SVBR-100: GENERATION IV SMALL MODULAR MULTIPURPOSE NUCLEAR REACTOR 2014

RUSSIA'S FIRST INNOVATIVE PROJECT IN NPP DEVELOPMENT CONDUCTED IN THE FORMAT OF PUBLIC-PRIVATE PARTNERSHIP The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. 2 2 Basic Element - diversified industrial group made up of over 100 Russian and international companies 50% Еstablished in 2009 as a public – private partnership. State Atomic Energy Corporation Rosatom Capacity100 MW-e Steam parameters580 tons/hour, saturated steam, p=6.7Mpa, T~282.9°C Municipal heatMore than 100 Gkal/hour Desalinated waterMax tons/day Fuel campaign duration7-8 years (for UO2 fuel with 16,3% enrichment) Reactor weight~280 tons Reactor dimensions4.5 m. diameter/ 8.2 m. height Useful lifetime60 years

MULTI-PURPOSE APPLICATION The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. 3 Construction of small and medium dual application complexes (power and heat) in local and remote areas with poor energy infrastructure Coastal desalination nuclear power complex comprising two types of onshore desalination plants (multi-layered distillation and reverse osmosis). Renovation allows to minimize capital costs per unit two fold as compared with the construction of new capacities. FLEXIBLE CAPACITY FOR LOCAL AND REMOTE AREAS: GRADUAL BUILD-UP MULTIPURPOSE INDUSTRIAL APPLICATION DESALINATION RENOVATION Example of possible allocationIndustry Oil and gas and chemical complex (Primorsky kray.) Oil & Gas Zheleznorudniy Ore Mining and Processing Industrial Complex (Buryatiya) Metal industry “Peschanka” gold field development (Chukotsky region) Mining *) The results of the complex study of technical feasibility and economic viability of the renovation of the 2nd, 3rd and 4th units of SVBR-100 based Novovoronezhskaya NPP Steam: 580 tons/hour, saturated steam, p=6.7Mpa, T~282.9°C Distillated water: – m 3 /day

SMR MARKET FORECASTED TO REACH 35 GW BY 2030 The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. 4 AVAILABILITY FOR RUSSIAN NUCLEAR POWER Argentina Japan Iran Southern Africa Ukraine Indonesia Kazakhstan UK Canada Brazil France Egypt Oman Algeria Taiwan Czech Republic Southern Korea Pakistan Malaysia Romania Mexico Nigeria Thailand Turkey Kuwait Poland Saudi Arabia India Russia USA China Venezuela Maroc Bulgaria Belarus UAE Tunis Azerbaijan Bangladesh Columbia ABILITY FOR SMR APPLICATIONHIGH. LOW. HIGH. LOW. MEDIAN Priority markets (size of circle corresponds with market size) Definition of priority markets SMRs market capacity, (BASE CASE) Sources: Platts, The World Bank, IAEA, WNA, expert assessments, Roland Berger Strategy Consultants, for more details please consider appendix 11,7 7,4 4,4 2,3 2,0 1,8 1,3 1,2 0,7 [GW] China India Russia Brazil Poland Indonesia S. Africa Kazakhstan Turkey Consensus forecast of SMR market volume till 2030 (including co-generation and desalination) is up to 35 GW of installed capacity or up to 200 US dollars 4

FOUR SVBR COMPETITIVE ADVANTAGES 5 The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. Electricity supply Heat supply Desalinated water Steam supply for industrial needs Combination of active and passive safety systems Chemically inert both to water and air lead-bismuth coolant Integral reactor layout Near-atmospheric pressure inside primary circuit Accident even with a loss of containment could not lead to radioactive emissions into the atmosphere Can operate in closed nuclear fuel cycle mode reducing consumption of uranium ore and nuclear waste output. ADVANCED SAFETY BROAD APPLICATION SUSTAINABLE DEVELOPMENT Small dimensions - transportable by rail way, road or waterway Modular design 100MWe *n – NPPs customized to local needs Possibility of deployment near residential area (less than 1 km) Fewer requirements to local energy infrastructure FLEXIBLE APPROACH

