Innovative Nuclear Concepts Workshop Liblice, Czech Republic April 10--13, 2012

1. Post-Fukushima Trends in Russian Nuclear EnergyA.Yu. GagarinskiyNational Research Centre “Kurchatov Institute” Innovative Nuclear Concepts Workshop Liblice, Czech Republic April 10--13, 2012

2. 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)

3. 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

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

5. 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). Floating nuclear power plantwith KLT-40S reactors FNPP launching, June 2010

6. 250 200 150 100 50 0 2005 2010 2015 2020 2030 2040 2050 MIN scenario MAX scenario (el) MAX scenario (non-el) 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. GWe

7. Russian nuclear energy technology prospects VVER-1300 (TOI) VVER-SUPER VBER-500 HTGR VVER-600 Fast reactors Thermal reactors Alternative SFR 100 MW 300-700 MW 1000 MW concepts FNPP, KLT-40 New icebreakers, RITM-200 Federal programs, Rosatom decisions Initiative designs BN-800 BN-1200 BREST-300 (Pb) MSR SVBR-100 (Pb-Bi) 2010 2015 2020 2025 2030 2035

8. 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 VVER technology for medium-sized reactors Use of VVER operation experience Use of developed ship reactor technology: operation experience over 6000 reactor years Maximum use of AES-2006 development experience Guaranteed safety: use of AST developments VBER-500 (OKBM) VVER-600 (OKB Gidropress) (AES-2006/2)

9. 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).

10. 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.

11. 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.