introduction to generation iv nuclear energy systems iv isu... · 3 • nuclear is a major...

Introduction to Generation IV Nuclear Energy Systems

Dr. Ralph Bennett, Technical Director, Generation IV International Forum, andDirector, International and Regional Partnerships, Idaho National Laboratory

16 Mar 2009

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The Problem of Climate 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 Warming (deg C) by 2100 (IPCC prediction)

http://www.aip.org/history/climate/summary.htm http://www.grida.no/climate/ipcc_tar/

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

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• Nuclear is a major contributor in the WEO 2008 450 Policy Scenario— about 250 GWe more generation by 2030 (an 80% increase from today)

• Nuclear energy systems must continue their advances in order to unlock a potential on this scale

The Challenge for Nuclear Energy

http://www.iea.org/weo/2008.asp

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Generations of Nuclear 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 and Physically Secure

Generation IV

RevolutionaryDesigns

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

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Creation of the International 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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Today’s Membership

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SystemNeutron Spectrum

FuelCycle

Size (MWe) Missions R&D Needed

Sodium Cooled Fast Reactor (SFR)

Fast Closed 300-1500 Electricity, Actinide Management

Advanced recycle options, Fuels

Very-High- Temperature Reactor (VHTR)

Thermal Open 250 Electricity, Hydrogen, Process Heat

Fuels, Materials,H2 production

Gas-Cooled FastReactor (GFR)

Fast Closed 1200 Electricity, Hydrogen,Actinide Management

Fuels, Materials,Thermal-hydraulics

Supercritical-Water Reactor (SCWR)

Thermal,Fast

Open,Closed

1500 Electricity Materials, Thermal- hydraulics

Lead-Cooled Fast Reactor (LFR)

Fast Closed 50-150300-6001200

Electricity,Hydrogen Production

Fuels, Materials

Molten Salt Reactor(MSR)

Epithermal or Fast

Closed 1000 Electricity, Hydrogen Production, Actinide Management

Fuel treatment, Materials, Reliability

Overview of the Generation IV Systems

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

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Sodium-Cooled Fast Reactor (SFR)Characteristics

• Sodium coolant, pool or loop type• 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 material

generation


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Primary Pump/IHX

Reactor Vessel

SG

Secondary Pump

IHXDHXPHTS pump

Reactor core

Steam Generator

AHX Chimney

PDRC piping

In-vessel core catcher

IHTS piping

IHTS pump

IHXDHXPHTS pump

Reactor core

Steam Generator

AHX Chimney

PDRC piping

In-vessel core catcher

IHTS piping

IHTS pump

12.03 m3,186 gal.

PLAN VIEW OF THE CORE

PRIMARYCONTROL RODS

1m TRAVEL DISTANCEOF THE CONTROL RODS

(10'-8")

THERMALSHIELD

(29.5")0.75m

3.25m

Na-COHEAT EXCHANGER

7m

IHXX-SECTION (FLATTENED FOR CLARITY)

(23')

(Ø 7.5' x 12.6' LONG)

IHX

2

SECTION A - A

Normal sodium level

Normal sodium level

Sodium faulted level

Pump offSodium Level

SODIUM DUMP TANKØ 2.5 m x 3.8 m LONG

CORE BARREL Ø266 / 268 cm(104.7" / 105.5")

SECONDARYCONTROL RODS

CONTROLRODS (7)

PUMPS (2)ON Ø 142.5" B.C.

PLAN VIEW OFIHX AND PUMPS IHX (2)

1.7m EACH2

DRACS (2)0.4m EACH2

Primary Vessel I.D.

Guard Vessel I.D.

