vver evolution and world references, licensing and post ... 3/1. vver 1200 - design and...

THE STATE ATOMIC ENERGY CORPORATION ROSATOM

VVER evolution and world references,

licensing and Post-Fukusima safety technologies

SERGEY NOVOSELTSEV

JSC Rusatom Overseas

November, 2017

Accra

2

Content

Design approach and evolution

VVER-1200 overview

Main components of VVER-1200

VVER-1200 safety

Conclusions

DESIGN APPROACH

AND EVOLUTION

The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn’t lead to any obligations to Rosatom and its affiliated companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information. 4

Design features expected from Gen III NPPs

* The IAEA safety target for future plants is 1x10-5. Calculated large release frequency (for radioactivity) is generally about ten times less than CDF.

a standardized design for

each type to expedite

licensing, reduce capital

cost and reduce

construction time;

a simpler and more rugged

design, making them easier

to operate and less

vulnerable to operational

upsets;

higher availability

and longer operating life -

typically

60 years

further

reduced

possibility

of core melt accidents*

1 2 3 4

substantial grace period, so

that following shutdown the

plant requires no active

intervention for (typically)

72 hours

resistance to serious

damage that would allow

radiological release from an

aircraft impact

higher burn-up to use fuel

more fully and efficiently

and reduce the amount of

waste

greater use of burnable

absorbers ('poisons') to

extend fuel life

5 6 7 8

WORLD NUCLEAR ASSOCIATION

INTERPRETS THIRD-GENERATION

REACTORS AS:


VVER-1200: Design evolution (1)

First VVER

since 196x

VVER-440

197x

• Leaktight

compartment

• Small LOCA

• Low leakage

containment

building

• Pipe 100 mm

break

• Limited release of

excess coolant at

high pressure

• Containment

• Primary circuit (Pipe

850 mm) break

• The use of safety

systems to

overcome design

basis accidents

• Double containment

• The use of means of

management of

design extension

conditions

• Passive heat removal

• Core catcher in case

of core meltdown

VVER-1000

198xVVER-1200

200x

VVER-1200 OVERVIEW


Advanced Technology: Rosatom Gen III+ VVER Design

Performance Indicators

VVER-1200 – FUSION OF TECHNOLOGICAL HERITAGE AND INNOVATIONS

First-of-a-class PWR Technology

Nominal Output* 1,200 MWe

Life cycle 60+

Efficiency 37%

Own power

consumption*≈ 7.5%

Availability > 0.9

Maneuverability 100-50-100

Turbine low Speed/high Speed

Maximum Fuel

burn-upup to 70 MW*day/kg U

Safety systems active + passive

Seismic loaddepends on the site and

customer’s request

ReferenceIn commercial operation

since Feb, 2017

* depends on particular project

The content of this presentation is for discussion purposes only, shall not be considered as an offer and doesn’t lead to any obligations to Rosatom and its affiliated companies. Rosatom disclaims all responsibility for any and all mistakes, quality and completeness of the information.

NOVOVORONEZH

NPP II UNIT 1 Commercial Operation –

February, 2017

First VVER-1200 Project ImplementedNovovoronezh NPP II, Unit 1

NOVOVORONEZH II UNIT 1 CAN BE CALLED THE FIRST AND ONLY

GENERATION III+ NPP IN THE WORLD THAT IS ALREADY GENERATING

POWER.

VVER-1200 REACTOR TECHNOLOGY IS EMPLOYED AT THE UNIT –

A FIRST-OF-A-CLASS PWR TECHNOLOGY, COMPLIANT WITH POST-

FUKUSHIMA SAFETY REQUIREMENTS.

8

MORE TO GO:

Hanhikivi NPP (Finland)

Ostrovets NPP (Belarus)

Paks NPP (Hungary)

Leningrad NPP (Russia)

Ropoor (Bangladesh)

Al Dabaa (Egypt)

MAIN COMPONENTS

OF REACTOR BUILDING


VVER-1200: Reactor building Main Components

MAIN

COMPONENTS

OF REACTOR

BUILDING:

REACTOR

STEAM GENERATORS

MAIN CIRCULATING

PUMPS

1

2

3

1

2

2

3

3


VVER-1200: Reactor building Main ComponentsReactor Pressure Vessel

• LESS IMPURITIES in base metal and welds, LESS

NICKEL in welds, increased vessel diameter in

order to REDUCE NEUTRON IRRADIATION of the

vessel;

• according to extensive research the MATERIAL

MAINTAINS DUCTILITY at the lowest possible

temperatures after 60 years of operation at full

power;

• LOW MATERIAL EMBRITTLEMENT by neutron

irradiation can be confirmed by investigating

material samples placed in optimum way on vessel

wall.

