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Roadmap Integration Team Presentation
RELAP5 User Mtg 04-Sept-2002
The Generation IV R&D Roadmap Overview
RELAP5 Users Meeting: Park City, UTSeptember 4, 2002
Roadmap Integration Team Presentation
Slide 2RELAP5 User Mtg 04-Sept-02
Objective – Next Generation Nuclear EnergyThe Technology Roadmap:
• Describes systems deployable by 2030 or earlier
• Determines which systems offer significant advances towards:
– Sustainability
– Safety and reliability
– Economics
• Plans activities for a Generation IV R&D program
Roadmap Integration Team Presentation
Slide 3RELAP5 User Mtg 04-Sept-02
Key Steps to Prepare the Roadmap• Define Technology Goals for Generation IV
• Identify Concepts with Potential
• Evaluate Concepts with a CommonMethodology
• Identify R&D Gaps and Needs
• Assemble a Program Plan
Roadmap Integration Team Presentation
Slide 4RELAP5 User Mtg 04-Sept-02
Organizational Evolution
NERAC
GEN IV RoadmapNERAC Subcommittee
(GRNS)
DOE-NE
Roadmap IntegrationTeam (RIT)
Generation IV InternationalForum (GIF)
Argentina Brazil France
S. Africa Korea UK US
Canada Japan
• Jan 2000 First Meeting of 9 Countries on Generation IV
• Sep 2000 Creation of NERAC Subcommittee
Roadmap Integration Team Presentation
Slide 5RELAP5 User Mtg 04-Sept-02
Organizational Evolution
NERAC
GEN IV RoadmapNERAC Subcommittee
(GRNS)
Technical Community
• Industry
• Universities
• National Laboratories
DOE-NE
Roadmap IntegrationTeam (RIT)
Evaluation Methodology
Water-Cooled Reactors
Gas-Cooled
Liquid-Metal-Cooled
Non-Classical ConceptsFu
el C
ycle
Cro
sscu
t
Generation IV InternationalForum (GIF)
Argentina Brazil France
S. Africa Korea UK US
Canada Japan
• Dec 2000 Creation of Working Groups and Fuel Cycle Crosscut
• Mar 2001 Incorporation of International Membership
Roadmap Integration Team Presentation
Slide 6RELAP5 User Mtg 04-Sept-02
Organizational Evolution
NERAC
GEN IV RoadmapNERAC Subcommittee
(GRNS)
Technical Community
• Industry
• Universities
• National Laboratories
DOE-NE
Roadmap IntegrationTeam (RIT)
Evaluation Methodology
Water-Cooled Reactors
Gas-Cooled
Liquid-Metal-Cooled
Non-Classical ConceptsFu
el C
ycle
Cro
sscu
t
Fuel
s &
Mat
eria
ls
Ris
k &
Saf
ety
Econ
omic
s
Ener
gy P
rodu
cts
Generation IV InternationalForum (GIF)
Argentina Brazil France
S. Africa Korea Switzerland UK US
Canada Japan
• Sep 2001 Organization of Crosscut Groups
• Feb 2002 Switzerland joins the GIF
Roadmap Integration Team Presentation
Slide 7RELAP5 User Mtg 04-Sept-02
GIF MeetingsJanuary 2000 Washington Countries support Gen IV idea
April 2000 Washington Experts convened on path forward
August 2000 Seoul Comment on goals, write charter
March 2001 Paris Finalize charter, support roadmap
October 2001 Miami Comment on methodology
February 2002 London Discuss concepts and selection
April 2002 Washington Review concept evaluations
May 2002 Paris Select 6-8 long-term concepts
July 2002 Rio de Janeiro Review R&D plans
September 2002 Tokyo Plan R&D collaborations
March 2003 Capetown Plan R&D collaborations
Roadmap Integration Team Presentation
Slide 8RELAP5 User Mtg 04-Sept-02
Important Missions for Generation IV
2000 2005 2010 2015 2020 2025 2030 2035 2040 2045 2050 2055 2060 2065
Hydrogen
Electricity Generation
Waste Burndown
Fissile Creation
Nearer-TermSystems
Actinide Management
Roadmap Integration Team Presentation
Slide 9RELAP5 User Mtg 04-Sept-02
Sodium Liquid Metal-Cooled Reactor (Na LMR)Characteristics•Sodium coolant, 550°C•150 to 500 MWe•Metal fuel with pyroprocessing / MOX fuelwith advanced aqueous
