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Advances in Reactor Concepts: Generation IV Reactors
Research Workshop Future Opportunities in Nuclear Power
October 16-17, 2014 Purdue University
Prof. Won Sik Yang Purdue University
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Nuclear energy is a significant contributor to U.S. and international electricity production – 15% world, 20% U.S., 74% France
Status of Nuclear Power Production
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Nuclear energy and hydropower are the only two major established base-load low-carbon energy sources.
Efforts to reduce CO2 emissions are thus a major factor in the renewed interest in nuclear energy that has become apparent in recent years.
Status of Nuclear Power Production
IEA/NEA, Nuclear Energy Technology Roadmap (2010)
World Electricity Generation (2009)
Total: 20130 TWh
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Future Use of Nuclear Energy
Extended lifetime and optimized operation of existing plants Construction of new plants (evolutionary designs in near term) Closure of fuel cycle to improve waste management
– Strengthened international safeguards regime Sustainable generation of electricity, hydrogen and other energy
products
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Generations of Nuclear Reactors
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Generation IV Systems: Technology Goals
Sustainability – Sustainable energy generation through long-term availability of
systems and effective fuel utilization – Minimize and manage nuclear waste and reduce the stewardship
burden in the future Safety & Reliability
– Very low likelihood and degree of reactor core damage – Eliminate the need for offsite emergency response
Economics – Life-cycle cost advantage over other energy sources – Level of financial risk comparable to other energy projects
Proliferation Resistance & Physical Protection – Unattractive materials diversion pathway – Enhanced physical protection against terrorism
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System
Neutron Spectrum
Fuel /Fuel Cycle
Coolant Temp. (C)
Power (MWe)
Plant Effici. (%)
Applications
Sodium Cooled Fast Reactor (SFR)
Fast MOX, Metal /Closed
500 - 550 50 300-600 1500
42 Electricity, Actinide Recycle
Very High Temperature Reactor (VHTR)
Thermal Coated particles /Open
900 -1000 250 > 47 Electricity, Hydrogen Production, Process Heat
Gas-Cooled Fast Reactor (GFR)
Fast Carbides /Closed
850 200-1200
45 - 48 Electricity, Hydrogen Production, Actinide Recycle
Supercritical Water Reactor (SCWR)
Thermal, Fast
UOX, MOX /Open; Closed
510 - 625 1500 Max. 50 Electricity
Lead-Cooled Fast Reactor (LFR)
Fast Nitrides; MOX /Closed
480 - 570 50-150 300-600 1200
42 - 44 Electricity, Hydrogen Production
Molten Salt Reactor (MSR)
Thermal, Fast
Fluorides salts /Closed
700 - 800 1000 Max. 45 Electricity, Hydrogen Production, Actinide Recycle
Overview of Generation IV Systems
A Technology Roadmap for Generation IV Nuclear Energy Systems, December 2002 GIF R&D Outlook for Generation IV Nuclear Energy Systems, August 2009
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Sodium-Cooled Fast Reactor (SFR)
KALIMER
ESFR
JSFR SMFR
Features fast spectrum and closed fuel cycle – Can either burn actinides or breed fissile material
High level of safety can be achieved through inherent and passive means
R&D focus – Analyses and experiments that demonstrate safety
approaches – High-burnup, minor actinide bearing fuels – Develop advanced components and energy conversion
systems
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In the US, innovative fast reactor designs are being developed – Advanced burner sodium-cooled fast reactor (ABR) for waste management – Breed and burn nuclear systems for improved fuel utilization – Small modular reactors for near-term deployment in remote locations and
other countries China has constructed CEFR, which achieved the initial criticality on
July 21, 2010. Developing CFR-600 with oxide fuel, but will be converted to metallic fuel.
