Sandor Tozser RRS Department of Nuclear Energy (NE) IAEA

Transcription

1 Nuclear Research: a Word Outlook (from IAEA perspective) Sandor Tozser RRS Department of Nuclear Energy (NE) Workshop on The Energy Problem: Status and Perspectives November, 2011 Pavia, Italy IAEA International Atomic Energy Agency

2 What would I like to talk about? Overview NPP roadmap (historical overview of NPP s generations in a nutshell) Challenges and international initiatives for advanced R&D on the field of nuclear research (NR) Highlight: structural material researches Challenges, objectives Role of IAEA Role of research reactors (RRs) Conclusion Remarks IAEA 2

3 NPP Roadmap Based on optimization of GEN-II types in safety and economics. Some units are already in operation, currently available on the market. Before 1970s, reactors using mainly natural uranium. GEN II Commercial reactors GEN III In coming years Are operation and currently available R&D process SCWR Super Critical Water Reactor VHTR Very-high Temperature GCR GCR Gas Cooled Fast Reactor Na FR Na-cooled FR LFR Pb(Bi) FR MSR Molten Salts Reactor Fusion for energy (ITER) GEN I Early prototypes Starting in the 70 s, light water reactors, currently in operation. Most units will reach the end of lifetime between IAEA 50s-60s 70s-80s 2000s Behind 2020 In R&D phase, six main concepts examined in international projects. Goal to have sustainable energy production. NPP generations

4 NPP P Generations (1/10) First Generation NPPs (features) Prototype units of the 50 s and 60 s Low unit capacities (<250 MW) Prototypes, or only few units constructed (except for Magnox) Deficiencies in safety Mainly natural uranium as fuel Exotic types FBR Fermi I., GCR Magnox, HWGCR Monts D'Arree, SGHWR Winfrith ith IAEA Dismantling Winfrith (UK) SGHWR 4

5 NPP P Generations (2/10) Second Generation NPPs (features) Developed from first generation types Only the safe and economic designs were kept (and the RBMK) Exotic types reappear after major development (FBR, gas- cooled, etc.) A certain level of standardisation, but the units still have several unique properties, p Commercial units, produced in large scale Most of currently operating units - mainly light water reactors (PWR and BWR about 88 % of units currently in operation). Few statistics on the next three slights IAEA 5

6 NPP P Generations (3/10) Second Generation NPPs (statistics - 1) As of NPPs in operation 433 NPP units Total electrical capacity: GW NPPs under construction 65 NPP units Total electrical l capacity: 62.6 GW Long term shutdown 5 NPP units Total electrical capacity: 2.8 GW IAEA 6 Source:

7 NPP P Generations (4/10) Second Generation NPPs (statistics - 2) Operational 84 (BWR) BWR No. of 2 Type Total MW(e) 17 FBR Units BWR (PWR) GCR FBR GCR LWGR PWR PHWR PWR Total: Under construction No. of Type Total MW(e) Units BWR FBR LWGR PHWR PWR IAEA Total: Source: 54 (PWR) LWGR PHWR BWR FBR LWGR PHWR PWR

8 NPP P Generations (5/10) Second Generation NPPs (statistics - 3) IAEA 8 Source:

9 NPP P Generations (6/10) Third Generation NPPs (features) Reactor types currently introduced to the market, advanced designs of Gen-II. Directions of development: To achieve economic competitiveness: reduce the costs of installation. Simplification, standardisation, modular structure, large sizes, shorter construction time (co-products: hydrogen, heat, desalination, etc.). Enhanced safety: probability of an accident has to be decreased, and the consequences should be reduced (development of active and passive SSs). Core Damage Frequency (CDM): < 10-5 /year (Gen-II: <10-4 /year; Gen-IV: <10-6 /year); Frequency of severe accident with significant emission: <10-6 /reactoryear Limited effects: (1) in the first 24 hours no emergency intervention needed outside the 800 m area; (2) outside 3 km area no emergency intervention needed at all; (3) food consumption limitation maximum 1-2 years, in very limited (small) area. Achieving non-proliferation goals: technological and/or administrative constraints focusing on security and non-proliferation objectives to improve global energy security (international initiatives, see later ). ) IAEA Constructions today (see next slide) 9

