Post-Fukushima Trends in Russian

Nuclear Energy A.Yu. Gagarinskiy

National Research Centre “Kurchatov Institute”

Innovative Nuclear Concepts WorkshopLiblice, Czech Republic

April 10--13, 2012

Commissioning of Russian-design units expected in 2011

Bushehr-1(connected to grid – September 2011)

Kalinin-4(connected to grid – November 2011)

Kudankulam-1(physical startup postponed)

Expected commissioning dates for NPPs currently under construction in Russia

(as by the beginning of 2012)

Novovoronezh NPP-II Beloyarsk NPP (BN-800) Vilyuchinsk FNPP (2 KLT-40S)Unit 1 – 2013; unit 2 – 2015 2014 2014

Leningrad NPP-II Rostov NPP Baltic NPP Unit 1 – 2014; unit 2 – 2016 Unit 3 – 2014; unit 4 – 2017 Unit 1 – 2017; unit 2 – 2018

New NPPs to be built in Russia by 2020 under the General Scheme of Power Facilities

Floating nuclear power plant with KLT-40S reactors

Barge – 144 m long, 30 m wide, 21.5 thousand t displacement

KLT-40S – 35 MWe or 75 GCal/h

Lifetime – 40 years (12-year intervals between overhauls).

FNPP launching, June 2010

Technological content of Russia’s nuclear energy program

• Increasing VVER-based capacities;• Introducing fast breeder reactors in the nuclear energy

system, with practical implementation of the closed nuclear fuel cycle;

• Introducing nuclear capacities in energy-intensive branches of industry and municipal sector;

• Developing a system of medium-sized NPPs;• Developing small nuclear power plants for local and

regional energy supplies.

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VVER-1300 (TOI) VVER-SUPER

FNPP, KLT-40 New icebreakers,

RITM-200

BN-800 BN-1200

SVBR-100 (Pb-Bi)

BREST-300 (Pb)

VBER-500

VVER-600

HTGR

MSR

Russian nuclear energy technology prospects

Federal programs, Rosatom decisions

Initiative designs

Use of VVER technology for medium-sized reactors

The capacity range for this reactor category based on LWRs includes two development lines: using traditional VVER configuration and using the experience and technology from shipbuilding industry.A two-loop VVER-600 is being developed on the basis of VVER-1200 circuit; units are also offered with VBER reactors (250 to 500 MWe) based on the standard 100 MWe module.

Use of developed ship

reactor technology:

operation experience over

6000 reactor years

Guaranteed safety: use of AST developments

Use of VVER operation

experience

Maximum use of AES-2006 development

experience

VBER-500 (OKBM) VVER-600 (OKB Gidropress) (AES-2006/2)

RITM-200 reactor for universal nuclear icebreakers and floating nuclear power plants

OKBM Afrikantov has developed a detailed design of RITM-200 reactor facility (36 MWe) for floating NPPs and the new-generation universal icebreaker with variable draught (10.5–8 m). RITM-200 continuous operation period makes 26 000 hours (compared with 8000 hours for nuclear facilities of icebreakers currently in service).

SVBR-100 – fast neutron reactor with lead-bismuth coolant

Industrial power unit with fast neutron reactor and lead-bismuth coolant, developed on modular basis (100 MWe per module). Can operate on uranium oxide fuel or MOX. Is based on Russian submarine experience. Commissioning scheduled after 2017.

Fast neutron reactor with lead coolant

Development of this reactor design was launched to confirm the alternative fast neutron reactor technology with lead coolant. Construction of 300 MWe pilot unit is scheduled for 2020.