VVER

VVER
ing 440 MW of electrical power. The V230 employs six
primary coolant loops each with a horizontal steam generator. A modified version of VVER-440, Model V213,
was a product of the first nuclear safety standards adopted
by Soviet designers. This model includes added emergency core cooling and auxiliary feedwater systems as
well as upgraded accident localization systems.[4]
The larger VVER-1000 was developed after 1975 and is a
four-loop system housed in a containment-type structure
with a spray steam suppression system. VVER reactor designs have been elaborated to incorporate automatic control, passive safety and containment systems associated
with Western third generation nuclear reactors.
The VVER-1200 is the version currently offered for construction, being an evolution of the VVER-1000 with increased power output to about 1200 MWe (gross) and
providing additional passive safety features.[5]
In 2012, Rosatom stated that in the future it intended to
certify the VVER with the British and U.S. regulatory authorities, though was unlikely to apply for a British license
before 2015.[6][7]
2 Design
WWER-1000 (or VVER-1000 as a direct transliteration of Russian ВВЭР−1000) is a 1000 MWe Russian nuclear power reactor of PWR type.
The Water-Water Energetic Reactor (VVER),[1] or
WWER (from Russian: Водо-водяной энергетический реактор; transliterates as Vodo-Vodyanoi Energetichesky Reaktor; Water-Water Power Reactor) is a series of pressurised water reactor designs originally developed in the Soviet Union, and now Russia, by OKB
Gidropress.[2] Power output ranges from 300 MWe to
1700 MWe[3] with the latest Russian development of
the design. VVER power stations are used by Armenia,
Bulgaria, China, Czech Republic, Finland, Hungary,
India, Iran, Slovakia, Ukraine and Russia.
1
ВВЭР-1000
Westinghouse 4-loop PWR
The arrangement of hexahedral fuel assemblies compared to a
Westinghouse PWR design
The Russian abbreviation VVER stands for 'water-water
energy reactor' (i.e. water-cooled water-moderated energy reactor). This describes the pressurised water reactor (PWR) design. The main distinguishing features of
the VVER[3] compared to other PWRs are:
History
• Horizontal steam generators
The earliest VVERs were built before 1970. The VVER440 Model V230 was the most common design, deliver-
• Hexagonal fuel assemblies
1
2
2
DESIGN
• No bottom penetrations in the pressure vessel
• High-capacity pressurisers providing a large reactor
coolant inventory
Reactor fuel rods are fully immersed in water kept at 15
MPa of pressure so that it does not boil at normal (220 to
over 300 °C) operating temperatures. Water in the reactor serves both as a coolant and a moderator which is an
important safety feature. Should coolant circulation fail,
the neutron moderation effect of the water diminishes,
reducing reaction intensity and compensating for loss of
cooling, a condition known as negative void coefficient.
Later versions of the reactors are encased in massive steel
pressure shells. Fuel is low enriched (ca. 2.4–4.4% 235 U)
uranium dioxide (UO2 ) or equivalent pressed into pellets
and assembled into fuel rods.
Reactivity is controlled by control rods that can be inserted into the reactor from above. These rods are made
Treatment of the interior part of a VVER-1000 reactor frame on
from a neutron absorbing material and, depending on Atommash
depth of insertion, hinder the chain reaction. If there is
an emergency, a reactor shutdown can be performed by
4. Pump: The pump ensures proper circulation of the
full insertion of the control rods into the core.
water through the circuit.
2.1
Primary cooling circuit
P
CP-4
To ensure safety primary components are redundant.
SG-3
SG-4
2.2 Secondary circuit and electrical output
CP-3
SG-2
CP-2
CP-1
SG-1
NR
Stereometric scheme of primary cooling circuit VVER-1000
As stated above, water in the primary circuit is kept under constant pressure to avoid boiling. Since the water
transfers all the heat from the core and is irradiated, integrity of this circuit is most crucial. In the circuit, four
subsystems can be distinguished:
1. Reactor: Water flows through fuel rod assemblies
and is heated by the nuclear chain reaction.