10 NPP P Generations (7/10) Third Generation NPPs (NPPs constructions today) Levels of advances (ways of progression ): Evolutionary reactor types (traditional engineering): Advanced type, based on existing designs, minor and medium modifications Intensive engineering tasks and tests needed Innovative (scientific achievements) types: Advanced type with breakthrough innovations in the design. Basic R&D needed, d feasibility studies, prototype/demo t unit should be built. Construction features Using: innovative, reliable, proven nuclear techniques Advanced designs are pre-licensed Combined construction and operation licenses (COL) Engineering maximized before construction New construction techniques Collaboration amongst project stakeholders Standard plant commitment Extensive use of information technology IAEA Containment Heat exchanger GEN-III types on market (see next slide) 10

11 NPP P Generations (8/10) Third Generation NPPs (main types, available on the market) Name Type Electric power Designer ABWR BWR 1385 MW GE, Hitachi, Toshiba EPR PWR 1650 MW Framatome ANP Status In operation in Japan: Kashiwazaki Kariwa 6-7, Hamaoka-5, Shika-2, 2 under constr. Under constr.: Finland, France Ordered: 2 in China AP1000 PWR 1200 MW Westinghouse Ordered: 4 in China APWR PWR 1538 MW Mitsubishi Tsuruga 3-4, planned VVER-1000 PWR 1000 MW Gidropress Under constr.: Balakovo-5, Novovoronez, Leningrad VVER-1200 PWR 1160 MW Gidropress Under development ACR-1000 PHWR 1165 MW AECL Considered for new units in Canada ESBWR BWR 1390 MW Hitachi-GE Comissioning in USA? ATMEA-1 PWR MW AREVA - Mitsubishi Under development IAEA 11 New entrants (next slide)

12 NPP P Generations (9/10) Third Generation NPPs (new entrants) Turkey signed (May 10) a deal with RF to construct 4 VVR NPPs units totalling 4,800 MWe by Considers to launch civilian nuclear programme: Jordan, Egypt: Tender for applications, billion USD Morocco, Algeria, Tunisia, Saudi Arabia, United Arab Emirates agreed on building 2 EPRs South Africa: "Nuclear-1" project: units in total of MW on short term; "Fleet" project: by ,000 MW nuclear capacity. Westinghouse (AP-1000) and Areva (EPR) showed interest Venezuela, Indonesia, Vietnam, Kazakhstan, Thailand, Guinea, Libya, Uganda, Senegal Mr Sarkozy sells EPR to UAE IAEA 12 Mr Sarkozy tries to sell EPR to Algeria Mr Sarkozy does not sell EPR to Libya

13 NPP P Generations (10/10) Forth Generation NPPs (requirements) Gen-IV reactors are in R&D phase Requirements: Sustainable International R&D initiatives GHG-free energy production long term availability of fuel, high efficiency of uranium and thorium(!) utilization minimizing the amount of radioactive waste, reducing the length of storage period Economically competitive clear economic advantages (considering the whole fuel cycle) financial risks should not exceed the risks of other energy producing technologies Safety and reliability excellent operational safety and reliability further reduction of CDF and its extent off-site accident preventions will not be needed d Proliferation resistance and physical protection enhanced security (terrorism) minimized possibility to get access to fissile material IAEA Six innovative concepts under study (next slide) 13

14 Six innovative concepts under study Gen-IV (six innovative concepts) Open FC (once through) Open/closed FC Very-High-Temperature Reactor Supercritical-Water Reactor Closed FC Closed FC Gas-Cooled Fast Reactor Closed FC Closed FC Lead-Cooled Fast Reactor Sodium Cooled Fast Reactor Molten Salt Reactor The six selected systems employ a variety of reactor, energy conversion and fuel cycle technologies. Their designs feature thermal and fast neutron spectra, closed and open fuel cycles and a wide range of reactor sizes from very small to very large. Depending on their respective degrees of technical maturity, the Generation IV systems are expected to become available for commercial introduction in the period between 2015 and 2030 or beyond. IAEA 14

