2_КLT-40S_VBER_OKBM_Afrikantov_Fadeev

8/9/2019 2_LT-40S_VBER_OKBM_Afrikantov_Fadeev

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1

KLT-40S Reactor Plantfor the floating CNPP FPU

VVER RP Chief DesignerYury P. Fadeev

JSC Afrikantov OKBMRUSSIA


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2

MAIN FIELDS OF OKBM ACTIVITY

MARINE REACTOR PLANTS FOR THE NAVY

MARINE REACTOR PLANTS FOR THE CIVIL FLEET

FAST REACTORS

HIGH-TEMPERATURE GAS-COOLED REACTORSFA

NUCLEAR FUEL HANDLING EQUIPMENT

UNIFIED EQUIPMENT FOR NP

(PUMPS, FANS)

1945FOUNDATION OF THE ENTERPRISE

UNIFIED EQUIPMENT FOR NP


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3

RP design, manufacture,

complete supply

Upgrade

Authors supervision duringmanufacture 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-150KLT-40

(KLT-40M,KLT-40S)

Four generations of marine RPs

RITM-200

INTRODUCTION

Disposal


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4

MARINE RPs

JSC AFRIKANTOV OKBMIS 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 AFRIKANTOVOKBMREACTORS.

20 REACTORS WERE FABRICATED AND

OPERATED.

THE RUNNING TIME IS MORE THAN 340REACTOR-YEARS.

6NUCLEAR ICE-BREAKERS ARE OPERATED.

THE ACTUAL LIFE TIME OF THE NUCLER ICE-

BREAKER ARKTIKA RP IS 177,204 H, THE

SERVICE LIFE IS 34YEARS.

SERVICE LIFE EXTENSION UP TO 200,000 HFOR NUCLEAR ICE-BREAKER RPs IS ENSURED.

THE WORLD-LARGEST NUCLEAR ICE-

BREAKER 50 LET POBEDYWITH THE -900

RP DESIGNED BY JSC AFRIKANTOV OKBM

WAS PUT IN COMMISSION ON ARCH 23, 2007

AT MURMANSK OCEAN COMPANY (FSUEATOMFLOT).

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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5

REACTORS FOR SMALL AND MEDIUM POWER PLANTS

THERMAL POWER1654 MW

ELECTRIC POWER

3.510 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 POWER3001700 MW

ELECTRIC POWER

100600 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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6

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 OFINDUSTRIAL SITE

REDUCED CONSTRUCTION COST

CONSTRUCTION TIME REDUCED TO 3 YEARS

FULL SERVICE MAINTENANCE AND REPAIR IN EXISTING

SPECIALIZED FACILITIES

GREEN LAWN PRINCIPLEIS 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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8

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 2070 MW

HEAT 50146 Gcal/h

FPU

with KLT-40S

RPs

Small CNPP

SPENT FUEL

AND RADWASTE

STORAGEREACTOR

PLANTS STEAM-TURBINE

PLANTS

UNDERWATER TRENCH

145X45

DEPTH, 9 M

HEAT

POINTDEVICES FOR DISTRIBUTING

AND TRANSFERRING

ELECTRIC POWER TO CONSUMERS

SALT WET

STORAGE CONTAINER

HOT WATER

CONTAINERS

1000 m31000 m3

HYDRO ENGINEERING FACILITIES


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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

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 TWh

FUEL ENRICHMENT < 20%

CRDM

MAIN CIRCULATIONPUMP

STEAMGENERATOR

REACTOR

LOCALIZING

VALVES

STEAMLINES

HYDRAULIC

ACCUMULATORHYDRAULIC

TANK

EXCHANGER OF i- iii

CIRCUITS

PRESSURIZER

CONTAINMENT INTERNAL PRESSURE

0.4 MPa

CONTAINMENT LEAK TIGHTNESS

volume/day 1%


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12

KLT-40S RP FLOW DIAGRAM

PASSIVE

EMERGENCY

SHUTDOWN COOLING

SYSTEM

SYSTEM OF REACTOR

CAISSON FILLING WITH WATER

ACTIVE EMERGENCY CORE

COOLING SYSTEM

ACTIVE SYSTEM OFLIQUID ABSORBER

INJECTION

PASSIVE EMERGENCY CORE

COOLING SYSTEM (HYDRAULICACCUMULATORS)

PASSIVE SYSTEM OF

EMERGENCY PRESSURE

DECREASE IN THE

CONTAINMENT

(CONDENSATION SYSTEM)

ACTIVE SYSTEM OF

EMERGENCY SHUTDOWNCOOLING THROUGH PROCESS

CONDENSER

PASSIVE SYSTEM OF

EMERGENCY PRESSURE

DECREASE IN THE

CONTAINMENT (BUBBLINGSYSTEM)

