Next Generation Nuclear Reactors

Transcription

1 Next Generation Nuclear Reactors Jacques BOUCHARD Commissariat à l Energie Atomique FRANCE WNU - Ottawa Jacques BOUCHARD, July 15,

2 Session Contents - Introduction - Nuclear Reactor Generations ; A brief history - Light Water Reactors - High Temperature Reactors - Fast Neutron Reactors - The Generation IV International Forum (GIF) - The IAEA program (INPRO) - Other initiatives - Discussion WNU - Ottawa Jacques BOUCHARD, July 15,

3 Introduction - Nuclear Energy - Safety principles - Economy - Public acceptance WNU - Ottawa Jacques BOUCHARD, July 15,

4 Introduction : Nuclear Energy Mastering the energy from the fission of heavy nuclides - A high density of energy - A process controlled through delayed neutrons - Radioactivity of fission products - Fissile and fertile isotopes - Criticality criteria - The front end of the fuel cycle - The back end of the fuel cycle WNU - Ottawa Jacques BOUCHARD, July 15,

5 Introduction : Safety Principles - Two main risks: - Uncontrolled increase of power - Loss of cooling - Inherent safety features - Protection and actions - Mitigation of severe accidents - Other types of risks WNU - Ottawa Jacques BOUCHARD, July 15,

6 Introduction : Economy capital cost % Nuclear energy : High capital investment costs Long planning horizons Low Fuel and O&M costs WNU - Ottawa Jacques BOUCHARD, July 15,

7 Introduction : Public Acceptance - Several issues: - Civilian vs. military applications - plant safety, in particular severe accidents, - waste management - Strong improvements in communication and transparency - New positive aspects (economy, climate change ) - A real need for education WNU - Ottawa Jacques BOUCHARD, July 15,

8 Nuclear Reactor Generations First Reactors Current Reactors Advanced Reactors Future Systems Generation I Generation II Generation III Generation IV WNU - Ottawa Jacques BOUCHARD, July 15,

9 Generation I : Early Prototypes Reactors built in the fifties and sixties - Many prototypes all around the world - Various types of thermal and fast neutron reactors - For most of the countries, a main limitation due to the use of natural uranium -> graphite or heavy water moderated cores - Development of the first light water reactors for naval propulsion - First production of electricity in ARCO (Idaho) 1951, with a fast neutron reactor WNU - Ottawa Jacques BOUCHARD, July 15,

10 Generation II : Current Power Plants Reactors built from the end of the sixties to the nineties - An industrial development accelerated by the first oil shocks - A large domination of light water reactors : - Pressurized Water Reactors - Boiling Water Reactors - Some countries made other choices: - Heavy Water Reactors (CANDU) - Gas Cooled Reactors (AGR) - Light Water Cooled Graphite Reactors (RBMK) - An expansion stopped in many countries after the TMI and Chernobyl accidents WNU - Ottawa Jacques BOUCHARD, July 15,

11 Generation II : Current Power Plants Status of existing power reactors (2005): The families Type Nb of units Total Capacity (GWe) PWR BWR PHWR GCR LWGR FBR 2 1 Total WNU - Ottawa Jacques BOUCHARD, July 15,

12 Generation II : Current Power Plants Status of existing power reactors connected to the grid (2005): The countries Country Nb of units Capacity (GWe) United States France Japan Russia United Kingdom South Korea Germany Canada Ukraine Others (22) Total WNU - Ottawa Jacques BOUCHARD, July 15,

13 Generation III : Advanced Reactors Near term deployment of industrial reactors - A new generation of reactors which design takes benefit of the large experience acquired in the operation of Gen II plants and of the lessons coming from TMI - Light Water Reactors are still dominating - To make new improvements in safety while keeping economic competitiveness have been the main objective - Different approaches have been studied and are still competing in the industrial offer : - small vs. large reactors - passive vs. active safety systems - Mitigation of severe accident consequences is a major step WNU - Ottawa Jacques BOUCHARD, July 15,

14 Generation III : The industrial offer Generation III reactors identified as Near Term Deployment by the Generation IV Forum Advanced Pressurized Water Reactors AP 600, AP 1000, APR1400, APWR+, EPR Advanced Boiling Water Reactors ABWR II, ESBWR, HC-BWR, SWR-1000 Advanced Heavy Water Reactors ACR-700 (Advanced CANDU Reactor 700) Small and middle range power integrated Reactors CAREM, IMR, IRIS, SMART High Temperature, Gas Cooled, Modular Reactors GT-MHR, PBMR WNU - Ottawa Jacques BOUCHARD, July 15,

15 Generation III : Market prospective Average values of current NP age (2005) Country Nb Reactors Mean Age United States years France years Japan years United Kingdom years Germany years Sweden years Belgium 7 28 years China 9 6 years Finland 4 25 years WNU - Ottawa Jacques BOUCHARD, July 15,

16 Generation III : Market prospective - Besides the renewal of existing power plants, there are many plans for new realizations (USA, China, India, UK ); - The nuclear production capacity could grow from 400 GWe to GWe by Most of the new nuclear plants in the three or four coming decades will be Gen III systems. WNU - Ottawa Jacques BOUCHARD, July 15,

17 Generation IV : Future Nuclear Systems R&D in preparation for a large expansion of nuclear energy - Prospects for energy needs show the possibility of a strongly increasing demand for nuclear power; - In such an hypothesis, sustainability becomes a predominant concern, which means preservation of natural resources, waste minimization and proliferation resistance are criteria as important as economy and safety. - Furthermore, other application of nuclear energy than electricity production are to be considered, in particular, hydrogen production, industrial use of heat or desalination. - The development of new systems will take time and require validation and demonstration. Therefore, the target for industrial scale applications is 2030 or later. WNU - Ottawa Jacques BOUCHARD, July 15,

18 Generation IV : An International Forum (GIF) New requirements for sustainable nuclear energy Gradual improvements in : Competitiveness Safety and reliability Concepts with breakthroughs Minimization of wastes Preservation of resources Non Proliferation Systems expected to reach technical maturity by 2030 Assets for new markets - hydrogen production - direct use of heat - sea water desalination An internationally shared R&D WNU - Ottawa Jacques BOUCHARD, July 15,

19 Light Water Reactors A mature technology with the largest experience - One technology but two different designs: - boiling water reactors - pressurized water reactors - More than equivalent year. reactor experience large power reactors in operation in 25 countries - Only one severe accident (TMI) with limited consequences - Initial lifetime expected to be expanded by many years - Considerable economic improvement through more than twenty years of operation - Strong evolution of the design from Gen II to Gen III - Two main limitations: - temperature below 300 C which means rather low yields - neutron balance which leads to poor regeneration rates WNU - Ottawa Jacques BOUCHARD, July 15,

20 LWR : Continuous improvements The US example (Source ANS) 100,0% 90,7% 91% Increasing capacity factors (equivalent to 23 new reactors) Excellent safety performances Reduction of O&M costs Reduction of wastes quantities Capacity Factor factor 80,0% 60,0% 40,0% 20,0% Reduction of exposure at work 0,0% '92 '93 '94 '95 '96 '97 '98 '99 '00 '01 '02 Significant events Events 1 0,8 0,6 0,4 0,2 0 0,9 0,77 0,45 0,4 0,25 0,26 0,21 0,17 0,08 0,1 0,04 0,03 0,02 0, Fiscal Year (Billions of Kilowatt-Hours) (Billions of KWh) '90 '94 '98 '99 '00 '01 '02 WNU - Ottawa Jacques BOUCHARD, July 15,