1 – Control rod driving mechanism (CRDM)

2 – Reactor pressure vessel (RPV) head

3 – Reactor pressure vessel (RPV)

4 – Protective tubes unit , inlet and outlet nozzles

5 – Belt zone

6 – Reactor baffle

7 – Core

REACTOR PRESSURE VESSEL

MATERIALS AND STRUCTURE:


VVER-1200: Reactor building Main ComponentsMain Circulating Pumps (MCP)

1. Primary circuit main circulating PUMPS

BEARINGS ARE WATER COOLED

and WATER LUBRICATED that

eliminates risk of oil fire inside the

reactor building.

2. Reactor cooling piping is designed in

compliance with the “LEAK BEFORE

BREAK” concept.

1

2

GCNA-1391

TWO SPECIAL DESIGN FEATURES

OF MCPS:


VVER-1200: Reactor building Main ComponentsSteam Generators

PGV-1000MK Performance

Capacity, MWt 800

Steam flow, t/h 1602

Inside diameter of steam generator vessel, m

4,2

Mass, t 330

• LARGER WATER INVENTORY

• Steam generators horizontal configuration

enables VVER to LOSE WATER SLOWER in

case of feed water supply failure

• LARGER STEAM EVAPORATION SURFACE

reduces steam velocity preventing tube

vibrations

• ENHANCED SEISMIC RESISTANCE

• EASY SG REPLACEMENT (no need to make a

hole in the containment wall)

• Material of the tubes: «08Х18Н10T» steel

(equiv. AISI 321) with ~10% Ni

• LONG SERVICE LIFE

VVER UTILIZES 4

HORIZONTAL STEAM

GENERATORS WITH

THE FOLLOWING

ADVANTAGES:

MAIN COMPONENTS

OF TURBINE BUILDING


VVER-1200: Turbine building Main Components

TURBINE TYPE:

• High-speed turbines - 3000 rpm

• Low-speed turbines -1500 rpm

COUNTRY OF ORIGIN:

• Russian referenced technologies

(Power Machines)

• Foreign solutions (GE-Alstom, Doosan,

Skoda Power, Siemens, etc.)

ROSATOM OFFERS A FLEXIBLE

AND TAILOR-MADE APPROACH

TO THE TURBINE SELECTION

AND ASSISTS PARTNER COUNTRIES

IN OPTING FOR THE MOST SUITABLE

SOLUTION ACCORDING TO THE

VARIOUS PARAMETERS:

VVER-1200 SAFETY


VVER-1200: Defence-in-Depth

CONTAINMENT

SYSTEM

Preventing fission

products release into

environment

PRIMARY CIRCUIT

Preventing fission

products release into

containment

FUEL ROD

Preventing fission

products release to

primary circuit

FUEL MATRIX

Preventing fission

products release

inside the fuel

cladding

DEFENSE-IN-DEPTH PRINCIPLE IS BASED ON USING PHYSICAL BARRIERS

TO PREVENT IONIZING RADIATION AND RADIOACTIVE MATERIALS LEAKS INTO THE

ENVIRONMENT, AND THE SYSTEM OF TECHNICAL AND ORGANIZATIONAL MEASURES

ON BARRIERS MANAGEMENT


The main principle in the design of the

VVER-1200 PLANTS is:

18

VVER-1200: Safety Concept

THAT ALLOWS THE OPERATOR TO USE DIFFERENT SAFETY SYSTEMS

INDEPENDENTLY AND FLEXIBLY, DEPENDING ON THE ACCIDENT

SCENARIO

ALL FUNDAMENTAL

SAFETY FUNCTIONS

SHALL BE PROVIDED

BOTH WITH

ACTIVE

SYSTEMS that have reliable

AC power supply

PASSIVE

SYSTEMSthat do not need

electricity


CONTROL

OF REACTIVITY

• preventing uncontrolled

reactor power increase

• ensuring fast and safe

reactor shutdown if

required

19

Fundamental Safety Functions

1 2 3

PROVISION OF THE THREE FUNDAMENTAL SAFETY FUNCTIONS IS NECESSARY AND SUFFICENT TO ENSURE NUCLEAR SAFETY:

CONTAINMENT

OF RADIOACTIVE

MATERIALS

• preventing significant

radioactive releases

to the environment

REMOVAL OF DECAY

HEAT TO THE

ULTIMATE HEAT SINK

• cooling of shutdown

reactor

• cooling of spent nuclear

fuel

Ensuring fundamental safety functions

#1 CONTROL OF REACTIVITY


DESIGN DIVERSITY PRINCIPLE

21

Control of Reactivity

When control rods are dropped into the core the reactor will turn

IN SHUTDOWN STATE (without boron injection)

