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    Introdu ct ion to Generat ion IV

    Nuclear Energy Sys tems

    and the In ternat ional Forum

    2008

    http://www.gen-4.org/

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    Our Vision for Nuclear Energy:

    SecureProvid ing diversi f icat ion of supply

    AffordableKeeping energy co sts compet it ive

    CleanDel iver ing a major n on-em it t ing sou rce

    The challenge for all countries is to put inmotion a transition to a more secure, lower-

    carbon energy system, without underminingeconomic and social development.World Energy Outlook 2007 (OECD/IEA)

    http://www.worldenergyoutlook.org/2007.asp

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    The Prob lem of Cl imate Change Global greenhouse gas (GHG) emissions have grown since

    pre-industrial times, increasing 70% between 1970 and 2004

    With current climate change mitigation policies and practices,

    global GHG emissions will continue to grow

    The Earth is about to undergo long lasting changes in its

    climate, seas and land cover, including

    Temperature

    Precipitation

    Sea level

    Ocean circulation

    Ice/snow cover

    Storm frequency

    Storm intensity

    Desertification

    Global Warmin g (deg C) by 2100 (IPCC predict io n)

    http://www.grida.no/climate/ipcc_tar/http://www.grida.no/climate/ipcc_tar/

    http://www.grida.no/climate/ipcc_tar/
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    Carbon emissions need to be brought to a sustainable balance

    Nuclear energy can be part of the future, sustainable sources

    Contributing a nuclear wedge would require tripling the number of

    nuclear plants worldwide, to abo ut 1000 plants, for example

    Nuclear energy systems must continue their advances in order to

    unlock a potential on this scale

    The Challenge fo r Nuclear Energy

    Holding CO2 Emissions con stant

    defines a triangle, or reduction goal

    Achieving the goal wou ld require 8 contr ibut ions

    of about 1 Gt/y in CO2 emiss ions each, through

    pol icy in i t ia t ives and/or technology deployment

    http://www.princeton.edu/~cmi/

    8 wedges

    1 wedge

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    Generat ions o f Nuc lear Energy

    Early Prototypes

    Generation I

    - Shippingport- Dresden- Magnox

    1950 1960 1970 1980 1990 2000 2010 2020 2030

    Gen I Gen II Gen III Gen III+ Gen IV

    Commercial Power

    Generation II

    - PWRs- BWRs

    - CANDU

    Advanced LWRs

    Generation III

    - CANDU 6- System 80+-AP600

    Generation III+

    Evolutionary Designs

    -ABWR-ACR1000-AP1000-APWR- EPR

    - ESBWR

    - Safe- Sustainable- Economical- Proliferation

    Resistant andPhysicallySecure

    Generation IV

    RevolutionaryDesigns

    http://www.gen-4.org/Technology/evolution.htm

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    Generation IV GoalsSustainability

    1. Generate energy sustainably, and promote long-term availability of nuclear fuel

    2. Minimize nuclear waste and reduce the long term stewardship burden

    Safety & Reliability

    3. Excel in safety and reliability

    4. Have a very low likelihood and degree of reactor core damage

    5. Eliminate the need for offsite emergency response

    Economics

    6. Have a life cycle cost advantage over other energy sources

    7. Have a level of financial risk comparable to other energy projects

    Proliferation Resistance & Physical Protection

    8. Be a very unattractive route for diversion or theft of weapons-usable materials,

    and provide increased physical protection against acts of terrorism

    GIF-019-00 Technology Goals.pdf

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    Creat ion o f the Internat ional Forum

    Started in Jan 2000 by nine countries and established Jul 2001 Agreed that nuclear energy is needed to meet future needs

    Defined four goal areas to advance nuclear energy into its next,

    fourth generation:

    Sustainability

    Safety & reliability

    Economics

    Proliferation resistance and physical protection

    Will collaborate to make Generation IV systems deployable in

    large numbers by 2030, or earlier

    http://www.gen-4.org/GIF/About/origins.htm

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    Generation IV In ternational Forum