21 LWR : a competitive energy 60 Comparison Europe : Comparison of European of markets power prices market between prices and fuel (coal, operating fuel oil, costs natural for gas, different nuclear) type and of power fuels 50 Euros/MWh janv- 00 avr- 00 juil- 00 oct- 00 janv- 01 avr- 01 juil- 01 oct- 01 Power Gas Coal Fuel oil Nuclear Source: EDF WNU - Ottawa Jacques BOUCHARD, July 15,

22 Light Water Reactors : Generation III New improvements for safety - Lessons drawn from the TMI accident - A further reduction of severe accident probability - Mitigation of consequences in case of core melting - Passive vs. active systems - A long story of R & D and engineering works WNU - Ottawa Jacques BOUCHARD, July 15,

23 Light Water Reactors : Generation III Westinghouse : AP1000 WNU - Ottawa Jacques BOUCHARD, July 15,

24 Light Water Reactors : Generation III WNU - Ottawa Jacques BOUCHARD, July 15,

25 Light Water Reactors : Generation III AREVA NP s EPR Double-wall containment with ventilation and filtration system EPR Core melt spreading area Improved safety Containment heat removal system Inner refueling water storage tank Four-train redundancy for main safeguard Le projet systems EPR WNU - Ottawa Jacques BOUCHARD, July 15,

26 Corium spreading test : CEA - VULCANO Melt spreading phenomena have been extensively investigated real UO2 with some ZrO2 WNU - Ottawa Jacques BOUCHARD, July 15,

27 LWR Gen III : Back end of the fuel cycle Capacity to load up to 100% MOX Core An enhanced capacity to burn Plutonium REP 900 MOX UOX Control rods EPR Plutonium annual balance Kg Pu/year REP 900 UO 2 : REP 900 MOX : 0 EPR 100% MOX : WNU - Ottawa Jacques BOUCHARD, July 15,

28 LWR : A challenge for other technologies - From the beginning, scientists and engineers are looking to other technologies in a try to overcome the two main LWR limitations: - Thermodynamic yield limited by rather low temperatures, - Uranium burning limited by small breeding rates. - Two main paths have been and are still considered, high temperature reactors and fast neutron reactors. - Other technologies can bring some improvements in one or the other way, such as supercritical water systems or molten salt reactors, but have not yet reached the same level of development. WNU - Ottawa Jacques BOUCHARD, July 15,

29 High Temperature Reactors A new path for both electricity and hydrogen productions - Direct use of heat for industrial applications, including possible hydrogen productions by chemical processes, requires temperatures in the range C. - Gas cooling is the only solution and among gases helium is the most practical choice. - A first try to develop that technology took place in the 70s (Fort St Vrain in the US, THTR in Germany) after some early prototypes. - Small experimental reactors have been built more recently in Asia (HTTR in Japan, HTR 10 in China). - New projects are considered in the frame of Gen III (PBMR in South Africa) or Gen IV ( NGNP in the US). WNU - Ottawa Jacques BOUCHARD, July 15,

30 High Temperature Reactors Source: General Atomics WNU - Ottawa Jacques BOUCHARD, July 15,

31 High Temperature Reactors : The challenges 1 The fuel : Small particles with carbon and SiC coatings; particles embedded in graphite; two options: - compacts (FSV, GT-MHR) - pebbles (THTR, PBMR) 2 Structural materials : Graphite is the basic material inside the core; 3 The cooling system : helium loops with direct conversion (Brayton cycle) or indirect conversion through heat exchangers. 4 Reactor power : limited by low power density and high gas pressure; still more limited in the pebble option by the control of core reactivity. WNU - Ottawa Jacques BOUCHARD, July 15,

32 High Temperature Reactors : The fuel Prismatic fuel element with TRISO particles (source: General Atomics) WNU - Ottawa Jacques BOUCHARD, July 15,

