classification of nuclear reactors

1.On the basis of neutron energies:

Intermediate reactors:Reactors in which the

velocity of neutrons is kept between the limits of fast

and slow reactors.

Fast reactors:In these reactors

Fast fission is caused by high energy neutrons.

Slow reactors:If in a reactor fission process is maintained due to slow neutrons capture, the reactor is

known as slow reactor.

2.On the basis of Fuel state:

LIQUID FUEL GAS FUELSOLID FUEL

3.On the basis of fuel material:

a. Natural uranium with U-235 contents (occurs in nature)b. Enriched uranium with more than 0.71% of U-235 (man made)c. Pu-239,Pu-241 or Pu-239 (man made)d. U-233 (man made)

1.Water (H₂o) moderated reactors

2.Heavy water (D₂o) reactors3.Graphite moderated reactors

4.Beryllium or beryllium oxide moderated reactors

5.Hydrocarbon or hydrides moderated reactors

Pressurised Water Reactor(PWR)-It is a light water cooled and moderated reactor. It uses enriched uranium as fuel.

Boiling water reactor(BWR)-In this type of reactor, enriched uranium is used as fuel and water is used as coolant, and moderator.

CANDU(Canadian-deuterium-uranium)reactor:It uses heavy water (99.8% D₂O) as moderator and coolant as well. It

differs from light water reactor as the later uses the same water as coolant and

moderator both while in CANDU reactor moderator and coolant are kept separate.

Gas-cooled reactor:

In such type of reactor, the coolant used can be air, hydrogen, helium or carbon dioxide. The moderator used is graphite.

There are two types of gas cooled reactors:1. The gas cooled graphite moderator reactor(GCGM):uses natural

uranium fuel and graphite as moderator.2. The high temperature gas cooled reactor(HTGC):uses enriched

uranium carbide mixed with thorium carbide as fuel and graphite as moderator.

Sodium –graphite reactor(SGR) is one of the typical liquid metal reactor in which sodium works as coolant and graphite works as moderator.

1)Research reactors-to produce neutron for research work.

2)Power reactor- to produce heat

3)Breeder reactor- to produce fissionable material (i.e..U-238 & Th-232 to Pu-239 & U-233) besides power production.

4)Production rector- to produce isotopes.

i. Cubical

ii.Cylindrical

iii.Octagonal

iv.Spherical

v. Slab

vi.Annulus

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Book=Power Plant Engineering(R.K.RAJPUT)

References: