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Fast breeder reactors
In PWRs and BWRs, a vast majority of the fission reactions occur in U-235, which makes up
for only 0.7 % of natural uranium and during fuel fabrication for these reactors it is enriched
to a few percent. Accordingly, in the already mentioned reactor types (sometimes referred to
as thermal reactors) U-238 is hardly applied as fissionable material. However, upon capturing
a neutron, the nucleus of U-328 can transform into Pu-239 (via radioactive decay), which is a
fissile material. For Pu-239, fission can also be induced using fast neutrons. The fast breeder
reactors use both processes. The largest nuclear power plant with a fast breeder reactor is the
Superphenix in France, which started operation in 1986. Its thermal power is 3000 MW, while
the electrical power is 1180 MW (this corresponds to an efficiency of 39%). Fast breeder
reactors have a share of less than 1% of the total power of the world's NPPs.
The core of a fast breeder reactor consists of two parts. The
fuel rods, which contain a mixture of uranium dioxide and
plutonium dioxide, are found in the inner part. Here fission
reactions dominate, while in the outer part the predominant
process is conversion of U-238 to Pu-239. This part contains
depleted uranium (i.e. uranium in which the U-235 content is
even lower than the natural 0.7%). In such a reactor one can
achieve a situation where more fissile plutonium nuclei are
produced in a unit time than the number of fissile nuclei which
undergo fission (hence the name "breeder"). On the other hand,
neutrons are not thermalized, since fast neutrons are needed for
the above described processes.
In the French Phénix breeder reactor it was determined that for 100 fission reactions there are
115 newly produced fissile nuclei. Correspondingly, more fissile material is produced than
used, and this can later be used in other thermal (such as light water moderated) or breeder
reactors.
Obviously, in a fast reactor there must not be any moderator, which implies that water is not
at all suitable as coolant. Instead some liquid metal, usually sodium is applied. In the
Superphénix, sodium enters the core at 395o
C and exits at 545o
C. Since the boiling point of
sodium is very high even at comparatively low pressures (at 10 bars about 900o
C), there is no
need to maintain a high pressure in the primary circuit and thus the construction and
manufacturing of the reactor vessel is easier.
1 Fuel (fissile material) 9 Cover 17 Condenser
2 Fuel (breeder material) 10 Na/Na heat exchanger 18 Cooling water
3 Control rods 11 Secondary Na 19 Cooling water pump
4 Primary Na pump 12 Secondary Na pump 20 High pressure turbine
5 Primary Na coolant 13 Steam generator 21 Low pressure turbine
6 Reactor vessel 14 Fresh steam 22 Generator
7 Protective vessel 15 Feedwater pre-heater 23 Reactor building
8 Reactor cover 16 Feedwater pump
The heat of primary sodium is transferred to the secondary sodium in an intermediate heat
exchanger, while the third heat exchanger is the steam generator. Application of three loops is
necessitated by safety considerations (liquid sodium is very dangerous: the primary sodium is
highly radioactive because of neutrons activation, which results in Na-24; the second sodium
loop prevents radioactive sodium from accidental contact with water.)

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251153278 fast-breeder-reactors

  • 1. Fast breeder reactors In PWRs and BWRs, a vast majority of the fission reactions occur in U-235, which makes up for only 0.7 % of natural uranium and during fuel fabrication for these reactors it is enriched to a few percent. Accordingly, in the already mentioned reactor types (sometimes referred to as thermal reactors) U-238 is hardly applied as fissionable material. However, upon capturing a neutron, the nucleus of U-328 can transform into Pu-239 (via radioactive decay), which is a fissile material. For Pu-239, fission can also be induced using fast neutrons. The fast breeder reactors use both processes. The largest nuclear power plant with a fast breeder reactor is the Superphenix in France, which started operation in 1986. Its thermal power is 3000 MW, while the electrical power is 1180 MW (this corresponds to an efficiency of 39%). Fast breeder reactors have a share of less than 1% of the total power of the world's NPPs. The core of a fast breeder reactor consists of two parts. The fuel rods, which contain a mixture of uranium dioxide and plutonium dioxide, are found in the inner part. Here fission reactions dominate, while in the outer part the predominant process is conversion of U-238 to Pu-239. This part contains depleted uranium (i.e. uranium in which the U-235 content is even lower than the natural 0.7%). In such a reactor one can achieve a situation where more fissile plutonium nuclei are produced in a unit time than the number of fissile nuclei which undergo fission (hence the name "breeder"). On the other hand, neutrons are not thermalized, since fast neutrons are needed for the above described processes. In the French Phénix breeder reactor it was determined that for 100 fission reactions there are 115 newly produced fissile nuclei. Correspondingly, more fissile material is produced than used, and this can later be used in other thermal (such as light water moderated) or breeder reactors. Obviously, in a fast reactor there must not be any moderator, which implies that water is not at all suitable as coolant. Instead some liquid metal, usually sodium is applied. In the Superphénix, sodium enters the core at 395o C and exits at 545o C. Since the boiling point of sodium is very high even at comparatively low pressures (at 10 bars about 900o C), there is no need to maintain a high pressure in the primary circuit and thus the construction and manufacturing of the reactor vessel is easier.
  • 2. 1 Fuel (fissile material) 9 Cover 17 Condenser 2 Fuel (breeder material) 10 Na/Na heat exchanger 18 Cooling water 3 Control rods 11 Secondary Na 19 Cooling water pump 4 Primary Na pump 12 Secondary Na pump 20 High pressure turbine 5 Primary Na coolant 13 Steam generator 21 Low pressure turbine 6 Reactor vessel 14 Fresh steam 22 Generator 7 Protective vessel 15 Feedwater pre-heater 23 Reactor building 8 Reactor cover 16 Feedwater pump The heat of primary sodium is transferred to the secondary sodium in an intermediate heat exchanger, while the third heat exchanger is the steam generator. Application of three loops is necessitated by safety considerations (liquid sodium is very dangerous: the primary sodium is highly radioactive because of neutrons activation, which results in Na-24; the second sodium loop prevents radioactive sodium from accidental contact with water.)