15 R&D required in Gen-VI System Very-High- Temperature Reactor (VHTR) Neutron Spectrum Fuel Cycle Size (MWe) Applications Thermal Open 250 Electricity, Hydrogen, Process Heat R&D Needed Fuels (1), Materials, H 2 production Supercritical Water- Thermal, Open, 1500 Electricity it Materials, Safety Cooled Reactor (SCWR) Fast Closed Gas-Cooled Fast Fast Closed Electricity, Hydrogen, Fuels (1), Materials, Reactor (GFR) Actinide Management Safety Lead-alloy-Cooled Fast Closed Fast Reactor (LFR) Sodium Cooled Fast Reactor (SFR) Molten Salt Reactor (MSR) Electricity, Hydrogen Production Fast Closed Electricity, Actinide Management Epithermal Closed 1000 Electricity, Hydrogen Production, Actinide Management Fuels (1), Materials Advanced recycle options (2), Fuels Fuel treatment, Materials, Safety, Reliability IAEA 15 (1) Advanced fuel cycle is a wide-ranging R&D subject (fuel cladding, waste forms, separations and disposal technology) (2)Transmutation science intensively researched field also.

16 International R&D activities Challenges and international initiatives The challenge (global): The next generation of nuclear energy systems - Gen-IV - must be licensed, constructed and operated in a manner that will provide a competitively priced supply of energy. They must consider an optimum use of natural resources, while addressing nuclear safety, waste and proliferation resistance and public perception concerns of the countries in which those systems are deployed. The conclusion Many countries share a common interest in advanced research and development (R&D). The answer: international initiatives (global answer): Recognizing both the positive attributes and shortcomings of the prior generations of reactor designs, few international initiatives were taken working together on R&D to lay the groundwork for the fourth generation, as well as for harnessing fusion energy. Initiatives International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) IAEA in 2000 Generation-IV International Forum (GIF) USA DOE in 2000 Global Nuclear Energy Partnership (GNEP) / International Framework for Nuclear Energy Cooperation (IFNEC) U.S. government in 2006 Multinational Design Evaluation Programme (MDEP) - (national safety authorities initiated by OECD NEA in ITER fusion for energy - a group of findustrial ti nations (six + EC), in 1985/2006. IAEA the five international initiatives in a nutshell 16

17 International initiatives (1/6) International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO) Initiated by IAEA in 2000; as of Oct MSs + European Commission Goals: provides a forum for discussions between experts and policy makers on the development and deployment of innovative nuclear energy systems. main objective is to support the safe, sustainable, economic and proliferationresistant use of nuclear technology to meet the global energy needs of the 21st century. INPRO methodology Identifies a set of (1) Basic Principles, (2) User Requirements and (3)Criteria in a hierarchical manner (with indicators and acceptance limits) Tk Takes a holistic approach to assess innovative nuclear systems (INSs) in seven areas. html IAEA 17 INPRO members (next slide)

18 International initiatives (2/6) INPRO Members IAEA 18

19 International initiatives (3/6) Generation-IV International Forum (GIF) Initiated by USA DOE in 2000, as of Oct 11 membership consists of 13 countries (OECD Nuclear Energy Agency serves as a Technical Secretariat t to the GIF) Goals: as a cooperative international endeavour organized to carry out the R&D needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems. provide a basis for identifying and selecting six nuclear energy systems for further development. GIF Technology Roadmap Outlines a roll-up of metrics systems with: 4 goal areas (sustainability, economics, safety and reliability, proliferation) 8 goals (e.g.: resource utilization, waste minimization, core damage, offsite emergency response) 15 criteria (e.g.: environmental impact, worker/public routine (accident) exposure, robust safety features) 24 metrics (e.g.: heat load, radiotoxicity, i it reliable decay heat removal, passive safety features) IAEA 19

