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      On
Breeder Reactor
For more help contact me

Muhammad Umair Bukhari

      Engr.umair.bukhari@gmail.com

          www.bzuiam.webs.com
              03136050151
Breeder reactor
 The reactors which are designed so that
  breeding will take place is known as breeder
  reactor.
  Breeder reactors are capable of producing more
  fissile material than they consume during the
  fission chain reaction (by converting fertile U-238
  to Pu-239, or Th-232 to U-233). Thus, a uranium
  breeder reactor, once running, can be re-fueled
  with natural or even depleted uranium, and a
  thorium breeder reactor can be re-fueled with
  thorium; however, an initial stock of fissile
  material is required.
Types of breeder reactors:

    Liquid-metal cooled fast breeder-
     reactor (LMFBR)
     Gas-cooled fast breeder-reactor
     (GCFR)
     Molten Salt Breeder reactor
    Light Water Breeder Reactor
Liquid-metal cooled
fast breeder reactor
The first experimental breeder
reactor was a small plutonium-
fueled, mercury-cooled device,
operating at a power level of 25 kW,
cooled with a mixture of sodium and
potassium, was placed in operation
in 1 95 1 at the Argonne National
Laboratory in Idaho.
 This reactor, the Experimental Breeder
  Reactor-I (EBR-I), produced steam in a
  secondary loop that drove a turbine
  generator. The system produced 200 kW
  of electricity, the world's first nuclear-
  generated electricity-and it came from
  LMFBR . Since these early experiments,
  dozens of LMFBRs have been
  constructed around the world.
 Sodium has been universally chosen as
  the coolant for the modern LMFBR.
 With an atomic weight of 23, sodium does
  not appreciably slow down neutrons by
  elastic scattering, although, it does
  moderate neutrons to some extent by
  inelastic scattering.     Sodium is also an
  excellent heat transfer agent, so that an
  LMFBR can be operated at high power
  density.
 Its melting point, 980oC is much higher
  than room temperature, so the entire
  coolant system must be kept heated at all
  times to prevent the sodium from
  solidifying. This is accomplished by
  winding a spiral of insulated heating wire
  called tracing along coolant piping, valves,
  and so forth.
 Unfortunately, sodium absorbs neutrons,
  even fast neutrons, leading to the
  formation of the beta-gamma emitter
  24Na, with a half-life of 15 hours.
  Therefore, sodium that passes through
  the reactor core becomes radioactive.
  LMFBR plants operate on the steam
  cycle-that is, the heat from the reactor is
  ultimately utilized to produce steam in
  steam generators.
Gas cooled fast breeder-
reactor .

    It is a helium-cooled reactor fueled with a
   mixture of plutonium and uranium.
  The core of the GCFR is similar to that of an
   LMFBR, with mixed PUO2 and UO2 pellets in
   stainless steel pins, except that the pins are
   not as close together as they are in the
   LMFBR. Also, the pins in the GCFR have a
   roughened outer surface to enhance heat
   transfer to the passing coolant.
Molten salt breeder-
reactor (MSBR)
  This is a thermal breeder that operates on the
   233 U-thorium cycle. It is recalled that 233U is
   the only fissile isotope capable of breeding in a
   thermal reactor.
  The MSBR concept is a unique design among
   reactors in that the fuel, fertile material, and
   coolant are mixed together in one
   homogeneous fluid. This is composed of
   various fluoride salts that, at an elevated
   temperature, melt to become a clear,
   nonviscous fluid.
Advantages of MSBR:

 Because of the low vapor pressure of the
 molten salts, the MSBR operates at just a
 little above atmospheric pressure and
 thus no expensive pressure vessel i s
 required.
 High temperatures are possible with the
 molten salts, the MSBR can produce
 superheated steam at 24 MPa and
 540 C, which leads to a very high overall
 plant efficiency of about 44% .
Light water breeder
 reactor
 Even when a special effort is made in the design of
  the LWBR to reduce neutron losses, its overall
  breeding gain will be very small-too small to make
  the reactor a net producer of 233U for other
  reactors of this type.
 To see whether breeding can actually be achieved
  in a light-water reactor,the U.S. Department of
  Energy developed an LWB R core that was installed
  in the government-owned pressurized water reactor
  at Shippingport, Pennsylvania.

