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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