20 International initiatives (4/6) Global Nuclear Energy Partnership (GNEP) from Jun 2010 International Framework for Nuclear Energy Cooperation (IFNEC) GNEP initiative was launched in 2006 by the U.S. government, then the name was changed to IFNEC in Jun 10. As of December 2010, IFNEC membership consists of 29 partner countries, 30 observer countries and three permanent observer intergovernmental organizations i (IAEA, GIF and Euratom) Goals (mission): to serve as a forum to support the development of the peaceful use of nuclear energy in a manner that is efficient and meets the highest standards of safety, security and non-proliferation. IFNEC The International Framework consists of a threetiered organization. At a Sept 07 meeting of the Executive Committee, two working groups were established to address matters concerning reliable nuclear fuel services and infrastructure development Infrastructure Development Working Group (IDWG) held its seventh meeting on December 6, 2010, in Rome, Italy. IAEA 20

21 International initiatives (5/6) Multinational Design Evaluation Programme (MDEP) Initiated by OECD NEA in Membership consist of 10 national safety authorities plus IAEA and EU through h EURATOM. Goals: to develop innovative approaches to leverage the resources and knowledge of the national regulatory authorities who will be tasked with the review of new reactor power plant designs. Broad range of activities including: Enhanced multilateral co-operation within existing regulatory frameworks. Multinational convergence of codes, standards and safety goals. Implementation of MDEP products to facilitate licensing of new reactors, including those being developed by the Generation IV International Forum. MDEP organisation structure It consists of a three-tiered organization also. The effective works running in two working groups: 1) design, 2) issue specific WGs; A key concept throughout the work is that national regulators retain sovereign authority for all licensing i and regulatory decisions. i IAEA 21

22 International initiatives (6/6) ITER group of industrial nations for fusion energy In 1985 a group of industrial nations agreed on a project to develop a new, cleaner, sustainable source of energy (aimed at developing fusion energy for peaceful purposes). The ITER Agreement was officially signed in Paris on 21 Nov 06 by Ministers from the seven ITER Members: EC (EURATOM), China, India, Japan. Korea, RF and USA. Thus, in ITER ( way in Latin), the world has now joined forces to establish one of the largest and most ambitious international science projects ever conducted. Schedule: Construction works began in 2010 on the ITER site in Cadarache, France. Operation in Mission objectives: during its operational lifetime, ITER will test key technologies necessary for the next step: the demonstration fusion power plant (DEMO) that will prove that it is possible to capture fusion energy for commercial use. 500 MW from 50 MW. "Broader Approach" agreement for complementary R&D three projects were set into motion that focus on the following areas: (1) materials testing, (2) advanced plasma experimentation and simulation, and (3) the establishment of a design team to prepare for DEMO. ITER is not an end in itself: it is the bridge toward a first plant that will demonstrate the large-scale production of electrical power. DEMO will lead fusion into its industrial era, beginning operations in the early 30s, and putting fusion power into the grid as early as IAEA 22

23 R&D projects objectives looking at a big picture R&D projects focus on: Developing reference systems (six innovative concepts) an preparing defendable safety cases (currently being researched). Plus ITER. Development & validation of reactor physics and core design analyses tools, reactor thermal-hydraulic and mechanical design analysis tools Materials research (key issue highlighted topic) Power-conversion unit assessments Fuel development and qualification (covers entire fuel cycle) Safety and risk analysis of the very high temperature reactor IAEA let s have an insight in advanced material R&D 23

24 Facts and research objectives Facts: Materials science and materials development are key issues for the implementation of innovative reactor systems such as GEN-IV and advanced fuel cycle initiatives. Development & Characterization/Qualification of materials for nuclear applications are a long term process. R&D covers: Processing techniques: casting, rolling, welding, ion-implantation, crystal growth, thin-film deposit, sintering, glassblowing, etc. Analytical techniques (characterization techniques relevant to NR using neutron beams): neutron scattering, -diffraction, -radiography. Characterization/qualification techniques are subjects and tools of R&D(!). Approach: cross-cutting research on structural material for GEN-IV and transmutation systems; plus R&D is linked with demand from fusion reactor. Engineering (traditional) and (2) Scientific (innovative). IAEA Let s have a look on few structural materials