2. Volume compensator (Pressurizer): To keep the
water under constant but controlled pressure, the
volume compensator regulates pressure employing
self-regulation of saturated steam-water interface
and by means of electrical heating and relief valves.
The secondary circuit also consists of different subsystems:
1. Steam Generator: Secondary water is boiled taking
heat from the primary circuit. Before entering the
turbine remaining water is separated from the steam
so that the steam is dry.
2. Turbine: The expanding steam drives a turbine,
which connects to an electrical generator. The turbine is split into high and low pressure sections. To
prevent condensation (Water droplets at high speed
damage the turbine blades) steam is reheated between these sections. Reactors of the VVER-1000
type deliver 1 GW of electrical power.
3. Condenser: The steam is cooled and allowed to condense, shedding waste heat into a cooling circuit.
4. Deaerator: Removes gases from the coolant.
5. Pump: The circulation pumps are each driven by
their own small steam turbine.
To increase efficiency of the process, steam from the tur3. Steam Generator: In the steam generator, heat from bine is taken to reheat coolant before the deaerator and
primary coolant water is used to boil water in the the steam generator. Water in this circuit is not supposed
secondary circuit.
to be radioactive.
3
2.3
Cooling circuit
3 Operational life of VVER 1000
The cooling circuit is an open circuit diverting water
from an outside reservoir such as a lake or river. Evaporative cooling towers, cooling basins or ponds exhaust
waste heat from the generation circuit, releasing it into the
environment. In addition to generating electricity most
VVERs have a capability to supply heat for residential
and industrial use. Operational examples of such systems
are the plants at Jaslovské Bohunice and Dukovany. [8]
2.4
Safety barriers
Control room of a VVER-1000 in 2009, Kozloduy Unit 5
When first built the VVER design was intended to be
operational for 35 years. A mid-life major overhaul including a complete replacement of critical parts such as
fuel and control rod channels was thought necessary after
that.[9] Since RBMK reactors specified a major replacement programme at 35 years designers originally decided
this needed to happen in the VVER type as well, although
The two VVER-440 units in Loviisa have containment buildings
they are of more robust design than the RBMK type.
that fulfil Western safety standards.
Most of Russia’s VVER plants are now reaching and passA typical design feature of nuclear reactors is layered ing the 35 year mark. More recent design studies have
safety barriers preventing escape of radioactive material. allowed for an extension of lifetime up to 50 years with
replacement of equipment. New VVERs will be nameVVER reactors have four layers:
plated with the extended lifetime.
1. Fuel pellets: Radioactive elements are retained In 2010 the oldest VVER-1000, at Novovoronezh, was
shut down for modernization to extend its operating life
within the crystal structure of the fuel pellets.
for an additional 30 years; the first to undergo such an
2. Fuel rods: The zircaloy tubes provide a further bar- operating life extension. The works include the modernrier resistant to heat and high pressure.
ization of management, protection and emergency systems, and improvement of security and radiation safety
3. Reactor Shell: A massive steel shell encases the systems.[10]
whole fuel assembly hermetically.
4. Reactor Building: A concrete containment building
that encases the whole first circuit is strong enough 4 VVER-1200
to resist the pressure surge a breach in the first circuit
would cause.
The VVER-1200 (or NPP-2006 or AES-2006)[5] is an
evolution of the VVER-1000 being offered for domestic
Currently operating Russian VVERs are inherently safer and export use.[11][12] Specifications include a $1,200 per
designs than the RBMK reactors of Chernobyl disaster. kW electric capital cost, 54 month planned construction
They do not have the vulnerability that the RBMK re- time, and expected 60 year lifetime at 90% capacity facactors had of a risk of a power surge transient or crit- tor. The VVER 1200 will produce 1,200 MWe of power.
icality accident. The Soviet Union opted to construct Safety features include a containment building and misgraphite-moderated RBMK series nuclear reactors with- sile shield. It has full emergency systems that include an
out containment structures on grounds of cost as well as emergency core cooling system, emergency backup diesel
the relative ease of re-fueling RBMK reactors. Fuel el- power supply, advanced refueling machine, computerized
ements in a RBMK reactor can be replaced while still reactor control systems, backup feed water supply and reoperational, allowing continued operation and plutonium actor SCRAM system. The nuclear reactor and associextraction compared to the VVER which needs to be ated systems are in a single building with another buildshut down. Many levels of protection and containment ing for the turbo generators. The main building comprises
have both been proposed and constructed for RBMK and the reactor, refueling machine and diesel backup power
VVER type reactors.
supply, steam generators and reactor control systems.
