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Overview of Fast Breeder Reactors
MA RASHID SARKAR , ALTAB HOSSAIN,
MD. GHULAM ZAKIR ,MD. SIFATUL MUKTADIR
NUCLEAR SCIENCE AND ENGINEERING (NSE)
DEPARTMENT,MIST
BUET-MEPhi workshop 4-9 November,2018
Organized by
Institute of Nuclear Power Engineering (INPE),BUET
Neutron Flux vs Neutron
Energy
Overview of Fast Breeder Reactors
Produce more fissile material than is
consumed
Technology first developed in the 1950’s
Utilize uranium 60 times as efficienctly as
PWRs
Cooled by liquid metal
Fast Breeder Reactors vs. Pressurized Water Reactors
FBR
◦ Fuel is enriched to 15-20%
◦ Moderator: none
◦ Heat transfer by liquid metal or
metal alloys
◦ Typically sodium
◦ Reactor under low pressure
◦ ~1.2 fissile atoms produced per
fission
PWR
◦ Fuel is enriched to 3-5%
◦ Moderator: water
◦ Heat transfer by water
◦ Reactor under high pressure
◦ Fissile material is only consumed
Breeding Fuel
Theory
◦ Each fission produces on average
2.4 neutrons
◦ Fissile material: U-235, Pu-239 or Pu-241
◦ Critical reaction
◦ One neutron per fission causes another
fission
◦ 1.4 neutrons are left over to enrich
depleted fuel
Practice
◦ Typical FBR produces about 1.2
fissile atoms per consumed fissile
atom
◦ Can produce enough fissile
material in 10 years to replace
spent fuel and enough to power
another reactor for 10 years
FBR Design
1) Highly enriched uranium or
plutonium
2) Control rods (same material
as core)
3) Depleted uranium
4) Heat is transferred from
primary to secondary
sodium
5) Heat is transferred from
secondary sodium to water
Figure: Baksiden, modified by Martin Metzner
Nuclear Fuel
Initially FBRs were designed to use pure uranium
oxide fuel
Eventually switched to MOX
Mixed oxide fuel (MOX):
Mixture of UO2 and PuO2
Already an existing source of fissile plutonium
Nuclear warheads
Highly enriched, former USSR and USA currently dismantling
arsenals
Depleted PWR fuel
Low enrichment caused by the fusion of U-238 and a neutron
Must be processed before it can be used
Liquid Metal Coolant
Typical metal used is sodium
Some reactors use lead, lead-bismuth alloy, or sodium
fluoride salt
Advantages of sodium
Low melting temperature (98°C)
High boiling temperature (892°C)
High heat capacity
System can run at low pressure
Risks of sodium
Burns when it comes in contact with air or water
Poisonous fumes
FBRs Today
 Only six active today
 Half of these are in Russia
 Average lifespan of reactors is only
about 20 years
 Many shut down prematurely
 Superphenix (France) and KNK 2
(Germany) were never operational
 Plagued by political controversy
 Only one notable accident
 Monju (Japan) in 1995
 A pipe carrying secondary sodium
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 Breeders
Next generation may use noble gases such as helium or argon instead of
sodium
Increase in the breeding ratio
◦ Believed that a ratio of 1.3 will be possible
Smaller reactors
◦ Lower maintenance and repair costs
Higher reactor temperatures
◦ Can be used for thermochemical hydrogen production

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Overview of Fast Breeder Reactors

  • 1. Overview of Fast Breeder Reactors MA RASHID SARKAR , ALTAB HOSSAIN, MD. GHULAM ZAKIR ,MD. SIFATUL MUKTADIR NUCLEAR SCIENCE AND ENGINEERING (NSE) DEPARTMENT,MIST BUET-MEPhi workshop 4-9 November,2018 Organized by Institute of Nuclear Power Engineering (INPE),BUET
  • 2.
  • 3. Neutron Flux vs Neutron Energy
  • 4. Overview of Fast Breeder Reactors Produce more fissile material than is consumed Technology first developed in the 1950’s Utilize uranium 60 times as efficienctly as PWRs Cooled by liquid metal
  • 5. Fast Breeder Reactors vs. Pressurized Water Reactors FBR ◦ Fuel is enriched to 15-20% ◦ Moderator: none ◦ Heat transfer by liquid metal or metal alloys ◦ Typically sodium ◦ Reactor under low pressure ◦ ~1.2 fissile atoms produced per fission PWR ◦ Fuel is enriched to 3-5% ◦ Moderator: water ◦ Heat transfer by water ◦ Reactor under high pressure ◦ Fissile material is only consumed
  • 6. Breeding Fuel Theory ◦ Each fission produces on average 2.4 neutrons ◦ Fissile material: U-235, Pu-239 or Pu-241 ◦ Critical reaction ◦ One neutron per fission causes another fission ◦ 1.4 neutrons are left over to enrich depleted fuel Practice ◦ Typical FBR produces about 1.2 fissile atoms per consumed fissile atom ◦ Can produce enough fissile material in 10 years to replace spent fuel and enough to power another reactor for 10 years
  • 7. FBR Design 1) Highly enriched uranium or plutonium 2) Control rods (same material as core) 3) Depleted uranium 4) Heat is transferred from primary to secondary sodium 5) Heat is transferred from secondary sodium to water Figure: Baksiden, modified by Martin Metzner
  • 8. Nuclear Fuel Initially FBRs were designed to use pure uranium oxide fuel Eventually switched to MOX Mixed oxide fuel (MOX): Mixture of UO2 and PuO2 Already an existing source of fissile plutonium Nuclear warheads Highly enriched, former USSR and USA currently dismantling arsenals Depleted PWR fuel Low enrichment caused by the fusion of U-238 and a neutron Must be processed before it can be used
  • 9. Liquid Metal Coolant Typical metal used is sodium Some reactors use lead, lead-bismuth alloy, or sodium fluoride salt Advantages of sodium Low melting temperature (98°C) High boiling temperature (892°C) High heat capacity System can run at low pressure Risks of sodium Burns when it comes in contact with air or water Poisonous fumes
  • 10. FBRs Today  Only six active today  Half of these are in Russia  Average lifespan of reactors is only about 20 years  Many shut down prematurely  Superphenix (France) and KNK 2 (Germany) were never operational  Plagued by political controversy  Only one notable accident  Monju (Japan) in 1995  A pipe carrying secondary sodium 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
  • 11. Future of Fast Breeders Next generation may use noble gases such as helium or argon instead of sodium Increase in the breeding ratio ◦ Believed that a ratio of 1.3 will be possible Smaller reactors ◦ Lower maintenance and repair costs Higher reactor temperatures ◦ Can be used for thermochemical hydrogen production