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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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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

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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

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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

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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

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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

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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

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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

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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

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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.

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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

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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

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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

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58

THANK YOU FOR YOUR

ATTENTION