33 High Temperature Reactors HTTR (Japan) WNU - Ottawa Jacques BOUCHARD, July 15,

34 High Temperature Reactors HTR 10 (China) WNU - Ottawa Jacques BOUCHARD, July 15,

35 High Temperature Reactors PBMR (South Africa) Main Power System Reactor Unit Recuperators Compressors Turbine Pre-cooler Generator Inter-cooler CCS & Buffer Circuit CBCS & Buffer Circuit Shut-off Disk Contaminated Oil Lube System Un-contaminated Oil Lube System WNU - Ottawa Jacques BOUCHARD, July 15,

36 VHTR Very High Temperature Reactor Thermal spectrum, once-through uranium cycle Prismatic block or pebble bed fuels Highly ranked in economics & in safety and reliability Hydrogen production & other process-heat applications WNU - Ottawa Jacques BOUCHARD, July 15,

37 Iodine-Sulfur process for hydrogen production Hydrogen Nuclear Heat Oxygen 1 H 2 O O C 900 C 1 H O Rejected H 2 SO 2HI 4 + I 2 SO 2 +H 2 O Heat C I 2 I (Iodine) Circulation 2H I + I 2 + H 2 O + H 2 O H 2 SO 4 SO 2 +H 2 O S (Sulfur) Circulation SO 2 + H 2 O Water WNU - Ottawa Jacques BOUCHARD, July 15,

38 Fast Neutron Reactors A solution for both an optimized use of resources and waste minimization - Fast neutrons allow a more efficient burning of actinides because the ratio of fission/capture cross sections is higher than with thermal neutrons. - The first consequence is the possibility of positive breeding gains which allows to burn all the uranium through conversion of Uranium 238 in Plutonium Another interesting feature is the possibility of burning all the actinides produced in the fast reactors themselves or in light water reactors by continuous recycling, thereby reducing considerably the long term radioactive potential of waste. WNU - Ottawa Jacques BOUCHARD, July 15,

39 Uranium Needs < 200 $/kg Higher than 1000 $/kg Between 200 up to 400 $/kg < 130 $/kg Engaged U Consumed U Mt Years Sea water, others Phosphate Speculative resources Estimated resources Scenario PWR only open cycle (IAASA A2) WNU - Ottawa Jacques BOUCHARD, July 15,

40 Recycling to optimize the use of uranium resources 1000 kg U nat Enrichment 100 kg U 5% 900 kg U dep Recycling 4 kg W + PF 1 kg Pu 95 kg U rep Fast neutron reactors burn plutonium while converting U 238 into plutonium that is burnt in situ (regeneration breeding of fissile fuel) The existing depleted uranium that is stored today in France is worth 5000 years of current nuclear production. WNU - Ottawa Jacques BOUCHARD, July 15,

41 A plausible scenario Growing energy demand ; Part of nuclear energy increasing after 2030; Light Water Reactors with uranium fuel remain dominant World Energy needs (GTOE) Nuclear primary energy (GTOE) Nuclear capacity (GWe) LWR capacity (GWe) WNU - Ottawa Jacques BOUCHARD, July 15,

42 Spent Fuel and Plutonium Accumulation The plausible scenario ; R&R limited to a few countries; Gen IV systems implemented progressively after Nuclear capacity (GWe) LWR capacity (GWe) Stored spent fuels ( Mtons) 0,2 0,5 1,0 Plutonium amount (tons) WNU - Ottawa Jacques BOUCHARD, July 15,

43 Fast Reactors : Resources optimization Cumulative Natural U (Million Tonnes) Cumulative Natural U (Million Tonnes) LWR LWR Once Through Through FR Introduced 2050 Speculative Resources FR Introduced Year Known Resources WNU - Ottawa Jacques BOUCHARD, July 15,

44 Fast Reactors : Waste minimization Relative radio toxicity MA + FP Plutonium recycling Pu + MA + FP Spent Fuel Direct disposal Uranium Ore (mine) FP P&T of MA Time (years) WNU - Ottawa Jacques BOUCHARD, July 15,

