1 Seventh International Scientific & Technical Conference (MNTK-2010) Moscow, 26 – 27 May 2010 Russian Nuclear Power in the Ever-changing World V.G. Asmolov.

Slides:



Advertisements
Similar presentations
Dr. Kamal Kant Dwivedi Counselor (S&T) Embassy of India Washington DC,
Advertisements

Electrical Engineering Department, Amirkabir University of Technology, Tehran, Iran M. Poursistani N. Hajilu G. B. Gharehpetian M. Shafiei CHP Systems.
May 2010 FEDERAL SCIENTIFIC PRODUCTION CENTER JSC “Afrikantov OKBM” EFFECTIVENESS EVALUATION FOR THE FAST SODIUM- COOLED REACTOR DESIGN SOLUTIONS AND THEIR.
1 7-th INTERNATIONAL SCIENTIFIC AND TECHNICAL CONFERENCE VVER technology development prospects V.A.Sidorenko RSC “Kurchatov Institute” Moscow, Moscow,
Outlook for the Requirements of the Nuclear Power Plant Irradiation Test in China SONG DANRONG Nuclear Power Institute of China.
1 ACPR Advanced, cost competitive, proven technology, and reliable The Third Generation Nuclear Reactor.
EStorage First Annual Workshop Arnhem, NL 30, Oct Olivier Teller.
1 EERMC Public Meeting on Combined Heat and Power September 17, 2013.
May 22nd & 23rd 2007 Stockholm EUROTRANS: WP 1.5 Task Containment Assessment IP-EUROTRANS DOMAIN 1 Design WP 1.5 Safety Assessment of the Transmutation.
Maximizing production efficiency for existing and new power infrastructure: Enel experience in Russia and technologies Enrico Viale Chief Executive Officer,
Indian strategy for management of spent fuel from Nuclear Power Reactors S.Basu, India.
© ABB Group August 13, 2015 | Slide 1 Power Generation Service Life Cycle Management for Power Plants Daniel Looser, Power Gen Europe in Amsterdam, June.
Getting Green Building Automation. Why is Building Automation a Green Technology? There are programs starting all over the nation that focus on alternative.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/2 Design Geoff Vaughan University of Central Lancashire,
Siemens sans siemens sans bold siemens sans italic siemens sans italic bold siemens sans black siemens black italic Siemens Building Technologies.
“ Second Moscow International Nonproliferation Conference PLUTONIUM UTILIZATION IN REACTOR FUEL A. Zrodnikov Director General State Scientific Center of.
SUSTAINABLE ENERGY REGULATION AND POLICY-MAKING FOR AFRICA Module 13 Energy Efficiency Module 13: SUPPLY-SIDE MANAGEMENT.
INTERNATIONAL CONFERENCE ON FIFTY YEARS OF NUCLEAR POWER – THE NEXT FIFTY YEARS 27 June – 2 July 2004 NUCLEAR POWER SAFETY: THE PRESENT AND ASSURANCE FOR.
Secondary circuit heat-exchange equipment efficiency improvement
R I Facer, NENP-NPTDS, IAEA
Office of Nuclear Energy U.S. Department of Energy
Overview of Conventional 2-loop PWR Simulator. PCTRAN Dr
Advanced Test Reactor.
1 Current Status and Development Plans for the Nuclear Power Sector in Russia: Generation Capacity, and Fuel-cycle Approaches.
Chapter 4 Nuclear Energy. Objectives Describe how nuclear fuel is produced. List the environmental concerns associated with nuclear power. Analyze the.
Generation Aino Ahonen CABABILITY OF APROS IN THE ANALYSES OF DIESEL LOADING SEQUENCES E. Raiko, H.Kontio, K.Porkholm, presented by A. Ahonen.
Co- and Poly- generation Martin Hannemann Andi Prah Nuri Feichtinger Paul Polterauer.
NUCLEAR POWER PLANT FINANCING IAEA - Infrastructure Technical Meeting Vienna, November 2007 Fanny Bazile Forecast Director Nuclear Energy Division.
PBNC- 1 Overview of US Nuclear Energy Initiatives /06- 1 Harold McFarlane President American Nuclear Society.
08 October 2015 M. Ammar Mehdi Introduction to Human Resource Management & SSG-16 Actions 4 th Steering Committee on Competence of Human.
AREVA: Steps towards a global leadership in the energy industry
Nuclear Power Plants. History of nuclear power 1938– Scientists study Uranium nucleus 1941 – Manhattan Project begins 1942 – Controlled nuclear chain.
OVER 40 YEARS ON THE WORLD MARKET Over 40 Years at the World Market «New Russian initiatives in the nuclear energy and the global nuclear renaissance»
Ministry of Economy, Trade and Industry Experience and Future Activities for Introduction of Nuclear Power Masaomi KOYAMA Deputy Director Nuclear Energy.
