Nuclear Physics (Symbols)¶
Symbols related to electrodynamics.
- geometric_buckling¶
Geometric buckling is a measure of neutron leakage in a nuclear reactor.
Links:
- Symbol:
B_g^2- Latex:
\(B_\text{g}^2\)
- Dimension:
1/area
- multiplication_factor¶
The multiplication factor denotes the rate of change of the neutron population in a system, and is the ratio of the neutron population in the following generation to the neutron population in the given generation.
Links:
- Symbol:
k- Latex:
\(k\)
- Dimension:
dimensionless
- infinite_multiplication_factor¶
The infinite multiplication factor is the
multiplication_factorwhen the medium is infinite so that neutrons cannot leak out of the system.Links:
- Symbol:
k_inf- Latex:
\(k_{\infty}\)
- Dimension:
dimensionless
- effective_multiplication_factor¶
The effective multiplication factor is most often defined as the ratio of the rate of neutron production to the rate of neutron loss in a nuclear system.
Links:
- Symbol:
k_eff- Latex:
\(k_\text{eff}\)
- Dimension:
dimensionless
- neutron_diffusion_area¶
Diffusion area is a quantity that appears when calculating the average distance between the neutron’s birth point as a thermal neutron and its absorption.
Links:
- Symbol:
L^2- Latex:
\(L^{2}\)
- Dimension:
area
- neutron_flux¶
Neutron flux is a scalar quantity defined as the total distance traveled by all free neutrons per unit time and volume.
Links:
- Symbol:
Phi- Latex:
\(\Phi\)
- Dimension:
1/(area*time)
- material_buckling¶
Material buckling is a measure of the difference between neutron production and neutron absorption in a nuclear reactor.
Links:
- Symbol:
B_m^2- Latex:
\(B_\text{m}^2\)
- Dimension:
1/area
- fast_non_leakage_probability¶
Fast non-leakage probability is defined as the ratio of the number of fast neutrons that do not leak from the reactor to the number of fast neutrons produced by all fissions.
- Symbol:
P_FNL- Latex:
\(P_\text{FNL}\)
- Dimension:
dimensionless
- thermal_non_leakage_probability¶
Thermal non-leakage probability is defined as the ratio of the number of thermal neutrons that do not leak from the reactor to the number of thermal neutrons produced by all fissions.
- Symbol:
P_TNL- Latex:
\(P_\text{TNL}\)
- Dimension:
dimensionless
- fast_fission_factor¶
Fast fission factor is the ratio of total number of fission neutrons to the number of fission neutrons from just thermal fissions.
Links:
- Symbol:
epsilon- Latex:
\(\varepsilon\)
- Dimension:
dimensionless
- resonance_escape_probability¶
Resonance escape probability is the probability that a neutron will slow down from fission energy to thermal energies without being captured by a nuclear resonance.
Links:
- Symbol:
p- Latex:
\(p\)
- Dimension:
dimensionless
- fast_absorption_fission_probability¶
Fast absorption fission probability is the probability that a fast neutron absorption in fuel causes fission.
Links:
- Symbol:
P_FAF- Latex:
\(P_\text{FAF}\)
- Dimension:
dimensionless
- thermal_absorption_fission_probability¶
Thermal absorption fission probability is the probability that a thermal neutron absorption in fuel causes fission.
Links:
- Symbol:
P_TAF- Latex:
\(P_\text{TAF}\)
- Dimension:
dimensionless
- thermal_utilization_factor¶
Thermal utilization factor is defined as the ratio of the number of neutrons absorbed by the fuel isotope to the number of neutrons absorbed anywhere.
Links:
- Symbol:
f- Latex:
\(f\)
- Dimension:
dimensionless
- fast_utilization¶
Fast utilization is the probability that a fast neutron is absorbed in fuel.
Links:
- Symbol:
u_f- Latex:
\(u_\text{f}\)
- Dimension:
dimensionless
- neutron_fermi_age¶
Fermi age is a measure of how far a neutron travels during moderation (e.g. in a graphite moderator), similar to the
neutron_diffusion_area.
- Symbol:
tau- Latex:
\(\tau\)
- Dimension:
area
- thermal_fission_factor¶
Thermal fission factor is defined as the ratio of the number of neutrons produced from fission to the absorption in fuel isotope.
Links:
- Symbol:
eta- Latex:
\(\eta\)
- Dimension:
dimensionless
- half_life¶
Half-life is the time required for a quantity to reduce to half of its initial value.
Links:
- Symbol:
t_1/2- Latex:
\(t_{1/2}\)
- Dimension:
time
- macroscopic_cross_section¶
The macroscopic cross section is an interaction rate per unit distance traveled by the neutron obtained by multiplying the microscopic cross section (expressed as an area) by atomic density (expressed as reciprocal volume).
Links:
- Symbol:
Sigma- Latex:
\(\Sigma\)
- Dimension:
1/length
- neutron_diffusion_coefficient¶
Diffusion coefficient is the proportionality constant between the neutron current density and the neutron current, as per the first Fick’s law of diffusion.
Links:
- Symbol:
D- Latex:
\(D\)
- Dimension:
length
- migration_area¶
Migration area, or the square of the migration length, is the measure of the distance a neutron travels while slowing down as a fast neutron and diffusing as a thermal neutron.
- Symbol:
M^2- Latex:
\(M^{2}\)
- Dimension:
area
- reproduction_factor¶
Reproduction factor is defined as the ratio of the number of neutrons produced from thermal fissions to the thermal absorption in fuel isotope.
Links:
- Symbol:
eta- Latex:
\(\eta\)
- Dimension:
dimensionless