RECIRCULATION SYSTEMPUMPS

NEWLY INTRODUCED

SAFETY SYSTEMS

STEAMGENERATOR

REACTOR MCP

PRESSURIZER

PSCS

METAL-

WATERPROTECTION

TANK

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CORE REACTOR AND FA

FAReactor

KLT-40S Cassette

Fuel rod

6.8 mm

CPS AR

BPR

Cover

Vessel

Block of CG

control rods

Cavity

14


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14

CORE REFUELING DIAGRAM

Refueling process safety is

ensured for all possible initial

events, in particular:

- SFA hanging-up duringrefueling;

- SFA container hanging-upduring transportation;

- SFA and SFA cask falling;

- refueling equipmentdeenergization;

- SFA-storage cooling circuitdepressurization;

- SFA-storage deenergization;

etc.

Refueling

compartment

Apparatus

room

Storage tankDry 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 sp eed sup ply, m3/h 870/290

Consumed p ower, kW

155/11

Rotor rotat ion sp eed,

syn chro nous , rpm 3000/1000

Head , m 38/4

Servic e life, year 20

PUMP TYPECANNED,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 PUMPAGGREGATE (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

INLETFEEDWATER

HEADER

STEAM HEADER

SG COVER

ADAPTER

FEEDWATER

TUBES

HEAT-EXCHANGINGTUBES

STEAM GENERATOR TYPE

VERTICAL RECUPERATIVE HEAT

EXCHANGER WITH COIL HEAT-

EXCHANGING SURFACE OF TITANIUMALLOYS 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 OPENINGPRIMARY 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 systemsandself-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 depressurizationscope 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

1FUEL COMPOSITION2FUEL ELEMENT CLADDING

3PRIMARY CIRCUIT

4RP CONTAINMENT

5PROTECTIVE ENCLOSURE


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Reactor Emergency Heat Removal Systems

Hydraul ical ly

op erated air

d ist r ibutors

Opening of

pneumat ica l ly-

dr iven valves of

ECCS passive

channels by

pr imary circu i t

overpressure

(coo ldown)

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 g enerator

3 Main circulat ion pump

4 Emergency heat remo val system

5 Puri f icat ion and cool in g system

6 Process condenser

6

21


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EMERGENCY CORE COOLING SYSTEMS

1 Reactor

2 Steam generator

3 Main circulation pump

4 ECCS hydroaccumulator

5 ECCS tank6 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 210 m3.

GA water volume is 24 m3.

The time margin in the passive mode before core drainage starts is approximately 3 h.

4

22


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SYSTEM OF EMERGENCY PRESSURE DECREASE IN CONTAINMENT

The passive

emergency

pressure decreasesystem

(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 CONFINEMENTIN KLT-40S RP REACTOR VESSEL

Reactor

ca isson

Reactor

vessel

Core melt

Melt volume, m3 - 0.885

Melt surface diameter, m - 1.918Melt 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 appearedtemperature difference

Radiation dose for population in case of

beyond design accident with severe core

damage does not exceed 5 mSv

Cool ing w ater

supp ly

24


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ANALYSIS OF HYDROGEN SAFETY IN SEVERE ACCIDENTS

Arrangement of hydrogenrecombiners (afterburners)in equipment and reactorcompartments of KLT-40SRP

25RADIATION AND ENVIRONMENTAL SAFETY


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25RADIATION AND ENVIRONMENTAL SAFETY

POPULATION RADIATION DOSE RATE UNDER NORMAL OPERATION CONDITIONS ANDDESIGN-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

26


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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

27

GO S OS S O O


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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 POWERUNIT 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 ISGENERATED BY HEAT POWER PLANTS

BASIC FUEL OF HEAT POWER PLANTSNATURAL GAS, COAL

UNIT CAPACITY OF HEAT POWER PLANT UNITS ~200-300 MW (e)

NUMBER OF UNITSMORE THAN 450

OTHER APPLICATION AREAS - DISTRICT HEATING, DESALINATION

AND INDUSTRIAL PRODUCTION OF POTABLE WATER

28

VBER RP DESIGN CONCEPT


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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

29


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TARGET REQUIREMENTS FOR VBER POWER UNITS

Target technical parameters of th e pow er un i ts comp ly w ith AES-2006 (Generat ion 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,

year30

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 10-6for reactor

per year

8. Probability of ultimate accidental release Not more than 10-7for 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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31COMPETITIVE ADVANTAGES OF VBER REACTORS AS COMPARED


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WITH LOOP-TYPE PRESSURIZED-WATER REACTORS(CONTINUED)

Criterion type Characteristics

Consistency

Application of mastered fuelFA of unified design based on TVSAintegrating 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 technologyof 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

32

POWER RANGE OF VBER RP


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POWER RANGE OF VBER RP

N=460W(e)

FIVE-LOOP RP

FOUR-LOOP RP

SIX-LOOP RP

N=600W(e)