    Chartered in July 2001 Set out Vision, Goals and Objectives

    Nine charter members

    Created a virtual organization

    Government leaders in a Policy Group

    Technical advisors in an Experts Group Makes decisions by consensus

    Members bear their own costs, and participate

    in the systems and R&D that they choose

    GIF works with other organizations, especially

    IAEA and OECD/NEA to draw expertise

    Shares information openly where possible

    http://www.gen-4.org/PDFs/GIFcharter.pdf

    Founding Members now joined by:

    Switzerland (2002), Euratom (2003), China and Russia (2006)

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    The Techno logy Roadmap

    Two-year effort by 100 international expertsfinding the most promising nuclear systems

    Six systemswere selected:

    Gas-Cooled Fast Reactor (GFR)

    Lead-Cooled Fast Reactor (LFR) Molten Salt Reactor (MSR)

    Sodium-Cooled Fast Reactor (SFR)

    Supercritical-Water Reactor (SCWR)

    Very-High-Temperature Reactor (VHTR)

    Timelines and research needs were developedfor the needed technology

    http://www.gen-4.org/Technology/roadmap.htm

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    Sod ium -Coo led Fast Reactor (SFR)

    Characteristics

    Sodium coolant

    550C outlet temperature

    600-1500 MWe large size, or

    300-600 MWe intermediate size

    50 MWe small module option

    Metal fuel with pyroprocessing or

    MOX fuel with advanced aqueous

    separation

    Benefits

    High thermal efficiency

    Consumption of LWR actinides

    Efficient fissile materialgeneration

    http://www.gen-4.org/Technology/systems/index.htm

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    Very -High -Temperatu re Reacto r (VHTR)

    Characteristics He coolant

    >900C outlet temperature

    250 MWe

    Coated particle fuel in eitherpebble bed or prismatic fuel

    Benefits Hydrogen production

    Process heat applications

    High degree of passive safety

    High thermal efficiency option

    http://www.gen-4.org/Technology/systems/index.htm

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    Gas-Coo led Fast Reacto r (GFR)

    Characteristics He coolant

    850C outlet temperature

    Direct gas-turbine cycle or

    supercritical CO2 cycle with

    optional combined cycles

    2400 MWth / 1100 MWe

    Several fuel options

    Carbide in plates or pins

    Nitride

    Oxide

    Benefits

    High efficiency Waste minimization and

    efficient use of uranium

    resources

    http://www.gen-4.org/Technology/systems/index.htm

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    Supercri t ic al-Water-Coo led Reacto r (SCWR)

    Characteristics Water coolant above

    supercritical conditions (374C,22.1 MPa)

    510-625C outlet temperature

    1500 MWe

    Pressure tube or pressurevessel options

    Simplified balance of plant

    Benefits

    Efficiency near 45% withexcellent economics

    Leverages the currentexperience in operating fossil-

    fueled supercritical steamplants

    Configurable as a fast- orthermal-spectrum core

    http://www.gen-4.org/Technology/systems/index.htm

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    Lead-Coo led Fast Reacto r (LFR)

    Characteristics Pb or Pb/Bi coolant

    550C to 800C outlet temperature

    Small transportable system 50-150 MWe, and

    Larger station 300-1200 MWe

    1530 year core life option

    Benefits

    Distributed electricity generation

    Hydrogen and potable water

    Replaceable core for regionalfuel processing

    High degree of passive safety

    Proliferation resistance throughlong-life core

    http://www.gen-4.org/Technology/systems/index.htm

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    Molten Salt Reacto r (MSR)

    Characteristics

    Fuel is liquid fluorides of U and Pu

    with Li, Be, Na and other fluorides

    700800C outlet temperature

    1000 MWe

    Low pressure (

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    System

    Neutron

    Spectrum

    Fuel

    Cycle

    Size

    (MWe) Appl ic at ions R&D Needed

    Very-High-

    Temp erature Reactor

    (VHTR)

    Thermal Open 250 Electricity, Hydrogen,

    Process Heat

    Fuels, Materials,

    H2 production

    Supercrit ical-Water

    Reactor (SCWR)

