5…2.8
from 8700
ОКБМ
57
STATIONARY NPP WITH THE ABV-6M RP
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.
LENGTH
ДЛИНА 67
67м
m
WIDTH
ШИРИНА
47 m47м
HEIGHT
ВЫСОТА
30 30
m М
TURBOGENERATOR
1
REACTOR
MODULE 1
STORAGE
POOL
TURBOGENERATOR 2
REACTOR
MODULE 2
MODULE BEING
TRANSPORTED TO THE
CONSTRUCTION SITE
REACTOR MODULE MASS
LENGTH
DIAMETER
600 t
13 m
8.5 m
THE LAND-BASED OPTION OF THE ABV6M RP IS A SINGLE MODULE
COMPLETELY PREPARED FOR
OPERATION AT THE MANUFACTURER
PLANT
THE STRONG HULL OF THE MODULE
FUNCTIONS AS A CONTAINMENT
ОКБМ
58
THANK YOU FOR YOUR
ATTENTION
ОКБМ