Hot Pool

Cold Pool

PRIMARY VESSEL(2" THICK)

3.5m(11'-8")

GUARD VESSEL(1" THICK)

1m(39.4")

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TURBINE/GENERATORBUILDING

ELEVATOR

(Ø 25.5')Ø 7.7m

Na-AirHEAT EXCHANGER (2)

CONTROLBUILDING

0 1 2 3 10METERS4 5

5.08m [16.7FT]

4.57m [15FT]

7m [23FT]

1.89m [6.2FT]

12.72m [41.7FT]

14.76m [48.4FT]

1.93m [6.3FT]

.61m [2FT]

2.29m [7.5FT]

EXHAUST TO VENT STACK

Large-scale Loop

Intermediate-scale Pool

Small-scale Modular

SFR Reactor Options

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• Minor actinide bearing fuel technology (fabrication, irradiation)– Metal and oxide fuel performance– Carbide fuel performance– Nitride/Carbide fuel performance

• Inspection & repair technologies– Ultrasonic and alternative techniques– Replace/repair experience

• High temperature leak-before-break assessment technologies– Creep-fatigue crack initiation and growth test results

• Advanced energy conversion concepts– Basic design concept of supercritical CO2 Brayton cycle system – Compact supercritical CO2-to-CO2 heat exchangers

SFR Technology Interests

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Very-High-Temperature Reactor (VHTR)Characteristics

• He coolant• >900C outlet temperature• 250 MWe• Coated particle fuel in either

pebble bed or prismatic fuel

Benefits• Hydrogen production• Process heat applications• High degree of passive safety• High thermal efficiency option


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VHTR Reactor OptionsPebble bed core Prismatic-fuel core

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VHTR Hydrogen Options

Porous Anode, Strontium -doped Lanthanum Manganite

Gastight Electrolyte, Yttria-Stabilized Zirconia

Porous Cathode, Nickel -Zirconia cermet

2 H20 + 4 e- 2 H2 + 2 O=

2 O= O2 + 4 e-

2 O=

H2O

H2

O2

4 e-

Interconnection

H2O + H2

Next Nickel-Zirconia Cermet CathodeH2O

H2




2 H20 + 4 e- 2 H2 + 2 O=

2 O= O2 + 4 e-

2 O=

H2O

H2

O2

4 e-

2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 10 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H2

Interconnection

H2O + H2


H2




2 H20 + 4 e- 2 H2 + 2 O=

2 O= O2 + 4 e-

2 O=

H2O

H2

O2

4 e-

Interconnection

H2O + H2


H2




2 H20 + 4 e- 2 H2 + 2 O=

2 O= O2 + 4 e-

2 O=

H2O

H2

O2

4 e-

2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H90 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 10 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H2

Interconnection

H2O + H2


H2

Sulfur-iodine cycle

High temperature electrolysis

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• Fuel and fuel cycle– Particle fuel irradiations and fission product monitoring

• Materials– Codes and standards extension– Materials database extension– Graphite dust behavior

• Hydrogen production– Sulfur-iodine cycle– High temperature electrolysis– Coupling of H2 production process and reactor heat transport system– Tritium transport

• Computational Methods• Components and helium turbine

– Intermediate heat exchanger

VHTR Technology Interests

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Lead-Cooled Fast Reactor (LFR)Characteristics

• Pb or Pb/Bi coolant• 550C to 800C outlet temperature• Small transportable system 50-

150 MWe, and• Larger station 300-1200 MWe• 15–30 year core life option

Benefits• Distributed electricity generation• Hydrogen and potable water• Replaceable core for regional

fuel processing• High degree of passive safety• Proliferation resistance through

long-life core


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LFR Reactor Options

Small, transportable module

CLOSURE HEAD

CO2 INLET NOZZLE (1 OF 4)

CO2 OUTLET NOZZLE (1 OF 8)

Pb-TO-CO2 HEAT EXCHANGER (1 OF 4)

ACTIVE CORE AND FISSION GAS PLENUM

RADIAL REFLECTOR

FLOW DISTRIBUTOR HEAD

FLOW SHROUDGUARD VESSEL

REACTOR VESSEL

CONTROL ROD DRIVES

CONTROL ROD GUIDE TUBES AND DRIVELINES

THERMAL BAFFLE

Large, stationary plant

• Pb coolant (both)• No intermediate loops

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• Collaborations based on ELSY and SSTAR – No formal agreement yet

