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A fast neutron reactor uses fast neutrons, so it does not use a moderator. Moderators may absorb a lot of neutrons in a thermal reactor, and fast fission produces a higher average number of neutrons per fission, so fast reactors have better neutron economy making a plutonium breeder reactor possible.
The BN-350 fast-neutron reactor at Aktau, Kazakhstan.It operated between 1973 and 1994. A fast-neutron reactor (FNR) or fast-spectrum reactor or simply a fast reactor is a category of nuclear reactor in which the fission chain reaction is sustained by fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors.
Fast fission or fission of some heavier actinides will produce 121m Sn at higher yields. For example, its yield from U-235 is 0.0007% per thermal fission and 0.002% per fast fission. For example, its yield from U-235 is 0.0007% per thermal fission and 0.002% per fast fission.
Thus, in any fission event of an isotope in the actinide mass range, roughly 0.9 MeV are released per nucleon of the starting element. The fission of 235 U by a slow neutron yields nearly identical energy to the fission of 238 U by a fast neutron. This energy release profile holds for thorium and the various minor actinides as well.
Fast neutrons have a small probability to cause fissions in uranium, specifically uranium-238. The fast fission factor describes the contribution of fast fissions to the effective neutron multiplication factor; The bounds of this factor are 1 and infinity, with a value of 1 describing a system for which only thermal neutrons are causing fissions.
(fast utilization) is the probability that a fast neutron is absorbed in fuel. is the probability that a fast neutron absorption in fuel causes fission. is the probability that a thermal neutron absorption in fuel causes fission.
A fast reactor directly uses fission neutrons without moderation. Fast reactors can be configured to "burn", or fission, all actinides, and given enough time, therefore drastically reduce the actinides fraction in spent nuclear fuel produced by the present world fleet of thermal neutron light water reactors, thus closing
On the other hand, a fast reactor needs no moderator to slow down the neutrons at all, taking advantage of the fast neutrons producing a greater number of neutrons per fission than slow neutrons. For this reason ordinary liquid water , being a moderator and neutron absorber , is an undesirable primary coolant for fast reactors.