    Thermal,

    Fast

    Open,

    Closed

    1500 Electricity Materials, Thermal-

    hydraulics

    Gas-Cooled Fast

    Reactor (GFR)

    Fast Closed 200-1200 Electricity, Hydrogen,

    Actinide Management

    Fuels, Materials,

    Thermal-hydraulics

    Lead-Cooled Fast

    Reactor (LFR)

    Fast Closed 50-150

    300-600

    1200

    Electricity,

    Hydrogen Production

    Fuels, Materials

    Sodium Cooled FastReactor (SFR)

    Fast Closed 300-1500 Electricity, ActinideManagement

    Advanced recycleoptions, Fuels

    Molten Salt Reactor

    (MSR)

    Epithermal Closed 1000 Electricity, Hydrogen

    Production, Actinide

    Management

    Fuel treatment,

    Materials, Reliability

    Overview o f the Generat ion IV Sys tems

    http://www.gen-4.org/Technology/systems/index.htm

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    Formal Ag reements fo r R&D

    GIF Framework Agreement: An agreement among the governments

    For research and development collaborations

    Assigns responsible ministries, departments and agencies

    Affords protection of intellectual property and sharing of rights

    Specifies steer ing commit tees for systems to manage the work,

    and projects under the steering committee to do the work

    Supports the creation of multilateral R&D contracts that can attract

    industry, universities and other countries into the collaborations

    GIF Framework

    Agreement Signing

    (Feb 2005)

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    Project Management

    Boards

    Project Management

    Boards

    Energy Conversion

    Project Management

    Boards

    Structu red Agreements

    System Steer ing

    Commit tees

    Project Management

    Boards

    System

    Arrangements

    Project

    Arrangements

    Framewo rk Ag reementPart ies:

    Canada,

    China,

    Euratom,

    France,

    Japan,

    Republ ic of Ko rea,

    South Afr ica,

    Switzerland,

    United States

    Undertaking accession :

    Russia

    Fuel and Fuel Cyc le

    Materials

    other

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    Todays Membership

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    System Partners

    VHTR Very-High-Temp erature ReactorGFR Gas-Cooled Fast ReactorSFR Sodium -Cooled Fast ReactorSCWR Supercri t ical Water-Cooled ReactorLFR Lead-Cooled Fast ReactorMSR Molten Salt Reactor

    Apr 2008

    ANRE Agenc y for Natural Resources and Energy (JP)CAEA China Atomic Energy Author i ty (CN)

    CEA Commissariat lnergie Atomique (FR)

    DME Department of Minerals and Energy (ZA)DOE Department of Energ y (US)JAEA Japan Atomic Energy Agency (JP)JRC Join t Research Centre (EU)KOSEF Korean Science and Engineer ing Found at ion (KR)MEST Minist ry of Educat ion, Science and Technology (KR)MOST Minist ry of Science and Technology (CN)NRCan Natural Resources Canada (CA)PSI Paul Scherrer Inst i tute (CH)

    http://www.gen-4.org/GIF/Governance/framework.htmhttp://www.gen-4.org/GIF/Governance/system.htm

    Partners: NRCan JRC CEA JAEA, MEST, PSI DOE CAEA, DMEANRE KOSEF MOST

    VHTRGFR

    SFR

    LFR

    MSR

    SCWR

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    Research Plans and Activ i t ies

    System Steering Committees each create a

    System Research Plan

    Four systems have finalized plans

    SFR, SCWR, VHTR and GFR

    LFR is under development

    MSR is planned in the future

    Each creates several projects

    Project participants make binding

    commitments for the scope, schedule

    and resources for their contribution

    Universities, industry and even

    countries outside the GIF may

    participate, with the approval of the

    Steering Committee

    http://www.gen-4.org/GIF/Governance/system.htm

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    Working Toward the Future

    The GIF joined together to help assure a sustainable energy future Underscored by the advance of global climate change

    Based on advanced nuclear energy systems that are sustainable,

    safe, economical, proliferation resistant and physically secure

    Accelerated by the collaboration of the GIF members, industry,

    academia and non-member nations and institutions