In India, the 500 MWe DFBR is expected to be online soon; they plan to construct 4 more 500 MWe units by 2020, and then 1000 MWe plants
Russia has constructed a BN-800 reactor, which achieved the initial criticality on June 27, 2014, and is developing the BN-1200 design
Japan envisions commercial fast reactors by 2050, and plans to construct a demo plant by 2025 (JSFR)
France envisions commercial fast reactors by ~2045, and plans a demo plant by 2020 (ASTRID)
Korea is developing the 150 MWe PGSFR design for demonstrating TRU transmutation
Designs Being Developed
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Very High Temperature Reactor (VHTR)
High temperature, helium cooled, graphite moderated reactor – High temperature enables non-electric applications
Goal – reach 1000 °C, with near term focus on 700 - 950 °C Reference configurations are the prismatic and the pebble bed
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Very High Temperature Reactor (VHTR)
R&D focus on materials and fuels – Shared irradiation
• Confirmed excellent performance of UO2 TRISO fuel
– Develop a worldwide material handbook – Benchmarking of computer codes
Japanese HTTR (30 MWt) is in operation – 50 days continuous operation at 950 °C
completed March 2010 Chinese HTR-PM demonstration plant is
under construction – Pebble bed core, 750 °C outlet temperature,
steam cycle, 40% efficiency – Two 250 MWt NSSS modules for 210 MWe
electricity – First concrete poured in Dec. 2012 – Plant operation expected around end of 2017
HTR-PM
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Gas-Cooled Fast Reactor (GFR)
Decay heat removal (LOCA) is a challenge – High power density – Low thermal inertia
High temperature, helium cooled fast reactor with closed fuel cycle – Fast spectrum enables efficient
use of uranium resources and waste minimization
– High temperature enables non-electric applications
– Non-reactive coolant eliminates material corrosion
Very advanced system – Requires advanced materials
and fuels Key R&D focus
– SiC clad carbide fuel – High temperature components
and materials
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Supercritical-Water-Cooled Reactor (SCWR)
0
5
10
15
20
25
30
250 350 450 550Temperature (C)
Pres
sure
(MPa
)
SCWR
PWR
BWR
superheated vapor
supercritical fluid
vapor
liquid
compressible liquid Merges Gen-III+ reactor technology with advanced supercritical water technology used in coal plants
Operates above the thermodynamic critical point (374 °C, 22.1 MPa) of water
Fast and thermal spectrum options Pressure tube or pressure vessel
options Key R&D focus
– Materials, water chemistry, and radiolysis – Thermal-hydraulics and safety to address
gaps in SCWR heat transfer and critical flow databases
– Fuel qualification
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Lead-Cooled Fast Reactor (LFR)
ELFR
– 1500 MWt / 600 MWe – MOX fuel – Coolant temp., 400/480C – Max. clad temp., 550C – Efficiency: ~42% – Breeding ratio: ~1
Lead is not chemically reactive with air or water – Highly corrosive and erosive
Fast spectrum and closed fuel cycle Three design thrusts
– European Lead Cooled Fast Reactor (Large, central station)
– Russian BREST-OD-300 (Medium size)
– US SSTAR (Small transportable system)
R&D focus – Materials corrosion – High burnup, MA-bearing fuels – Safety
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LFR Concepts Being Studied
BREST-OD-300 – 700 MWt / 300 MWe – UN+PuN fuel – Coolant temp: 420/540C – Max. cladding temp., 650C – Efficiency: 42% – Breeding ratio: ~1
SSTAR – SSTAR is a small natural
circulation fast reactor of 20 MWe/45 MWt, that can be scaled up to 180 MWe/400 MWt.
– Uranium nitride fuel with 15-20 year lifetime
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Molten Salt Reactor (MSR)
MSFR – Since 2005, European R&D interest
has focused on Molten Salt Fast neutron Reactor (MSFR) as a long term alternative to solid fueled fast neutrons reactors
High temperature system Design options
– Fuel dissolved in molten salt coolant • Traditional MSF concept • On-line waste management
– Solid fuel with molten salt coolant • VHTR + molten salt coolant
Key R&D focus – Neutronics – Materials and components – Safety and safety systems – Liquid salt chemistry and properties – Salt processing
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Two reactors concepts using molten salt are studied in the GIF MSR – Molten salt reactors, in which the salt is both the fuel and the coolant
• France and Euratom work on MSFR • Russia works on MOSART (Molten Salt Actinide Recycler & Transmuter)
– Reactors with solid fuel cooled by molten salt • USA and China work on FHR (fluoride salt-cooled
|high-temperature reactor) concepts
MSR Concepts Studied
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Summary
Generation-IV systems are being developed worldwide – Gen-IV International Forum was established in 2001 and provides
an international framework for development of Gen-IV systems – Collaborative projects started with significant R&D investment
worldwide – Prototype demonstration reactors are being designed and/or built
• SFR (France and Russia) • VHTR (China)
Much still needs to be done before Gen-IV systems become a reality – Continue R&D on Gen-IV systems – Develop advanced research facilities – Engage industry on the design of Gen-IV systems – Develop the workforce for the future
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