Reproduction factor from macroscopic cross sections in fuel¶
Reproduction factor can be found using the macroscopic fissure and absorption cross sections in the fuel and the average number of neutrons produced per fission.
Links:
- neutrons_per_fission¶
Average number of neutrons produced per fission. See
particle_count.
- Symbol:
nu- Latex:
\(\nu\)
- Dimension:
dimensionless
- macroscopic_fission_cross_section¶
macroscopic_cross_sectionof fission in the fuel.
- Symbol:
Sigma_ff- Latex:
\(\Sigma_\text{f}^\text{f}\)
- Dimension:
1/length
- macroscopic_absorption_cross_section¶
macroscopic_cross_sectionof absorption in the fuel.
- Symbol:
Sigma_af- Latex:
\(\Sigma_\text{a}^\text{f}\)
- Dimension:
1/length
- reproduction_factor¶
Neutron
reproduction_factor.
- Symbol:
eta- Latex:
\(\eta\)
- Dimension:
dimensionless
- law¶
eta = nu * Sigma_ff / Sigma_af- Latex:
- \[\eta = \frac{\nu \Sigma_\text{f}^\text{f}}{\Sigma_\text{a}^\text{f}}\]