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Neutron Capture Cross Sections

The probability that a fission reaction will occur is related to the neutron capture cross section σ. There are two principle modes of interaction -

1. Elastic Scattering σs

n + AX → AX + n

The neutron scatters off the nucleus leaving the with the same number of protons and neutrons.

2. Compound nucleus formation

n + AX → A+1X*

The * denotes that the nucleus is in an excited state.

A neutron must be "captured" by the nucleus to initiate the fission. The cross section of the interaction varies with the energy of the incident neutron.

After the capture several things can then happen.

Inelastic scattering σI

A+1X* → AX* + n

followed by AX* → AX + γ

Radiative capture σc

A+1X* → A+1X + γ

Emission of light charged particle σp

A+1X* → A(X-1)* + p

Fission σf

236U* → 147La + 87Br + 2n δ

Total cross section σt = σs + σI + σc + σp + σf

Absorption cross section σa = σc + σp + σf
i.e. the neutron is removed from the flux

Each cross section will vary with the kinetic energy of the neutron

For example the natural Uranium Cross Sections differ as the neuton kinetic energy is reduced

k.e. σs (b) σf (b) σI (b) σc (b)
2 MeV
4
0.6
2.9
0.2
0.3 Mev
9
0.009
0.5
0.2
1 keV
11
0.06
0
4
40 eV (thermal)
8
4.1
0
3.7

A chain reaction is difficult because as σf increases so does σc

But for 235U a chain reaction is more easily achieved as the k.e. → 0.3 MeV because σf > σc

k.e. σs (b) σf (b) σI (b) σc (b)
2 MeV
3.5
0.3
2.3
0
0.3 Mev
7
1.3
0.7
0
1 keV
10
8
0
3
40 eV (thermal)
10
580
0
100

 

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