• Conceptual design and safety – Innovative components and design

– Compact, in-vessel steam generators– Decay heat removal by air and water– Refueling ‘out-of-Pb’ coolant

– Innovative structural design– Buoyant fuel element support– Seismic isolation of reactor building

• Fuel and core materials– Many options

LFR Technology Interests

ELSY: European Lead-cooled System; SSTAR: Small Secure Transportable Autonomous Reactor

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Supercritical-Water-Cooled Reactor (SCWR)Characteristics

• Water coolant above supercritical conditions (374C, 22.1 MPa)

• 510-625C outlet temperature• 1500 MWe• Pressure tube or pressure

vessel options• Simplified balance of plant

Benefits• Efficiency near 45% with

excellent economics• Leverages the current

experience in operating fossil- fueled supercritical steam plants

• Configurable as a fast- or thermal-spectrum core


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Gas-Cooled Fast Reactor (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


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Molten Salt Reactor (MSR)Characteristics

• Fuel is liquid fluorides of U or Th with Li, Be, Na and other fluorides

• 700–800C outlet temperature• 1000 MWe• Low pressure (<0.5 MPa)

Benefits• Waste minimization• Avoids fuel development• Proliferation resistance through

low fissile material inventory


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OrganizationPolicy Group

Chair (France)

Chair

System Steering Committees

Co-Chairs

Project Management Boards

(multiple R&D projects)

Methodology Working Groups

Proliferation Resistance and Physical Protection,

Risk & Safety, Economics

Policy Secretariat

Policy TechnicalDirector Director

NEA, Paris

Technical Secretariat

Experts Group

Senior IndustryAdvisory Panel

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

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System Partners

VHTR – Very-High-Temperature ReactorGFR – Gas-Cooled Fast ReactorSFR – Sodium-Cooled Fast ReactorSCWR – Supercritical Water-Cooled ReactorLFR – Lead-Cooled Fast ReactorMSR – Molten Salt Reactor

Mar 2009

ANRE – Agency for Natural Resources and Energy (JP)CAEA – China Atomic Energy Authority (CN)CEA – Commissariat à l’Énergie Atomique (FR)DME – Department of Minerals and Energy (ZA)DOE – Department of Energy (US)JAEA – Japan Atomic Energy Agency (JP)JRC – Joint Research Centre (EU)KOSEF – Korean Science and Engineering Foundation (KR)MEST – Ministry of Education, Science and Technology (KR)MOST – Ministry of Science and Technology (CN)NRCan – Natural Resources Canada (CA)PSI – Paul Scherrer Institute (CH)

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

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

VHTR

GFR

SFR

LFR

MSR

SCWR

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Generation IV Annual Report• Captures key information and accomplishments

from System Steering Committee annual reports into one widely distributed report

• Captures brief summaries of working groups’ accomplishments, and background on the Forum

• Audience includes:– World-wide Research and Development

Community– Governments sponsoring Generation IV R&D– GIF committees, boards and working groups

• The 2008 Report has just issued

http://www.gen-4.org/PDFs/GIF_2008_Annual_Report.pdf

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Working Toward the FutureThe 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

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Bibliography• The web links provided on most slides lead to source

documents, background materials or updates• The full Generation IV Roadmap and all supporting documents

are available at: http://gif.inel.gov/roadmap/• Some technical papers are listed on the OECD NEA website (GIF

website) at www.gen-4.org within each system• Recent outlook articles on nuclear deployment:

– IEA http://www.iea.org/weo/2008.asp (subscription)– NEA http://www.nea.fr/neo/ (subscription)– IAEA http://www-pub.iaea.org/MTCD/publications/PDF/RDS1-28_web.pdf– WNA http://www.world-nuclear.org/outlook/clean_energy_need.html– EPRI (US R&D strategy and deployment outlook, respectively)

http://my.epri.com/portal/server.pt?Product_id=000000000001018514.pdf– http://my.epri.com/portal/server.pt?Product_id=000000000001018431.pdf

• My contact information:– [email protected]

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