4/2003 Rev 2 I.4.7 – slide 1 of 48 Session I.4.7 Part I Review of Fundamentals Module 4Sources of Radiation Session 7Nuclear Reactors IAEA Post Graduate.
Several problems in implementation of the investment programs in power industry Speaker: A.Y.Kopsov, Member of the “Nice Club”, Doctor of Technical Science,
Priority Programs of the Nuclear Power Industry Branch of Russia Vladimir Asmolov 17 th Symposium of AER on VVER Reactor Physics and Reactor Safety
1 Prospects of the Floating Nuclear Power Plant overseas projects State Atomic Energy Corporation “Rosatom” JSC “Concern Rosenergoatom” «Directorate for.
Management and Organisation of Electricity Use Electrical System Optimisation Belgrade November 2003.
Experience of fuel operation at Russian NPPs N.M. Sorokin, Yu.V. Kopyov, V.E. Khlentsevich, А.К. Egorov N.M. Sorokin, Yu.V. Kopyov, V.E. Khlentsevich,
Experience of new fuel assembly operation and perspectives of fuel cycle development for for NPP with VVER Author: Мokhov V. А. International scientific.
TACIS Project: R8.01/98 – TRANSLATION, EDITING AND DIFFUSION OF DOCUMENTS (Result Dissemination) Probabilistic Safety Analysis Technology (PSA) TACIS R3.1/91.
1 Nuclear Energy Division MIT Report on the Future of Nuclear Power in the United-States : review and discussion Eric Proust Director, Industrial Affairs.
NUCLEAR INDUSTRY OF RUSSIA TODAY AND TOMORROW S.I. ANTIPOV NUCLEAR SOCIETY OF RUSSIA 15-th Conference of the Pacific Nuclear Society October 15-20, 2006.
ENERGY FOR THE 21 ST CENTURY the Potential for Nuclear Power Luis Echávarri Director-General, OECD Nuclear Energy Agency IAEA Scientific Forum at the General.
11 International Cooperation in the Nuclear Fuel Market as a factor of increasing the Security of Supply Moscow, 2009.
OPPORTUNITIES FOR CZECH COOPERATION WITH ROSATOM
International Atomic Energy Agency 1 Grid, Industrial involvement and procurement Akira OMOTO DIR, NENP.
Regional Meeting on Applications of the Code of Conduct on Safety of Research Reactors Lisbon, Portugal, 2-6 November 2015 Diakov Oleksii, Institute for.
Westinghouse Non-Proprietary Class 3© 2015 Westinghouse Electric Company LLC. All Rights Reserved. 1 Graham Cable Vice President, New Plant Development.
October 2002, Lille, France1 First Deputy Minister of the Russian Federation of Atomic Energy M.I. Solonin CURRENT STATUS AND PROSPECTS OF NUCLEAR POWER.
2nd Workshop on PGI in NEA, May , Shenzhen, China 1 “RFE-NEC-DPRK-RK” POWER GRID INTERCONNECTION Sergei Podkovalnikov Energy Systems Institute,
DEVELOPMENT OF THE NATIONAL INFRASTRUCTURE FOR NUCLEAR POWER IN VIETNAM DEVELOPMENT OF THE NATIONAL INFRASTRUCTURE FOR NUCLEAR POWER IN VIETNAM Vuong Huu.
J. G. Weisend II for the ESS Team Energy Efficiency & Recovery at ESS.
E.ON Russia Production management September 2013 Deputy General Director on production Igor Popov.
Strategic Development of Power Generation in the Context of “Energy Strategy for the Year 2030” Chisinau - September 2010 Al. Gribincea PhD World economy,
NUCLEAR REACTORS G. HETSRONI Emeritus Danciger Professor of Engineering Technion – Haifa – Israel.
Introduction to Nuclear Energy Candace Davison Senior Reactor Operator Penn State University.
Logistics. 英语班级: 08 级 1B6 专业:物流管理 组员: 温凯靖 王蒙露 叶雯雯 马昀 王晓 林.
04/16/ Planning New Generation APPA Operations & Engineering Conference April 10, 2006 Jay Hudson, PE Manager, Environmental Management.
NuScale Generator A Practical Energy Alternative for the Future
DDG Nuclear Energy: Mr Zizamele Mbambo
Nuclear power development in Nordic area - Fennovoima project
IAEA PERSPECTIVE ON THE FUTURE OF NUCLEAR POWER
IAEA International Conference on Fifty Years of Nuclear Power – The next Fifty Years Moscow - Obninsk, Russian Federation - June 28, 2004 Nuclear.
Offerings for design safety from harmonization
Improving Energy Reliability & Performance
Improving Energy Reliability & Performance
Session Name: Lessons Learned from Mega Projects
Comparison of Performance Indicators of Different Types of Reactors Based on the ISOE Data H. Janžekovič, M. Križman.
Presentation transcript:

1 Seventh International Scientific & Technical Conference (MNTK-2010) Moscow, 26 – 27 May 2010 Russian Nuclear Power in the Ever-changing World V.G. Asmolov

2 Russian NPPs in commercial operation NPPs, 32 Units, N inst. = MW

33 Electricity generation by Russian NPPs

44 Load Factor of Russian NPPs

55 Load Factor at Russian NPPs in 2009

66 Execution of the planned target for electricity generation at Russian NPPs in 2009 (% and mln. kW-h)

77 Trend of operational events at Russian NPPs

88 Trend of events with scrams at Russian NPPs

99 Radioactive noble gases releases from NPPs in 2009 (% of the allowed release level) New limits for allowed release introduced (by SP AS-99 standard) On-line data for 2009

10 Collective doses at NPPs for different reactor types (man-Sv/Unit)

11 Summary of the year 2009 ►Nuclear power units safe operation has been ensured ►The maximum electricity generation level of bln kW-h (100.6% of the FTS balance target) has been achieved ►The maximum generation capacity of MW has been attained ►Load Factor of 80.2 % has been reached (79.5% in 2008) ►Availability Factor of 83.6 % has been reached (82.2% in 2008)

12 Production targets for 2010 Planned generation as per FTS balance target bln kW-h Load Factor - 81,3 %

13 Electricity generation increase at the operating nuclear power units is achieved by implementation of relevant measures in the following areas: ►Reliability improvement; ►Nuclear power units efficiency factor raise; ►Thermal power increase; ►Reduction of overhaul and mid-life repair terms; ►Thermal efficiency improvement for thermomechanical equipment; ►Operation life extension for NPP units. Electricity generation increase

14 The gradual comprehensive upgrading plan for VVER-1000 power units ReactorSteam GeneratorTurbineGenerator ►Reduction of conservatism in defining the design basis and operational limits. ►Reduction of linear power release in a fuel element by means of axial and radial profiling. ►Fuel assembly modernization. ►Upgrading the steam separation system. ►Evaluation of internal SG pressure raising feasibility. ►Evaluation of feasibility of SG replacement with a more efficient one. ►Upgrading the flow-through part and optimization of the thermal circuit. ►Enhancement of the feedwater recovery system for efficiency factor improvement purpose. ►Upgrading in order to obtain a maximum possible electric power. ►Evaluation of feasibility of the generator replacement.