25 Few structural materials R&D programs for development and/or characterization of advanced materials, like: W conventionally high temperature (refractory) tungsten alloys Mo(TZM) Molybdenum alloys (Ti-Zr-Mo) Ta-8W-2Hf Tantalum composite alloys Let s have a look on degradation process Nb-1Zr-1C 1C Niobium derivative alloys (enhanced creep strength) V-4Cr-4Ti Vanadium alloys The restricted operating temperature window ODS Oxide dispersion strengthened ferritic steels F/M Reduced activation ferritic/martensitic steels Inconel Ni-Co alloy CuNiBe Cupper alloy (high conductivity) SiC/SiC Silicon carbide composite materials CMC Ceramic matrix composite materials Structural Material Operating Temperature Windows: dpa Radiation embrittlement regime SCWR VHTR Thermal creep regime IAEA 25

26 Degradation process main issues few degradation phenomena Radiation damage Direct impact of mechanical properties effects like: Direct Matrix Damage (dpa), segregation, phase transportation phenomenon, etc. Embrittlement Impact/effect: problem related to the loss of ductility (define lifetime: RPV, RVI) Swelling Issue for fuel cladding and core components Corrosion and Cracking Impact/effect: (1) stress corrosion cracking (SCC) issue for weld materials; (2) irradiation assisted stress corrosion cracking issue for BWR, SCWR; (3) high coolant flow rate (thermal-hydraulic stress) issue for LWR. R&D Effect of flux, flux-spectra & dose-rate, penetration of phenomenon, coolant media chemistry, temperature, etc. vs. metallurgical behaviour of material. Goal: to develop characterised and qualified advance (composite and alloy) nuclear structural materials. IAEA 26 1 dpa (displacement per atom) = every single atom in lattice has been displaced)

27 R&D objectives and supporting tools Main R&D objectives (innovative R&D physics and material science) Better understanding of radiation effects and mechanisms of material damage and basic physics of accelerator irradiation under specific conditions (fundamental research). Developmental of theoretical models for radiation degradation mechanism Improvement of knowledge and data for the present and new generation of structural materials (e.g.: transmutation science and engineering that explores physics and materials challenges. Tools ( among others for characterization/qualification sample irradiation in real environment measurements in neutron beams, PIE) Harnessing modern nuclear, accelerator and research reactor based techniques for simulation and studies of radiation damage in reactor core structural materials (utilized rigs & loops for material testing, then PIE). Harnessing advanced physical models and computational codes developed for prediction of high-dose radiation effects (codes validations experimental facility needs!) Construct (subject specific, state-of-the-art) new material test research reactor(s) (JHR-France). Fostering the advanced or innovative technologies by promotion of information exchange, collaboration and networking. IAEA Thus, RRs play a significant role in advanced material R&D

28 IAEA activity on supporting material R&D Facts Present in many areas of the IAEA s Projects (cross-cutting area at the Agency) Related projects (INPRO) advanced tool for support MSs in their nuclear energy development (Technology development for advanced reactor lines) (Nuclear power reactor fuel engineering) 124(N (Nuclear fuels &f fuel cycles for advanced dand dinnovative reactors) (Enhancement of utilization and applications of RRs ) (Improvement of knowledge and data for the design and engineering of advanced d materials of economic importance) (Nuclear fusion) Nuclear Science Programme (1.4) Towards supporting materials research for advanced reactors IAEA 28 Contact: D.Ridikas@iaea.org

29 Major Activities related to NR From IAEA s perspective (according to the Agency missions ) Assistance and support of MSs in the field of 1. Accelerators 2. Research Reactors 3. Controlled Fusion 4. Nuclear Instrumentation 5. Cross-cutting Material Research (see next slide) Based on MSs needs, requests & recommendations Planning & implementation of P&B activities Proposal and implementation of CRPs Management of Data Bases Organization of Conferences, Technical & Consultancy Meetings Organization of ICTP workshops, training schools and courses Support of TC projects Promotion of Nuclear Sciences, Applications and Technologies IAEA cross-cutting cutting support activity as well 29

30 Cross-cutting Coordination IAEA s activities on RRs (including material R&D) A cross-cutting coordinated area Activities coordinated through a Cross-Cutting Coordination Group for Research Reactors (CCCGRR) Multi-departmental involvement CCCGRR includes representatives from the: Departments of Nuclear Safety (NS), Nuclear Science (NA), Nuclear Energy (NE), Safeguards (SG) and Technical Cooperation (TC) IAEA 30