4
If a VVER-1200 experiences a loss of coolant accident
or loss of power accident the turbogenerators 'coast down'
for 30 seconds, during which time a shutdown can be initiated using residual power in the system. Further emergency power is available from a backup set of diesel generators kept on standby to maintain cooling flow to the
reactor. The reactor design has been refined to optimize
fuel efficiency.
The first two units are being built at Leningrad
Nuclear Power Plant II and Novovoronezh Nuclear
Power Plant II. More reactors with a VVER-1200/491
like the Leningrad-II-design are planned (Kaliningrad
and Nizhny Novgorod NPP) and under construction.
The VVER-1200/392M[13] under construction at the
Novovoronezh NPP-II is selected for the Seversk, Zentral and South-Urals NPP. A standard version was developed as VVER-1200/513 and based on the VVER-TOI
(VVER-1300/510) design.
6 POWER PLANTS
which meets a number of target-oriented parameters using modern information and management
technologies.[21]
• VVER-1700 Supercritical water reactor version.
6 Power plants
See the Wikipedia pages for each facility for
sources.
Russia recently installed two nuclear reactors in China at
the Tianwan Nuclear Power Plant, and an extension consisting of a further two reactors was just approved. This
is the first time the two countries have co-operated on a
nuclear power project. The reactors are the VVER 1000
type, which Russia has improved incrementally while reIn July 2012 a contract was agreed to build two AES-2006 taining the basic design. These VVER 1000 reactors
in Belarus at Ostrovets for a cost of about $10 billion.[14] are housed in a confinement shell capable of being hit
An AES-2006 is being bid for the Hanhikivi Nuclear by an aircraft weighing 20 tonnes and suffering no exPower Plant in Finland.[15]
pected damage. Other important safety features include
an emergency core cooling system and core confinement
system. Russia delivered initial fuel loads for the Tianwan
reactors. China planned to begin indigenous fuel fabri4.1 Passive heat removal system
cation for the Tianwan plant in 2010, using technology
A passive heat removal system had been added to the ex- transferred from Russian nuclear fuel producer TVEL.[27]
isting active systems in the AES-92 version of the VVER- The Tianwan Nuclear Power Plant uses many third party
1000 used for the Kudankulam Nuclear Power Plant in parts. While the reactor and turbo-generators are of
India. This has been retained for the newer VVER-1200 Russian design, the control room was designed and built
and future designs. The system is based on a cooling by an international consortium. In this way the plant
system and water tanks built on top of the containment was brought to meet widely recognised safety standards;
dome.[16] The passive systems all safety functions for 24 safety systems were already mostly in place but the prehours, and core safety for 72 hours.[5]
vious monitoring of these systems did not meet internaOther new safety systems include aircraft crash protection tional safety standards. The new VVER 1000 plant built
and a core catcher to contain the molten reactor core in in China has 94% of its systems automated, meaning the
plant can control itself under most situations. Refueling
the event of a severe accident.[12][14]
procedures require little human intervention. Five operators are still needed in the control room. The IAEA has
referred to the station as the “safest nuclear power plant
5 Future versions
in the world”.[28]
In May 2010 Russia secured an agreement with the TurkA number of designs for future versions of the VVER
ish government to build a power plant with four VVER[17]
have been made:
1200 reactors at Akkuyu, Turkey.[29][30] However, due
to the accident experienced in Fukushima, anti-nuclear
• MIR-1200 (Modernised International Reactor) - de- environmentalist groups heavily protested the proposed
signed in conjunction with Czech company ŠKODA reactor at Akkuyu.
