Liquid Metal Fast Liquid Metal Fast Breeder ReactorsBreeder Reactors

Martin W. MetznerMartin W. Metzner

November 19, 2007November 19, 2007

Overview of Fast Breeder ReactorsOverview of Fast Breeder Reactors

Produce more fissile material than is consumedProduce more fissile material than is consumed

Technology first developed in the 1950’sTechnology first developed in the 1950’s

Utilize uranium 60 times as efficienctly as PWRsUtilize uranium 60 times as efficienctly as PWRs

Cooled by liquid metalCooled by liquid metal

Fast Breeder Reactors vs. Pressurized Water Fast Breeder Reactors vs. Pressurized Water ReactorsReactors

FBRFBR Fuel is enriched to 15-Fuel is enriched to 15-

20%20% Moderator: noneModerator: none Heat transfer by liquid Heat transfer by liquid

metal or metal alloysmetal or metal alloysTypically sodiumTypically sodium

Reactor under low Reactor under low pressurepressure

~1.2 fissile atoms ~1.2 fissile atoms produced per fissionproduced per fission

PWRPWR Fuel is enriched to 3-Fuel is enriched to 3-

5%5% Moderator: waterModerator: water Heat transfer by waterHeat transfer by water Reactor under high Reactor under high

pressurepressure Fissile material is only Fissile material is only

consumed consumed

Breeding FuelBreeding Fuel

TheoryTheory Each fission produces Each fission produces

on average 2.4 on average 2.4 neutrons neutrons

Fissile material: U-235, Fissile material: U-235, Pu-239 or Pu-241Pu-239 or Pu-241

Critical reactionCritical reactionOne neutron per fission One neutron per fission causes another fissioncauses another fission

1.4 neutrons are left 1.4 neutrons are left over to enrich depleted over to enrich depleted fuelfuel

PracticePractice Typical FBR produces Typical FBR produces

about 1.2 fissile atoms about 1.2 fissile atoms per consumed fissile per consumed fissile atomatom

Can produce enough Can produce enough fissile material in 10 fissile material in 10 years to replace spent years to replace spent fuel and enough to fuel and enough to power another reactor power another reactor for 10 yearsfor 10 years

FBR DesignFBR Design

1)1) Highly enriched uranium Highly enriched uranium or plutoniumor plutonium

2)2) Control rods (same Control rods (same material as core)material as core)

3)3) Depleted uraniumDepleted uranium

4)4) Heat is transferred from Heat is transferred from primary to secondary primary to secondary sodiumsodium

5)5) Heat is transferred from Heat is transferred from secondary sodium to secondary sodium to waterwater

Figure: Baksiden, modified by Martin Metzner

Nuclear FuelNuclear Fuel

Initially FBRs were designed to use pure Initially FBRs were designed to use pure uranium oxide fueluranium oxide fuelEventually switched to MOXEventually switched to MOX Mixed oxide fuel (MOX):Mixed oxide fuel (MOX):

Mixture of UOMixture of UO22 and PuO and PuO22

Already an existing source of fissile plutoniumAlready an existing source of fissile plutonium Nuclear warheadsNuclear warheads

Highly enriched, former USSR and USA currently dismantling Highly enriched, former USSR and USA currently dismantling arsenalsarsenals

Depleted PWR fuelDepleted PWR fuelLow enrichment caused by the fusion of U-238 and a neutronLow enrichment caused by the fusion of U-238 and a neutronMust be processed before it can be usedMust be processed before it can be used

Liquid Metal CoolantLiquid Metal Coolant

Typical metal used is sodiumTypical metal used is sodium Some reactors use lead, lead-bismuth alloy, or Some reactors use lead, lead-bismuth alloy, or

sodium fluoride saltsodium fluoride salt

Advantages of sodiumAdvantages of sodium Low melting temperature (98Low melting temperature (98°C)°C) High boiling temperature (892°C)High boiling temperature (892°C) High heat capacityHigh heat capacity System can run at low pressureSystem can run at low pressure