15 Reduction of conservatism in the VVER-1000 power capability evaluation Parameter Value at presentConservatism reduction Measures towards conservatism reduction 1. K r – fuel element power nonuniformity coeff. 1,521,48 Fuel load optimization 2. q тв - fuel element power capability, KW Reduction of conservatism in the accident analysis domain 3. F общ (q тв ) - margin coefficient 1,171,11 Ensuring the overall 95% probability of being within the limits доп As a result thermal power can be increased by 12%

16 Phases of Russian Nuclear Power Development in Post-Chernobyl Period ►1992 – the “survival” period ►2004 – nuclear “renaissance” ►2008 – global financial crisis ►2010 onward- end of recession period and post-crisis development

17 Russian NPPs built in the “survival” period 1993 – Balakovo NPP Unit – Kalinin NPP Unit – Volgodonsk NPP Unit 1

18 Foreign NPPs of the “survival” period Tianwan NPP (China) Bushehr NPP (Iran) Kudankulam NPP (India)

19 The “survival” period outcome ►R&D infrastructure and the knowledge for the basis technology (VVER and BN reactors) have been retained ►The technology and infrastructure for the construction of NPP power units, and the whole nuclear industry have been retained ►Severe accidents research programs have been carried out, and computer codes have been developed and verified ►New safety design features have been developed and tested

20 Safety database APPLICATION TO THE NUCLEAR INSTALLATIONS      Thermohydraulics - integral experiments Hydrogen (deflagration, detonation) RASPLAV, MASCA Melt - concrete interaction Thermomechanics of fuel elements   Thermomechanics of a reactor vessel Reactivity initiated accidents RESEARCH PROGRAMS IN RUSSIA with Western partners involvement RESEARCH PROGRAMS FACILITIES with Russian involvement AT WESTERN INTERNATIONAL PROGRAMS data bases, codes)( Thermohydraulics CAMP, ICAP OECD EU, IAEA programs NEA / EU, IAEA programs Severe accidents CSARP NEA / OECD             - Thermohydraulics - PMK (Hungary), PACTEL (Finland) Core damage - CORA (Germany) BETA (Germany), ACE (USA) Filters on the containment venting system -  Hydrogen - ACE (USA), TYPHOON (Germany) HDR(Germany) Melt-concrete interaction -

21 The public request for accelerated nuclear power development External conditions: ● Non-uniform distribution of fossil fuel resources ● Increased tension at global energy market Demonstration of developing consumer-oriented features of NPPs: ● guaranteed safety ● economic efficiency ● closed NFC  RW & SF management  fuel breeding Boundary conditions that determined the nuclear “renaissance”

22 Nuclear power globalization degree ►Five countries (U.S.A., France, Japan, Russia and Germany) altogether produce 70% of nuclear-generated electricity in the world. ►Light water reactors of three types (PWR, BWR, VVER) represent 80% of global reactor fleet. ►Five countries (Russia, France, Japan, China, India) are developing fast reactor technologies in an advanced phase. ►Six companies (Rosatom, URENCO, USEC, EURODIF, CNNC, JNFL) are performing commercial-scale uranium enrichment. ►Six countries (France, United Kingdom, Russia, Japan, China, India) have nuclear fuel reprocessing capacities.

23 - red line separates the units with guaranteed financing - blue line designates the mandatory power unit commissioning programme Kola, Unit 2 Kola, Unit 1 LNPP, unit 2 LNPP Unit 1 Mandatory programme Mandatory and supplementary programmes Installed capacity by 2020, GW Capacity to be commissioned, GW Kola-II Unit 1 Kola-II Unit 2 Central, Unit 1 Kola-II, Unit 3 Kola-II, Unit 4 Prim., Unit 1 Prim., Unit 2 To be decommissioned: 3.7 GW NPP construction roadmap according to the General Plan till 2020 February 2008 Rostov, Unit 2 completion Kursk, Unit 5* completion Kalinin, Unit 4 completion NVoronezh-II, Unit 1 Beloyarsk, Unit 4 BN-800 Leningrad-II, Unit 1 Rostov, Unit 3 Seversk, Unit 1 Tver, Unit 1 Rostov, Unit 4 Nizhniy Novorod Unit 1 South Urals, Unit 1 NVoronezh-II, Unit 2 NVoronezh-II, Unit 3 Nvoronezh-II, Unit 4 Leningrad-II, Unit 2 Leningrad-II, Unit 3 Leningrad-II, Unit 4 Tver, Unit 2 Tver, Unit 3 Tver, Unit 4 South Urals, Unit 2 South Urals, unit 3 South Urals, Unit 4 Seversk, Unit 2 Nizhniy Novorod, Unit 2 Nizhniy Novorod, Unit 3 Nizhniy Novorod, Unit 4 Central, Unit 2 Central, Unit 3 Central, Unit 4 NVNPP, Unit 3 NVNPP, Unit 4

