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PIME 2009

Pime 2009
15 - 17 February 2009, Edinburgh, UK

RRFM 2009

RRFM 2009
22 - 25 March 2009 in Vienna, Austria

American Nuclear Society

ANS/ENS Int. Winter Meeting
9 -13 Nov 2008, Reno, NV, USA

Nuclear for the People

Nuclear Power for the People
13-15 November 08 in Sofia, Bulgaria

CONTE 2009

CONTE 2009
8 - 11 Feb 2009, Jacksonville, FL, USA

NPIC&HMIT 2009

NPIC&HMIT 2009
5 - 9 April 2009, Knoxville, Tennessee


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Glossary

Fast breeding reactor

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Nuclear reactor with a chain reaction maintained by fast neutrons and generating more fissile material than it consumes. The reactor core is composed of 'fissile' U-235 enriched uranium or Pu-239 fuel which is surrounded by a 'breeder' blanket of natural uranium containing 'fertile' U238. This 'fertile' U-238 is converted into the fissile Pu-239 by capture of neutrons (escaping from the core) and two subsequent beta decays. The reactor core is designed to obtain a high 'breeding' ratio, practically exclusively with fast neutrons. Since the neutrons should be decelerated as little as possible, water is excluded as a coolant due to its decelerating effect. For technical reasons, sodium, which is liquid above temperatures of 97.8°C, is particularly well suited. By converting the natural uranium in the 'breeder' blanket into Pu239 which can then be recycled into fuel, the fast breeder can utilize uranium up to 60 times better than by thermal reactors such as PWRs.

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