31 Example: IAEA CRPs Active new CRP 1575 ( ): 2012): Development, Characterization and Testing of Materials of Relevance to Nuclear Energy Sector Using Neutron Beams (SANS, diffraction and neutron radiography) Objectives: investigation and characterization of materials relevant to nuclear energy applications optimization and validation of experimental and modeling methods creation of a database of reference data for nuclear materials research enhancement e of the capacity of research reactors for nuclear materials a research 10 Research Contracts + 9 Research Agreements 1. Argentina 2. Australia 3. Brazil 4. China 5. Czech Republic 6. France 7. Germany 8. Hungary 9. Indonesia 10. Italy 11. Japan 12. Korea 13. The Netherlands 14. Romania 15. Russian Federation (2) 16. South Africa 17. Switzerland Expected output: 18. USA Creation of multilateral network in the field of advanced nuclear materials research IAEA Creation of an experimental reference database for models and calculations Final project publication

32 Status of RRsRs Worldwide For almost 60 years RRs have contributed to the development of nuclear science & technology. We know about 676 RRs in 69 countries (67 MS) of which 237 are still operating TOTAL: 676 Operational 237 Temp. shutdown 12 Under construction 3 Planned 2 Shutdown/Decommissioned 417 Cancelled 5 Operational RRs are distributed over 56 countries Russia ~47 USA ~41 China ~16 Japan ~15 France ~11 Germany ~10 Source: IAEA RRDB, February 2011 Region Operational RRs Africa 9 Americas 66 Asia/Pacific 59 Europe (with Russia) 100 IAEA 32 Source:

33 Key issues and challenges Characteristic features Age: 2/3 rd > 30 y 20% of all are in developing countries RR underutilization Ageing & needs for refurbishment Fuel cycle issues Requests for new RRs Safety & security Steady thermal power (MW) 5000 Number of reactors 400 Steady thermal power No of reactors Year of all RRs, % Fraction Utilisation rate IAEA 33 0 high, >20FPW/year medium small, <4FPW/year Source: IAEA RRDB, February 2011

34 Education & training activities Synergetic approach for fission and fusion IAEA More info: 34

35 RR under construction JHR (1/2) Dedicated Material Test Reactors JHR, France, operation expected in 2015 MTR pool, 100 MW, in core flux ~1*10 15 n/(s cm 2 ) Fuel: Ref. UMo LEU, Backup: U 3 Si 2 27 % U-235 In support of future nuclear power, Gen3+ & Gen4 Dedicated for material/fuel irradiation and testing Other applications envisaged (isotope production). International consortium. IAEA 35 Contact: D.Ridikas@iaea.org

36 RR under construction JHR (2/2) Presentation of experimental capacity IAEA 36

37 Concluding remarks (1/2) Nuclear renaissance: Increasing energy demand, plus concerns over climate change and dependence on overseas supplies of fossil fuels are coinciding to make the case for increasing use of nuclear power. Increased inherent safety: the March 2011 Fukushima accident has set back public perception p of nuclear safety. This event put in focus the inherent safety of a nuclear facility. Requires R&D as well. International initiatives to support and coordinate R&D worldwide. INPRO and GIF are two deterministic, long- term research projects, where leading scientists from a dozen countries join forces in the effort to develop future reactor designs and carry out supplementary research. IAEA 37

38 Concluding remarks (2/2) Main R&D challenges and issues relevance to NR: Develop Gen-IV reactor types: six different types of reactor design are considered currently being researched. (plus ITER). Advanced material R&D for supporting Gen-IV reactor materials. Nuclear experimental facilities (RRs, accelerators) are harnessed for testing material samples (modelling real test environment). They are subjects and tools of R&D. characterisation (non-destructive testing of materials and structural components by neutron beams), PIE. Future prospects p (Let me quote an expressive answer on questions asking about the future.) With regard to the fusion energy production the scientists currently state that their was a paradigm shift - until now we have always said that harnessing fusion energy will take at least 30 years, however from this point we will say it will take at least 50 years. IAEA 38

39 Thank you for your attention! IAEA 39