N=250W(e)

THREE-LOOP RP

TWO-LOOP RP

N=150W(e)

UNIFIED TECHNICAL

SOLUTIONS

N=300W(e)

33

COMPACTNESS OF VBER RP


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COMPACTNESS OF VBER RP

VBER-300VVER-300

34

REACTOR MODULE INTEGRATED VESSEL


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INTERGRATED VESSELSCALED

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


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FUEL ASSEMBLY

STIFFENING

ANGLE

TOPNOZZLE

SPACING

GRID

BOTTOME

NOZZLE

GUIDE CHANNELS FOR AE

GFESTIFFENING

ANGLE

IN VBER RP CORES THERE ARE USED FASOF 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 PILOTTVSA FOR 6-YEAR OPERATION AT THE 1STUNIT OF KALININ NPP

WAS 66 MWDAY/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 32 years,

41.5 year

36

MAIN CIRCULATION ELECTRIC PUMP


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MAIN CIRCULATION ELECTRIC PUMP

Parameter Value

NOMINAL SUPPLY, m3/h 5560

POWER CONSUMPTION, Wt 1.360

SYNCHRONOUS ROTOR SPEED, S-1(RPM) 50 (3000)

HEAD AT NOMINAL SUPPLY, m 52

MCP DIMENSIONS, mm 38701215

MASS OF ELECTRIC PUMP, t 21

SERVICE LIFE, years 30

PUMP TYPE-AXIAL, SINGLE-STAGE, WITHCANNED 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 b earing

Radial

bearingGuide vanes

Impeller

Stator cooler

37

STEAM GENERATOR


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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 101.4

TUBE SYSTEM MATERIAL Titanium

alloy

TUBE SYSTEM MASS, t 58.5


STEAM GENERATOR TYPE - ONCE-THROUGH, MODULAR, COILED, WHERESECONDARY FLUID ARRANGED INSIDE TUBES

THE DESIGN WAS IMPROVED AS COMPARED WITH ICE-BREAKER STEAMGENERATORS (FEED WATER SUPPLY ASSEMBLIES AND SG COVER JUNCTIONSWERE 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 USINGMODULE-WITNESSES IN THE FORM OF REMOVABLE STEAM-GENERATINGMODULES

AUTOMATED ON-LINE DETECTION OF INER-CIRCUIT LEAKAGES BYSECONDARY CIRCUIT STEAM ACTIVITY

REPAIRABILITY WITHOUT OPENING PRIMARY CIRYUT CAVITIES

CAPABILITY OF HIGH-MANEUVERABLE MODES

DEPRESSURIZATION DIMENSIONS AT PRIMARY CIRCUIT LEAKAGE NOT MORETHAN DEQ.=40 MM

From

reactor

To

reactor

STEAM GENERATOR

Makeup

water

nozzleSteam no zzle

SG cover

SG module

SG casing

38

REFUELING SYSTEM


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REFUELING SYSTEM

Refueling

machine

SFA

storage pool

FFA

transportation

container TK-13

or cask

Core

Refueling

machine in theFAs 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 REFUELINGMETHOD

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

39

TECHNOLOGY OF EQUIPMENT MODULE FABRICATION AND MOUNTING


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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

40

VBER 300 REACTOR PLANT CONTAINMENT


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VBER-300 REACTOR PLANT CONTAINMENT

Inner metalcontainment

-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.

41

SAFETY CONCEPTION OF VBER RP


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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 principlesdeveloped by the world community and reflected in IAEA

recommendations.

42

SYSTEMS OF REACTOR EMERGENCY SHUTDOWN


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SYSTEMS OF REACTOR EMERGENCY SHUTDOWN

System of l iquid

absorber in ject ion

Electromechanical

sys tem of react iv i ty

cont ro l

1 Reactor

2 CPS dr ive mechanisms

3 System of l iquid absorber in ject ion

4 From m akeup system and boron contro l system

5 Electr ic pow er circuit-breaker by pressu re

From makeup system

and boron cont ro l

system

43

EMERGENCY CORE COOL ING SYSTEMS


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EMERGENCYCORE COOL ING SYSTEMS

1 Reactor

2 Steam generator

3 Main circulation pump

4 ECCS first-stage hydraulicaccumulator

5 ECCS second-stage hydraulicaccumulator

6 Makeup system

7 Recirculation system

1

2

3

4

5

6

7

Passiv e emergency c ore

coo l ing sys tem(24 h)

Recirculat ion and

repai r c oo ldown

system

Makeup

system

44

REACTOR EMERGENCY HEAT REMOVAL SYSTEMS


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REACTOR EMERGENCY HEAT REMOVAL SYSTEMS

1 Reactor

2 Steam generator

3 Main circulat ion pump

4 Emergency heat removal system

5 Pur if icat ion and cool ing do wn s ystem

6 Process condenser

Passive emergency

heat removal system

(72 hr s)

Process condenser

Puri f icat ion and

coo l ing down system

6

45

POWER UNIT STRENGTH


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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 Pa, which is less than the allowable one,

equal to 370 Pa.