45 Global Actinide Recycling U nat Spent fuel Treatment and Re-fabrication Ultimate wastes FP GEN IV FR Actinides Saving uranium resources Minimizing waste heat and radiotoxicity Ensuring a strong proliferation resistance WNU - Ottawa Jacques BOUCHARD, July 15,

46 Global Actinide Recycling The requirements No separation of pure elements, in particular Plutonium Very low quantities of actinides in the ultimate waste An efficient burning (by fission) of actinides in the reactor, in order to avoid growing inventories of heavy elements WNU - Ottawa Jacques BOUCHARD, July 15,

47 Fast Neutron Reactors : Technologies - To keep a fast neutron system it is necessary to avoid light elements in the core and in particular for the cooling system. - The two main possibilities for cooling are liquid metals or gases. They are part of Gen IV selected systems. - A broad worldwide effort have been devoted to sodium cooling technology including industrial prototypes (BN600 in Russia, Superphenix in France, Monju in Japan). - The Russians have used lead cooling for naval reactors and some more studies have been made for possible use of lead or lead-bismuth cooling systems. - The use of helium technology developed for HTGRs is also considered for fast reactors. - After a negative attempt to use vapor cooling, supercritical water has been selected by the GIF as a possible candidate for fast reactor cooling. WNU - Ottawa Jacques BOUCHARD, July 15,

48 Fast Reactors : Sodium Technology - Sodium is a very suitable coolant: - liquid in a wide range of temperatures ( C) - mono isotope (Na23) - thermodynamics parameters - no corrosion (when purified) - Large industrial experience : - various industrial uses - 40 years of technological studies for nuclear applications - many prototypes - Well-known drawbacks : - chemical reactivity (sodium fires and sodium-water reactions) - difficulties for handling and inspection WNU - Ottawa Jacques BOUCHARD, July 15,

49 SFR Sodium-Cooled Fast Reactor The pool design WNU - Ottawa Jacques BOUCHARD, July 15,

50 Phenix WNU - Ottawa Jacques BOUCHARD, July 15,

51 SFR Sodium-Cooled Fast Reactor The loop design Heat?Exchanger Steam Generator Control Rods Turbine Generator Electrical Power Hot Plenum Condenser Primary Sodium?Hot? Core Pump Pump Heat Sink Cold Plenum Primary Sodium?Cold? Pump Secondary Sodium WNU - Ottawa Jacques BOUCHARD, July 15,

52 FBR Prototype Monju (Japan) Reactor bldg. Air cooler Secondary pump condenser DG D/ G Bat. Outlet Heat exchangers Coolers Fuel WNU - Ottawa Jacques BOUCHARD, July 15,

53 BN 600 (Russia) A 600 MWe plant built at Beloyarsky (Russia) First criticality: 1980; still in operation WNU - Ottawa Jacques BOUCHARD, July 15,

54 SUPERPHENIX A 1200 MWe plant built at Creys-Malville (France) First criticality: 1985; Shutdown: 1997 WNU - Ottawa Jacques BOUCHARD, July 15,

55 Fast Reactors : Lead Technology - A candidate to avoid the risks associated with sodium fires or sodium-water reactions - A less favorable coolant (thermodynamics parameters, corrosion risks) - lead-bismuth alloy to reduce corrosion risks - An experience limited to Russian applications in naval propulsion - Many studies going on in various countries WNU - Ottawa Jacques BOUCHARD, July 15,

56 LFR Lead-cooled Fast Reactor WNU - Ottawa Jacques BOUCHARD, July 15,

57 Fast Reactors : Helium Technology - Gas cooling is less efficient than liquid metal cooling - The development of a gas cooled fast reactor will require a new type of fuel - Helium technology is already considered for VHTR - Specific safety concerns which should be clarified - If it can be successfully designed, the result will satisfy both objectives for a sustainable development (fast neutron physics and high temperature technology) WNU - Ottawa Jacques BOUCHARD, July 15,