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Presentation on Breeder Reactor Types and Designs

  • 1. Presentation On Breeder Reactor
  • 2. For more help contact me Muhammad Umair Bukhari Engr.umair.bukhari@gmail.com www.bzuiam.webs.com 03136050151
  • 3. Breeder reactor  The reactors which are designed so that breeding will take place is known as breeder reactor. Breeder reactors are capable of producing more fissile material than they consume during the fission chain reaction (by converting fertile U-238 to Pu-239, or Th-232 to U-233). Thus, a uranium breeder reactor, once running, can be re-fueled with natural or even depleted uranium, and a thorium breeder reactor can be re-fueled with thorium; however, an initial stock of fissile material is required.
  • 4. Types of breeder reactors:  Liquid-metal cooled fast breeder- reactor (LMFBR)  Gas-cooled fast breeder-reactor (GCFR)  Molten Salt Breeder reactor  Light Water Breeder Reactor
  • 5. Liquid-metal cooled fast breeder reactor The first experimental breeder reactor was a small plutonium- fueled, mercury-cooled device, operating at a power level of 25 kW, cooled with a mixture of sodium and potassium, was placed in operation in 1 95 1 at the Argonne National Laboratory in Idaho.
  • 6.  This reactor, the Experimental Breeder Reactor-I (EBR-I), produced steam in a secondary loop that drove a turbine generator. The system produced 200 kW of electricity, the world's first nuclear- generated electricity-and it came from LMFBR . Since these early experiments, dozens of LMFBRs have been constructed around the world.
  • 7.  Sodium has been universally chosen as the coolant for the modern LMFBR.  With an atomic weight of 23, sodium does not appreciably slow down neutrons by elastic scattering, although, it does moderate neutrons to some extent by inelastic scattering. Sodium is also an excellent heat transfer agent, so that an LMFBR can be operated at high power density.
  • 8.  Its melting point, 980oC is much higher than room temperature, so the entire coolant system must be kept heated at all times to prevent the sodium from solidifying. This is accomplished by winding a spiral of insulated heating wire called tracing along coolant piping, valves, and so forth.
  • 9.  Unfortunately, sodium absorbs neutrons, even fast neutrons, leading to the formation of the beta-gamma emitter 24Na, with a half-life of 15 hours. Therefore, sodium that passes through the reactor core becomes radioactive. LMFBR plants operate on the steam cycle-that is, the heat from the reactor is ultimately utilized to produce steam in steam generators.
  • 10. Gas cooled fast breeder- reactor . It is a helium-cooled reactor fueled with a mixture of plutonium and uranium.  The core of the GCFR is similar to that of an LMFBR, with mixed PUO2 and UO2 pellets in stainless steel pins, except that the pins are not as close together as they are in the LMFBR. Also, the pins in the GCFR have a roughened outer surface to enhance heat transfer to the passing coolant.
  • 11. Molten salt breeder- reactor (MSBR)  This is a thermal breeder that operates on the 233 U-thorium cycle. It is recalled that 233U is the only fissile isotope capable of breeding in a thermal reactor.  The MSBR concept is a unique design among reactors in that the fuel, fertile material, and coolant are mixed together in one homogeneous fluid. This is composed of various fluoride salts that, at an elevated temperature, melt to become a clear, nonviscous fluid.
  • 12. Advantages of MSBR: Because of the low vapor pressure of the molten salts, the MSBR operates at just a little above atmospheric pressure and thus no expensive pressure vessel i s required. High temperatures are possible with the molten salts, the MSBR can produce superheated steam at 24 MPa and 540 C, which leads to a very high overall plant efficiency of about 44% .
  • 13. Light water breeder reactor  Even when a special effort is made in the design of the LWBR to reduce neutron losses, its overall breeding gain will be very small-too small to make the reactor a net producer of 233U for other reactors of this type.  To see whether breeding can actually be achieved in a light-water reactor,the U.S. Department of Energy developed an LWB R core that was installed in the government-owned pressurized water reactor at Shippingport, Pennsylvania.