JS[18] to satisfy European requirements[19]
On 11 October 2011 an agreement was signed to build
Belarus’ first nuclear power plant at Astravyets, using
• VVER-1500 - VVER-1000 with dimensions intwo NPP-2006 reactors with active and passive safety
creased to produce 1500 MWe gross power outsystems. The first unit is planned to be completed by
put, but design shelved in favour of the evolutionary
2017.[31]
[20]
VVER-1200
In October 2013 the VVER-1000 (AES-92) design was
• VVER-TOI is aimed at development of typical opti- selected by the Jordan Atomic Energy Commissionin a
mized informative-advanced project of a new gener- competitive tender for Jordan’s first twin reactor nuclear
ation III+ Power Unit based on VVER technology, power station.[32]
5
7
Gallery
Operated reactors
NPP Leningrad VVER-1200
NPP Balakovo VVER-1000
NPP Novovoronezh VVER-1200
NPP Rivne VVER-1000
NPP Novovoronezh VVER-1200
Canceled/Closed Power Plants
NPP Khmelnytsky VVER-1000
NPP Stendal VVER-1000
NPP Balakovo VVER-1000
NPP Żarnowiec VVER-440
NPP Kudankulam VVER-1000
Power Plants under construction
6
9
REFERENCES
[9] Martti Antila, Tuukka Lalitinen. “Recent Core Design
and Operating Experience in Loviisa NPP” (PDF). Fortum Nuclear Services Ltd, Espoo, Finland (IAEA). Retrieved 20 September 2011.
[10] “Modernization works begin at Russia’s oldest VVER1000”. Nuclear Engineering International. 30 September
2010. Retrieved 10 October 2010.
[11] “AES-2006 (VVER-1200)". Rosatom. Retrieved 22
September 2011.
NPP Juragua VVER-440
[12] V.G. Asmolov (10 September 2009). “Development
of the NPP Designs Based on the VVER Technology”
(PDF). Rosatom. Retrieved 9 August 2012.
[13] “WWER-1000 reactor plant (V-392)". OKB Gidropress.
Retrieved 22 September 2011.
[14] "$10 billion construction contract signed for two AES
2006 Russian reactors in Belarus”. I-Nuclear. 19 July
2012. Retrieved 8 August 2012.
[15] “Rosatom buys into Fennovoima”. World Nuclear News.
28 March 2014. Retrieved 29 March 2014.
NPP Greifswald VVER-440
8
9
[16] V.G. Asmolov (26 August 2011). “Passive safety in
VVERs”. JSC Rosenergoatom (Nuclear Engineering International). Retrieved 6 September 2011.
See also
• Russian floating nuclear power station
[17] “Advanced Nuclear Power Reactors”. World Nuclear Association. September 2011. Retrieved 22 September
2011.
• VBER-300
[18] “MIR.1200”. ŠKODA JS. Retrieved 23 September 2011.
[19] “MIR-1200”. OKB Gidropress. Retrieved 22 September
2011.
References
[1] “Kudankulam nuclear plant starts generating power, connected to southern grid - The Times of India”. The Times
Of India.
[2] “Historical notes”.
September 2011.
OKB Gidropress.
Retrieved 20
[3] “WWER-type reactor plants”. OKB Gidropress. Retrieved 25 April 2013.
[4] Prof. H. Böck. “WWER/ VVER (Soviet designed
Pressurized Water Reactors)" (PDF). Vienna University
of Technology. Austria Atominstitute. Retrieved 28
September 2011.
[5] Nikolay Fil (26–28 July 2011). “Status and perspectives of VVER Status and perspectives of VVER nuclear power plants nuclear power plants” (PDF). OKB
Gidropress. IAEA. Retrieved 28 September 2011.
[6] “Rosatom Intends to Certify VVER in Great Britain and
USA”. Novostienergetiki.re. 6 June 2012. Retrieved 21
June 2012.
[7] Svetlana Burmistrova (13 August 2013). “Russia’s
Rosatom eyes nuclear contracts in Britain”. Reuters. Retrieved 14 August 2013.
[8] Cogeneration in the Former Soviet Union; June 24 1997
[20] “WWER-1500 reactor plant”. OKB Gidropress. Retrieved 22 September 2011.