TECHNICAL SPECIFICATIONS The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. 6 Capacity100 MW-e, 280 MW-t Thermal output100 Gkal/hour Steam parameters580 tons/hour, saturated steam, p=6.7Mpa, T~282.9°C Desalinated water – m 3 /day Power plant efficiency36% Design availability factor90% Fuel campaign 7-8 years (for a standard UO 2 fuel, 16.3% enrichment) *) other types of fuel are also applicable, including MOX- fuel and closed nuclear fuel cycle with near self-sustainment mode Reactor module weight~280 tons Reactor module dimensions 4.5 / 8.2 meters (diameter/height) **) produced and assembled on the factory with relatively small dimensions which allows it to be transported by the railways, vehicles or sea Lifetime for reactor vessel60 years Load following capability0.5-2%Nnom per minute in % power range Seismic design For structures and pipelines: horizontal PGA=0,12 g (7-point on MSK scale), For reactor module equipment: horizontal PGA=0,25 g (8-point on MSK scale) Predicted reactor vessel damage frequency 1×10-7/reactor year

SAFETY FEATURES: ADVANTAGES OF PB-BI COOLANT The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. 7 WaterSodiumPb / Pb-Bi Maximal potential energy, GJ/m3, incl.: Temperature Thermal energy / incl. compression potential energy P = 16 Mpa Т = 300 ºС Т = 500 ºС ~ 21,9 ~ 10 ~ 1,09 ~ 0,90/~ 0,15 (PWR) ~ 0,6/None ~ 1,09/None Potential Chemical energy of interaction Potential chemical energy of interaction of released hydrogen with air With zirconium ~11,4 With water 5,1 With air 9,3 None ~ 9,6 ~ 4,3None Т = 490 ºС Coolant potential energy strongly influences the number and complexity of the safety systems and can display its impact in case of accidents Parameters /Coolant type

SAFETY FEATURES AND INTERNATIONAL NUCLEAR REGULATION COMPLIANCE OF SVBR The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. 8 Coolant evaporation Inability to remove Fuel afterheat Growth of temperature in the reactor core Fuel rods zirconium casing interaction with water Hydrogen extraction & explosion TMIChernobylFukushima SVBR – 100 – is an “after” Chernobyl & TMI & Fukushima NPPs designed up to “the lessons learned” SVBR Not possible Not possible in significant quantities SVBR design features t b = 1670ºC Heat removal by natural circulation of LBC with heat transfer to tank water + 72 hours of non- interference No zirconium (steel casing)

PROJECT STATUS The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. 9 Construction Concept design Design and engineering Operation and Commercialization Obtained the status of the operating organization Establishment of AKME- engineering Public hearings passed successfully Obtained the status of a nuclear market participant Site identified for the construction of the pilot unit Project documentation finished License for construction of the pilot unit obtained First concrete Operating license obtained Physical start Power start Selection and contracting of suppliers of major systems and equipment executed License for the placement obtained Construction and installation work

NPP PROJECT WITH SVBR-100 PILOT UNIT CONSTRICTION 10 The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. Prototype nuclear plant is to be constructed in Dimitrovgrad, Ulyanovsk region  1 unit  Co-generation mode  Installed electric capacity: 100 MW(e)  Heat capacity: 100 Gcal/h  Efficiency factor: ~36%  Working time: 50 years  ICUF*: ~90% Dimitrovgrad  Positive resolution of public hearing  Authorized site (signed rental agreement)  Collaboration agreement with regional government FIRST OF A KIND SVBR NPP PARAMETERS: EVENTS BEHIND:

LEADING RUSSIAN ENTERPRISES ARE INVOLVED IN THE PROJECT 11 The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering.  Chief Designer  Designer of reactor (integrator) Institute for Physics and Power Engineering named after A. I. Leypunsky  Scientific director;  Designer of the reactor core cooling technologies and systems TVEL Russian Research and Design Institute for Power Technologies (VNIPIET)  General designer of the pilot unit  Fuel supplier Central Design Institute of Machinery (CKBM)  Constructor of the main circulation pump and refueling machine  Experimental study of the core elements and structural materials Scientific Research Institute of Atomic Reactors (NIIAR) Experimental and Design Organization Gidropress Established: 1946 Established: 1954 Established: 1933 Established: 1996 (managing company) Established: 1945 Established: 1956

AKME-ENGINEERING BOARD OF DIRECTORS 12 The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. Deputy CEO for Innovation Management Rosatom Director General Rusatom Overseas Director General AKME-engineering Deputy Director of the Block for Innovation Management Rosatom Oleg Deripaska Chairman of the Board of Directors President of En+ Group Gulzhan Moldazhanova CEO of Basic Element Vladimir Petrochenko Vyacheslav Pershukov Dzhomart Aliev Alexander Tuzov

CONTACT INFORMATION 13 The content of this presentation is for discussion purposes only. It shall not be considered as an offer and doesn’t lead to any obligations to AKME-engineering. JSC «AKME-engineering» Tel. +7 (495) , Fax +7 (495) Pyatniskaya str. 13 bld.1, Moscow Russia /