Risks of sodiumRisks of sodium Burns when it comes in contact with air or waterBurns when it comes in contact with air or water Poisonous fumesPoisonous fumes

FBRs TodayFBRs TodayOnly six active todayOnly six active today

Half of these are in RussiaHalf of these are in Russia

Average lifespan of reactors is Average lifespan of reactors is only about 20 yearsonly about 20 years

Many shut down prematurelyMany shut down prematurely Superphenix (France) and Superphenix (France) and

KNK 2 (Germany) were never KNK 2 (Germany) were never operationaloperational

Plagued by political Plagued by political controversycontroversy

Only one notable accidentOnly one notable accident Monju (Japan) in 1995Monju (Japan) in 1995 A pipe carrying secondary A pipe carrying secondary

sodium rupturedsodium ruptured

Output Mwe Operation

USA    

EBR 1 0.2 1951-63

EBR 2 20 1963-94

Fermi 1 66 1963-72

SEFOR 20 1969-72

Fast Flux TF N/A 1980-93

UK    

Dounreay FR 15 1959-77

Prototype FR 270 1974-94

France    

Rapsodie N/A 1966-82

Phenix 250 1973-Now

Superphenix 1 1240 1985-98

Germany    

KNK 2 21 1977-91

India    

FBTR N/A 1985-Now

Japan    

Joyo N/A 1978-Now

Monju 280 1994-96, 08?

Kazakhstan    

BN350 135 1972-99

Russia    

BR 5/10 N/A 1959-71, 1973-Now

BOR 60 12 1969-Now

BOR 600 600 1980-Now Table: World Nuclear Association, June 2006

Future of Fast BreedersFuture of Fast Breeders

Next generation may use noble gases Next generation may use noble gases such as helium or argon instead of sodiumsuch as helium or argon instead of sodium

Increase in the breeding ratioIncrease in the breeding ratio Believed that a ratio of 1.3 will be possibleBelieved that a ratio of 1.3 will be possible

Smaller reactorsSmaller reactors Lower maintenance and repair costsLower maintenance and repair costs

Higher reactor temperaturesHigher reactor temperatures Can be used for thermochemical hydrogen Can be used for thermochemical hydrogen

productionproduction

ReferencesReferences

ConflictConflict. Baksiden. 16 Nov. 2007 . Baksiden. 16 Nov. 2007 <http://www.baksiden.net/atomreaktorinnforing.htm>. For image on <http://www.baksiden.net/atomreaktorinnforing.htm>. For image on slide 4. slide 4.

Fast Breeder ReactorsFast Breeder Reactors. Georgia State University. 16 Nov. . Georgia State University. 16 Nov. 2007     <http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/fasbre.2007     <http://hyperphysics.phy-astr.gsu.edu/hbase/nucene/fasbre.html>. html>.

Fast Neutron ReactorsFast Neutron Reactors. June 2006. World Nuclear Association. 16 Nov. . June 2006. World Nuclear Association. 16 Nov. 2007     <http://www.world-nuclear.org/info/inf98.html>.2007     <http://www.world-nuclear.org/info/inf98.html>.

Guidez, J, et al. Guidez, J, et al. Phenix: The Irradiation Program for Transmutation Phenix: The Irradiation Program for Transmutation ExperimentsExperiments. . Nuclear EnergyNuclear Energy          AgencyAgency. 31 Aug. 2004. 15 Nov. . 31 Aug. 2004. 15 Nov. 2007 2007 <http://www.nea.fr/html/pt/docs/iem/lasvegas04/     10_Session_IV/<http://www.nea.fr/html/pt/docs/iem/lasvegas04/     10_Session_IV/S4_01.pdf>.S4_01.pdf>.

Mixed Oxide Fuel (MOX)Mixed Oxide Fuel (MOX). Sept. 2007. Uranium Information Centre. 16 . Sept. 2007. Uranium Information Centre. 16 Nov. 2007     <http://www.uic.com.au/nip42.htm>. Nov. 2007     <http://www.uic.com.au/nip42.htm>.