Benefits•Consumption of LWRactinides
•Efficient fissile materialgeneration
Roadmap Integration Team Presentation
Slide 10RELAP5 User Mtg 04-Sept-02
Very High-Temperature Reactor (VHTR)Characteristics•He coolant•1000°C outlet temperature•600 MWe•Solid graphite block corebased on GT-MHR
Benefits•High thermal efficiency•Hydrogen production•Process heat applications•High degree of passivesafety
Roadmap Integration Team Presentation
Slide 11RELAP5 User Mtg 04-Sept-02
SERSI
TURBINE
ALTERNATOR
RECUPERATOR
510°C2.5 MPa
125°C
850°C8 MPa
H. P. COMPRESSOR
INT.EXCHANGER
L. P. COMPRESSOR
PRE COOLER
490°C
Radial blanket
Axial blanket
Efficiency : # 50%
Aux.Exchanger
SERSI
TURBINE
ALTERNATOR
RECUPERATOR
510°C2.5 MPa
125°C
850°C8 MPa
H. P. COMPRESSOR
INT.EXCHANGER
L. P. COMPRESSOR
PRE COOLER
490°C
Radial blanket
Axial blanket
Efficiency : # 50%
Aux.Exchanger
Gas-Cooled Fast Reactor (GFR)Characteristics
• He coolant• 850°C outlet temperature• direct gas-turbineconversion cycle –48% efficiency
• 600 MWth/288 MWe
• Several fuel options andcore configurations
Benefits• Waste minimization andefficient use of uraniumresources
Roadmap Integration Team Presentation
Slide 12RELAP5 User Mtg 04-Sept-02
Supercritical Water Reactor (SCWR)Characteristics•Water coolant atsupercritical conditions
•550°C outlet temperature•1700 MWe•Simplified balance ofplant
Benefits•Efficiency near 45% withexcellent economics
•Thermal or fast neutronspectrum
Roadmap Integration Team Presentation
Slide 13RELAP5 User Mtg 04-Sept-02
Pb/Bi Reactor – Cartridge Core (Pb/Bi Battery)Characteristics•Pb/Bi or Pb coolant•550°C to 800°C outlettemperature
•120-400 MWe•15-30 year core life
Benefits•Distributed electricitygeneration
•Hydrogen and potable water•Cartridge core for regionalfuel processing
•High degree of passive safety•Proliferation resistancethrough long-life cartridgecore
Roadmap Integration Team Presentation
Slide 14RELAP5 User Mtg 04-Sept-02
Molten Salt Reactor (MSR)Characteristics•Fuel: liquid U, Puflorides,NaF/Zr F4
•700 – 800 °C outlettemperature
•1000 MWe•Low pressure (<0.5 MPa)
Benefits•Low source term due toonline processing
•Waste minimization andefficient use of uraniumresources
•Proliferation resistancethrough low fissilematerial inventory
HeatExchanger
Reactor
GraphiteModerator
SecondarySalt Pump
Off-gasSystem
PrimarySalt Pump
PurifiedSalt
ChemicalProcessing
Plant
Turbo-Generator
FreezePlug
Critically Safe, Passively Cooled Dump Tanks(Emergency Cooling and Shutdown)
Steam Generator
NaBF _NaFCoolant Salt
4
72LiF _Th
Fuel Salt_BeF F _UF4 4
566 Co
704 Co
454 Co
621 Co
538 Co
Roadmap Integration Team Presentation
Slide 15RELAP5 User Mtg 04-Sept-02
Highlights of System Concept StrengthsSustainability• Closed cycle fast-spectrum systems
– Reduced waste heat and radiotoxicity– Optimal use of repository capacity– Resource extension via regeneration of fissile material
Safety and Reliability• Many concepts make good advances
Economics• Water- and gas-cooled concepts
– High thermal efficiency– Simplified balance of plant– Large and small plant size
Hydrogen production and high-temperature applications• Temperatures above 700-800°C
Roadmap Integration Team Presentation
Slide 16RELAP5 User Mtg 04-Sept-02
Selected Highlights of the R&D Challenges
• Fuels and materials for higher temperatures• Increased corrosion/erosion in alternative coolants• Design for inherent safety• Recycling technology and methods• Fuel fabrication methods• Hydrogen thermochemical processes• Manufacturing and constructability• Component technologies
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