Neutron moderator: Difference between revisions
imported>Howard C. Berkowitz |
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:ζ = energy loss per collision | :ζ = energy loss per collision | ||
:∑<sub>s</sub> = [[scattering cross-section]] | :∑<sub>s</sub> = [[scattering cross-section]] | ||
:∑<sub>a</sub> = [[absorption cross-section]] | :∑<sub>a</sub> = [[absorption cross-section]], a nonscalar value differing for different neutron energies | ||
Other desirable properties include high density, chemical stability, and resistance to radiation damage. | Other desirable properties include high density, chemical stability, and resistance to radiation damage. | ||
Revision as of 08:50, 11 May 2010
In a nuclear reactor, a reactor moderator controls the flow of neutrons. Moderators are often in the form of control rods, which increase nuclear fission when withdrawn and decrease fission when inserted; a SCRAM is an emergency shutdown in which all rods are inserted to their maximums.
Moderators and reactor coolants have comparable properties, and, if the reactor design permits, making them of the same material increases safety.
The key figure of merit for a moderator material is the moderator ratio (MR).[1]
where
- ζ = energy loss per collision
- ∑s = scattering cross-section
- ∑a = absorption cross-section, a nonscalar value differing for different neutron energies
Other desirable properties include high density, chemical stability, and resistance to radiation damage.
Light (ordinary) water
Light water is both the most common moderator and reactor coolant in Boiling Water Reactors and Pressurized Water Reactors used for electricity generation and naval nuclear propulsion.
Heavy water
Graphite
Beryllium
References
- ↑ John Bernard, Reactor Physics, Part I, 22.05 Neutron Science and Reactor Physics, MIT Open Courseware
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