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In a nuclear reactor neutrons are produced, slowed down and captured.
Furthermore, energy is produced by the fission process, and, to a lesser
extent, by radioactive decay. The most important nuclear quantities of a
nucleus present in a reactor are, therefore:
- The fission cross section
.
- The capture cross section
- The number of neutrons
emitted following the capture of a
neutron by a fissile nucleus. This quantity is basic for the possibility of
establishing a chain reaction. It can be decomposed in two factors:
Thus,
- The scattering cross sections, either elastic
or inelastic
which control the propagation of neutrons, in the medium.
- The atomic mass of the nucleus A which controls the amount of slowing
down of the neutron following an elastic scattering. After scattering at an
angle
in the center of mass, the final laboratory energy of the
neutron of initial energy E0, is given by
.
If the scattering in the
center of mass is isotropic it follows that all final energies between E0
and
are
equiprobable. Since, in this latter case, the neutron energy loss is
proportional to its initial energy, it is convenient to measure energies in
terms of lethargy
where E0 is some arbitrary
initial energy (usually the average energy of fission neutrons), and E the
actual neutron energy. We define
 |
(4.1) |
It is convenient to define the average lethargy gain per collision
 |
(4.2) |
which, expressed as function of the mass A yields
 |
(4.3) |
For large A,
.
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