TO ENSURE

REACTIVITY

CONTROL VVER

UTILIZES

BORON INJECTION

SYSTEMS

(ACTIVE SAFETY

SYSTEM)

REACTOR CONTROL

AND PROTECTION

SYSTEM

(PASSIVE SAFETY

SYSTEM)

VVER-1200 REACTOR ENJOYS A UNIQUE SAFETY FEATURE IN

COMPARISON WITH OTHER PRESSURIZED WATER REACTORS:

Ensuring fundamental safety functions

#2 REMOVAL OF DECAY HEAT TO THE

ULTIMATE HEAT SINK


VVER-1200: removal of decay heat to the ultimate heat sink

• via the secondary circuit (water circulation can be established in a

closed loop: steam generators – steam lines – turbine by-pass –

capacitor – feedwater lines)

ACTIVE SYSTEMS (IN CASE OF DESIGN BASIS

CONDITIONS - DBC) REMOVE RESIDUAL HEAT AND TURN NPP INTO COLD SHUTDOWN MODE:

PASSIVE SYSTEMS (IN CASE OF DESIGN EXTENSION

CONDITIONS - DEC) REMOVE THE RESIDUAL HEAT FROM STEAM GENERATORS DIRECTLY

TO THE ATMOSPHERE.

• by removing heat directly from the primary circuit to the atmosphere

DESIGN DIVERSITY PRINCIPLE

Ensuring of fundamental safety functions

#3 CONFINEMENT OF RADIOACTIVE

MATERIALS


Confinement of Radioactive Materials

all physical phenomena that could occur in connection with core

meltdown and endanger the containment integrity are taken into

account, and

dedicated means and systems are provided to ensure containment

integrity.

.

systems that are completely independent and separated from the

systems that are intended to prevent a severe reactor core damage.

THE STRATEGY FOR PROTECTION OF VVER-1200

CONTAINMENT AFTER POTENTIAL REACTOR CORE

MELTDOWN ENSURES THAT

PROTECTION OF VVER-1200 CONTAINMENT

INTEGRITY IS BASED ON


VVER-1200: Double Containment

• INTERNAL CONTAINMENT – pre-

stressed reinforced concrete of 1.2

METERS thickness in cylindrical part

(1.1 METER in dome) with 6 MM internal

steel cladding.

• EXTERNAL CONTAINMENT – reinforced

concrete of 2.2 METERS thickness in

cylindrical part (0.8 METERS in dome).

• The gap between two walls (annulus) is

1.8 METERS and has filtering ventilation

to outside.

INTERNAL CONTAINMENT

EXTERNAL CONTAINMENT


VVER-1200: Core Catcher

• installed under the reactor vessel to PROTECT

CONTAINMENT FROM MELTDOWN IMPACTS (the

temperature of molten core exceeds 2000°C).

• RETAINS MOLTEN CORE AND SOLID

FRAGMENTS of the core and reactor vessel.

• COOLS AND SOLIDIFIES MOLTEN CORE due to

sacrificial material.

• FORMS A CRUST AT THE UPPER PART to

prevent radioactive leakage into the

environment.

CORE CATCHER


Fukushima Lessons Learnt

28

ALL VVER PLANTS IN OPERATION OR ARE UNDER CONSTRUCTION

ARE IN COMPLIANCE WITH THE LATEST SAFETY REQUIREMENTS

Long-term cooling of reactor core without power supply

Long-term decay heat removal independent of primary heat sink (natural or artificial water body, cooling tower, etc)

Maintaining reactor containment integrity after a potential

core meltdown accident

All technical means for management DEC should

be protected from the effects of accidents by

using mobile means stored in safe places.

Safety systems of a single unit of an

NPP must be independent from the

safety systems of another unit deployed

on the same site

The defense-in-depth concept and

the practical elimination of

accidents with early or large

release are fully applicable to the

spent fuel pool

CONCLUSIONS


Conclusions

1

2

3

5

4

The VVER type nuclear power plants have gone through a continuous

evolution during 50 years and have demonstrated their safety and

reliability in power generation.

The VVER-1200 plants have safety design features that take into

account the latest development of safety requirements and safety

technology.

All fundamental safety functions are ensured by multiple different

safety systems, both active and passive.

Such combination ensures both quick (due to active part) and reliable

(due to passive part) mitigation of any accidents that can occur.

The VVER designers have developed already before the Fukushima

Daiichi accident the NPP safety features that have been commonly

suggested to new nuclear power plants after the accident.

Rusatom Overseas

Tel.: +7 (495) 280-00-14

e-mail: [email protected]

Web page: www.rusatom-overseas.com

THANK YOU FOR YOUR ATTENTION!

mailto:[email protected]

http://www.rusatom-overseas.com/

vver evolution and world references, licensing and post ... 3/1. vver 1200 - design and...

Documents