POWER UNIT STRENGTH

SEISMIC STABILITY

46

POWER UNIT STRENGTH


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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

,.g

,

-

- Y

- Z

Overloading spectrum

47

POWER UNIT STRENGHT


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AIRCRAFT CRASH

VNIIEF and OKM 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

,.g

,

Theoverloadingeffecting the

power unitattachmentpoints is lessthan underseismic effect.

POWER UNIT STRENGHT

48

HYPOTHETICAL ACCIDENT OF GUILLOTINE RUPTURE OF MAIN NOZZLE


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HYPOTHETICAL ACCIDENT OF GUILLOTINE RUPTURE OF MAIN NOZZLE

SG

Reactor

STRENGTH ANALYSES OF THE

DEVICE PERFORMED BY OKBM

AND VNIIEF SHOW THAT

PRIMARY COOLANT OUTFLOWDOES NOT EXCEED THE

EQUIVALENT DIAMETER DN =

100 MM

DN< 100 mmLimiting device

49

POSTULATED SEVERE ACCIDENT ANALYSIS


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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, thatcorresponds completely to severe accident management concepts in newgeneration middle-size RP designs

LIMITATION OF SEVERE ACCIDENT CONSEQUENCIES

Time margin before the core overheating start is 24 h minimum owing to passiveECCS and EHRS operation.

The scenario of core melting under high pressure is eliminated due to passivesystems operation.

Favorable conditions for core melt confinement inside the reactor vessel:reduced power density, large time margin before melting start, low thermal fluxesfrom melt at the bottom.

Special emergency reactor vessel cooling system (reactor cavity filling withwater) 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.

SAFETY IN POSTULATED SEVERE ACCIDENT


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51

VBER-300 RADIATION SAFETY


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VBER 300 RADIATION SAFETY

The achieved level of VBER-300 RP radiation safetymeets the contemporaryrequirements for the new generation reactors

Indus tr ia l si te of thenuclear

cogenerat ion plant

Buffer area

1 km

Protect ive Act ion

Planning Area

Radiat ion dose for p opulat ion in c ase

of beyond design accident withsevere core damage does no t exceed

5 mSv

Populat ion dos e rate:

- During no rmal operat ion 0.01%

- During m aximum design-basis accident - 5%of natural radiat ion backgroun d

52RITM-200 REACTOR PLANT (RP)


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Steamgenerator (SG)(4 pcs.)

Core

RCCP

(4 pcs.)

Common SGheader

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 primarycircuit 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 yearsAssigned running time 320 000 h

Core generating capacity 7.0 TWh

Fuel enrichment < 20%

53RITM-200 REACTOR PLANT (RP)


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Hydraulic accumulator

Steam generator unit(SGU)

Shieldtank

RCCP

Pressurizer

Biological

shielding

54KLT-40S RP AND RITM-200 RP COMPARED


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RITM-200KLT-40S

The RP mass in containment is 1870 t.

The RP dimensions in containment

are 12 7.9 12 m.

The RP mass in containment is 1100 t.

The RP dimensions in containment

are 6 6 15.5 m.

55

ABV-6M REACTOR PLANT (RP)


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REACTOR TYPE INTEGRAL PWR

WITH NATURAL

COOLANTCIRCULATION

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


REFUELING INTERVAL, years 10

CORE GENERATING CAPACITY, TWh 3.1

FUEL ENRICHMENT, % < 20

( )

REACTOR COVER

UNDER

BIOLOGICAL

SHIELDING

BUILT-IN STEAM

GENERATOR

UNITSPROTECTIVE

TUBE

ASSEMBLY

REACTOR

VESSEL

FAs IN THE

CORE

56FLOATING CO-GENERATION NPP WITH THE ABV-6M RP


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CRDM

VALVES

PCDS

COOLER

PCDS

PUMP

REACTOR

PRESSURIZE

RSGA MASS, t

200

LENGTH, m 5

WIDTH, m 3.6HEIGHT, m 4.5

MAXIMUM LENGTH, m 97140

BEAM, m 1621

SIDE HEIGHT, m 10

DRAFT, m 2.52.8

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

57

STATIONARY NPP WITH THE ABV-6M RP


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67

47

30

TURBO-

GENERATOR 2

REACTORMODULE 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 CONTAINMENTMODULE BEING

TRANSPORTED TO THECONSTRUCTION SITE

LENGTH 67 m

WIDTH 47 m

HEIGHT 30 m

58


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THANK YOU FOR YOURATTENTION

Documents

2_КLT-40S_VBER_OKBM_Afrikantov_Fadeev