58 GFR Gas-Cooled Fast Reactor WNU - Ottawa Jacques BOUCHARD, July 15,

59 Generation IV International Forum WNU - Ottawa Jacques BOUCHARD, July 15,

60 The Gen IV Structure WNU - Ottawa Jacques BOUCHARD, July 15,

61 Six innovative concepts with technological breakthroughs Sodium Fast reactor Closed Fuel Cycle Lead Fast Reactor Closed Fuel Cycle Closed Fuel Cycle Gas Fast Reactor Once Through Very High Temperature Reactor Once/Closed Supercritical Water Reactor Molten Salt Reactor Closed Fuel Cycle WNU - Ottawa Jacques BOUCHARD, July 15,

62 GIF Collaborative R&D Structure Framework Agreement SFR SA GFR SA SCWR SA VHTR SA LFR SA MSR SA Advanced Fuel PA GACID PA Component Design & Balance of Plant PA System Integration & Assessment PA Fuel, Core Materials & Fuel Cycle PA Material & Chemistry PA System Integration & Assessment PA Thermal- Hydraulic & Safety PA Fuel & Fuel Cycle PA H2 Production PA Materials PA Legend : PA :Project Arrangement SA: System Arrangement, Signed Not yet signed System Integration & Assessment PA WNU - Ottawa Jacques BOUCHARD, July 15,

63 Signature of the Generation IV Framework Agreement on 28th February 2005 in Washington DC WNU - Ottawa Jacques BOUCHARD, July 15,

64 Charter Signing Ceremony by China and Russia Paris, 11/06 WNU - Ottawa Jacques BOUCHARD, July 15,

65 VHTR SA Signing Ceremony Paris, 11/06 WNU - Ottawa Jacques BOUCHARD, July 15,

66 The IAEA INPRO INPRO : International Project on Innovative Nuclear Reactors and Fuel Cycles. Basis of INPRO : Resolution at the IAEA General Conference in 2000 in Vienna and at the United Nations General Assembly in Text of IAEA General Conference Resolution in September 2000: o IAEA GC 2000 has invited all interested Member States to combine their efforts under the aegis of the Agency in considering the issues of the nuclear fuel cycle, in particular by examining innovative and proliferation-resistant nuclear technology WNU - Ottawa Jacques BOUCHARD, July 15,

67 General Objectives of INPRO INPRO General Objectives: 1. To help to ensure that nuclear energy is available to contribute in fulfilling energy needs in the 21st century in a sustainable manner. 2. To bring together both technology holders and technology users to consider jointly the actions required to achieve desired innovations in nuclear reactors and fuel cycles. INPRO Time horizon is 50 years into the future. WNU - Ottawa Jacques BOUCHARD, July 15,

68 GIF and INPRO Membership (as of May 2006) GIF has an R&D Framework with most of the countries with large R&D programs or industries INPRO has participation of most of the countries with nuclear reactors or plans to acquire them WNU - Ottawa Jacques BOUCHARD, July 15,

69 Current Scope of Activities WNU - Ottawa Jacques BOUCHARD, July 15,

70 The US initiative GNEP Growing Nuclear Energy Demand Advanced Fuel Cycle Fast Reactors burning Actinides Small Reactors for countries starting with nuclear International Partnership Advanced fuel cycle technology Fuel services for countries without fuel cycle facilities WNU - Ottawa Jacques BOUCHARD, July 15,

71 Future Prototypes : VHTR NGNP ( USA, Idaho) WNU - Ottawa Jacques BOUCHARD, July 15,

72 Future Prototypes : Fast Reactors January 2006 Presidential Announcement: Construction of a 4 th generation reactor prototype in 2020 Generation IV International Forum (GIF) February 2006 Global Nuclear Energy Partnership (GNEP) GNEP Fast Reactor in April 2006: Fast Reactor Cycle Technology Development (FaCT) project Demo / Fast reactor in 2025 WNU - Ottawa Jacques BOUCHARD, July 15,