[21] "Создание типового проекта оптимизированного
и информатизированного энергоблока технологии
ВВЭР (ВВЭР-ТОИ)". Rosatom Nuclear Energy State
Corporation.
[22] “Bulgarian Parliament Votes to Abandon Belene Nuclear
Plant”. worldnuclearreport.org. 27 Feb 2013. Retrieved
22 Sep 2014.
[23] Anton Khlopkov and Anna Lutkova (21 August 2010).
“The Bushehr NPP: Why did it take so long” (PDF). Center for Energy and Security Studies. Retrieved 1 March
2011.
[24] http://www.world-nuclear.org/info/Country-Profiles/
Countries-A-F/Finland/
[25] Kudankulam becomes India’s first nuclear plant to generate 1,000MW power
[26] “New life of Novovoronezh 3”. Nuclear Engineering International. 3 June 2002. Retrieved 9 March 2011.
[27] Tianwan fuel fabrication moves to China; March 2010
[28] Russian-Chinese nuclear station safest in the world:
IAEA, RussiaToday, 2007-12-07
7
[29] “Arrangements Completed for Nuclear Power Plant”.
Turkish Weekly. 15 August 2011.
[30] "Генплан размещения первой турецкой АЭС
разработают осенью 2011 года (Master plan of placing
the first Turkish nuclear power plant will develop a
fall 2011)". Ria Novosti. 22 August 2011. Source for
"четырех энергоблоков с реакторами ВВЭР−1200 по
российскому" or “four VVER-1200 reactors”
[31] “Russia signs up to build NPP in Belarus”. Nuclear Engineering International. 20 October 2011. Retrieved 24
October 2011.
[32] “Jordan selects its nuclear technology”. World Nuclear
News. 29 October 2013. Retrieved 2 November 2013.
10
External links
• WWER-type reactor plants, OKB Gidropress.
• AES-2006 (VVER-1200), Rosatom.
• VVER Reactor at Virtual Nuclear Tourist.
8
11
11
TEXT AND IMAGE SOURCES, CONTRIBUTORS, AND LICENSES
Text and image sources, contributors, and licenses
11.1
Text
• VVER Source: https://en.wikipedia.org/wiki/VVER?oldid=651681109 Contributors: Ray Van De Walker, Andrewa, Katana0182, Balcer, EugeneZelenko, Berkut, Bender235, Nk, JanSöderback, Rwendland, Xmort~enwiki, Brhaspati, Rjwilmsi, TheRingess, Smithfarm,
Lcolson, FlaBot, Ysangkok, Simesa, Vmenkov, YurikBot, Midgley, Limulus, Jengelh, Gaius Cornelius, Los688, Adamrush, Ospalh,
Brozen, Cassini83, Petri Krohn, Mikus, Sardanaphalus, SmackBot, Eskimbot, Chaojoker, Marc Kupper, Ottawakismet, Hibernian, Chlewbot, Enr-v, SashatoBot, Arnoha, PhoenixHallow, Jkausel, CmdrObot, Tec15, Q43, MPorciusCato, AntiVandalBot, Corella, Lklundin,
JAnDbot, Beagel, MarkBA~enwiki, CommonsDelinker, Tulkolahten, Aleksandr Grigoryev, C1010, KylieTastic, VolkovBot, Indochinetn,
GRindala~enwiki, Geeperzcreeperz, SieBot, Timothy Cooper, BlackSlivers, Afernand74, VargaA, Rhatsa26X, Arjayay, Hamishnz, Addbot, SpellingBot, ChNPP, Luckas-bot, Yobot, ArthurBot, LilHelpa, Xqbot, Rsmn, Huunta, Filippo83, Jonesey95, King Zebu, RedBot,
Nora lives, IRISZOOM, Hullernuc, RjwilmsiBot, John of Reading, WikitanvirBot, Dwalin, Tom120, ZéroBot, Canelvan, Knowing guy,
Thompn4, Mmarre, Tarduyabgu, Asauers, Васильев Виктор Николаевич, BattyBot, Dust of the world, BigJolly9, Tony Mach, Yilku1,
NukePolicyWonk and Anonymous: 79
11.2
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