24 NPPs in operation NPPs under construction Prospective NPPs NPP siting in accordance with the General Plan Bilibino Vilyuchinsk (PATES) Primorye Kola Pevek (PATES) Seversk South Urals Leningrad Kalinin Balakovo Beloyarsk Rostov Kursk Tver Smolensk Novovoronezh Nizhniy Novgorod In operation - 31 units Under construction - 10 units (including floating units - PATES) Prospective - 28 units (including floating units - PATES) Upgrading - 14 units Decommissioning - 9 units (including Bilibino NPP) Central Baltic Power unit information

25 The AES-2006 design is the basis for implementation of the General Siting Plan “roadmap”

26 ● Thermal power has been increased up to 3200 MW and Efficiency factor (gross) of a power unit has reached 36.2%, due to: ▬ elimination of excessive conservatism ▬ improvement of steam turbine thermal circuit ▬ improvement of steam parameters at the steam generator outlets and decrease of pressure losses in steam lines ● Economic efficiency has been improved by means of: ▬ optimization of passive and active safety systems used in AES-91 and AES-92 designs ▬ unification of the main equipment; ▬ decrease of materials consumption AES-2006 – the targets reached

27 Negative effects of the world financial crisis ►Industrial production shrinkage ►Energy consumption recession ►Grid restrictions and NPP generation reduction ►Decreased profits and reduced investments in construction of new NPPs

28 As both the economics and electricity demand will be recovered, it is expected to build: Central NPP; Nizhniy Novgorod NPP; Seversk NPP; South Urals NPP; Tver-II NPP Rostov NPP power unit 2 Kalinin NPP power unit 4 Novovoronezh-II NPP Power unit 1 Leningrad-II NPP power unit 1 Rostov NPP Power unit 3 Leningrad-II NPP power unit 2 Rostov NPP Power unit 4 Leningrad-II NPP power unit 3 Baltic NPP power unit 2 Leningrad-II NPP power unit 4 Beloyarsk NPP Power unit 4 (BN-800) Novovoronezh-II NPP Power unit 2 Baltic NPP Power unit 1 NPP units currently under construction

29 NPPs under construction – current status ►Completion of NPPs with VVER-1000 reactors: - Rostov NPP, power units 2, 3 and 4 - Kalinin NPP, power unit 4 ►Construction of NPPs of the AES-2006 design: - Novovoronezh-II NPP, power units 1 and 2 - Leningrad-II NPP, power units 1 and 2 ►Construction of NPP with BN-800 reactor: - Beloyarsk NPP, power unit 4 ►Construction of floating nuclear cogeneration plant (PATES) with KLT-40 reactor (Vilyuchinsk)

30 Rostov NPP Units 2, 3 and 4 Rostov NPP Unit 2 Rostov NPP Units 3,4

31 Kalinin NPP Unit 4

32 Novovoronezh-II NPP

33 Leningrad-II NPP

34 Beloyarsk NPP Unit 4

35 Floating nuclear cogeneration plant (PATES)

36 NPP-2006 siting licenses for new sites NPPLicense obtaining date Seversk NPP Nizhniy Novgorod NPP3 rd quarter of 2010 Tver NPP3 rd quarter of 2010 Leningrad-II NPP (Units 3 and 4)2 nd quarter of 2010 Baltic NPP Central NPP2 nd quarter of 2010

37 Main areas of optimization in AES-2006 Economic requirements and boundary conditions of the Customer Basis – AES-2006 design Reactor unit Turbine hall Heat exchangers Safety systems Auxiliary systems: Ventilation, Radwaste Automated process control system AES-2010 (VVER-SOC) Design is not changed. Removal of conservatism Variability. Optimization. Simplification of the design and completion of passive safety justification Optimization Development in accordance with the adopted design Significant upgrading (there is a significant back-up)

38 Development areas for AES-2010 concept design AreaComments Cost and risks analysis for introduction of new advanced plant equipment and systems : - reduced number of control rods; R&D works accomplished - introduction of new main circulation pumps (water lubrication, one-speed motor); R&D works to be accomplished in implementation of new steel for pressure vessels; R&D works to be accomplished in 2011

39 Development areas for AES-2010 concept design (continuation) AreaComments - implementation of new set of heat exchanging equipment of collector-platen type; The collector-platen arrangement of heat exchanging devices will allow to reduce metal consumption - transition to a deaeratorless layout of the secondary circuit; The transition will allow to achieve significant savings as regard to Turbine hall equipment & systems - introduction of heat accumulators to ensure maneuverable parameters of a power unit Application of heat accumulators will enable the NPP power units involved in maneuvering regimes to maintain the high LF levels and up-to-date fuel cycle parameters

40 Development areas for AES-2010 concept design (continuation) AreaComments - abandon the demineralizer use, or transition to low- capacity demineralizers; This is connected with application stainless steels or titanium for heat exchanging surfaces in the secondary circuit and with transition to ethanolamine- based water chemistry - optimization of the secondary circuit feedwater system arrangement Introduction of feedwater pump capacity control by means of smooth variation of pump rotation speed. Analysis of application of: - a high-speed rotating turbine drive, a frequency- controlled motor drive; - a motor drive with hydraulic clutch

41 Development areas for AES-2010 concept design (continuation) AreaComments - implementation of MOX fuel Analysis of feasibility to implement the EUR requirement concerning MOX fuel use - introduction of hydrogen-potassium water chemistry for the primary circuit coolant Will allow to: - minimize equipment composition and dimensions; - optimize service parameters of the water chemistry maintenance systems; - reduce significantly volume of process waste being generated

42 ● Low efficiency in beneficial use of mined natural uranium – less than 1% ● Continuously growing volumes of SNF and RW Systemic problems of the modern nuclear power

43 1.Economical efficiency 2.Guaranteed safety 3.No limitations in regard to a raw materials base for а historically significant time span 4.SNF and RW management – the NP fuel cycle is to be organized in a way ensuring safe ultimate RW confinement 5.Energy production scale – the share in the national electricity market should be not less than 30% 6.Energy production structure is to ensure an opportunity to expand the markets Requirements to a nuclear power system (NPS)

44 A power unit of the 4 th generation with a sodium-cooled fast reactor: ►Complying with the requirements of large- scale nuclear power in areas of fuel utilization and minor actinides management ►With improved technical, economic performance and safety features

45 Requirements to VVER technology development aimed at its application in combination with breeder reactors within the closed NFC: Fuel utilization (Breeding Ratio) Efficiency coefficient Investment payback terms

46 Target features of an innovative NPP unit based on the traditional VVER technology ►Fuel utilization – possibility of operation with breeding ratio (BR) of ~ 0.8 – 0.9 and natural uranium consumption of 130 – 135 t/GW(e) per year ►Thermodynamic efficiency - improvement of the efficiency coefficient by optimization of the steam generator design and by the maximum possible increase of steam parameters ►Investment payback – shortening of the construction period down to 3.5 – 4 years due to the enlarged industrial modular fabrication

47 Today Mid of 21-st century Basic electricity supply Electricity supply, extra fuel breeding Electricity supply + fuel breeding Heat supply + electricity High potential heat, new energy carriers VVER-440 NPPs, VVER-1000 NPPs RBMK NPPs BN-600 NPP Bilibino NHPP Open nuclear fuel cycle AES-2006, AES-2006М NPPs with VVER-1000 NPPs with Super-VVER for operation in CNFC with BR ~ 0.9 BN-800 NPPs commercial breeders Regional NHPPs with small- and medium-size reactors High-temperature reactors Closed nuclear fuel cycle Perspective pattern of Russian nuclear power system