Nuclear Physics (Symbols) ========================= Symbols related to electrodynamics. .. py:currentmodule:: symplyphysics.symbols.nuclear .. py:data:: geometric_buckling **Geometric buckling** is a measure of neutron leakage in a nuclear reactor. **Links:** #. `Wikipedia `__. Symbol: :code:`B_g^2` Latex: :math:`B_\text{g}^2` Dimension: :code:`1/area` .. py:data:: 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:** #. `Wikipedia `__. Symbol: :code:`k` Latex: :math:`k` Dimension: :code:`dimensionless` .. py:data:: infinite_multiplication_factor The **infinite multiplication factor** is the :attr:`~multiplication_factor` when the medium is infinite so that neutrons cannot leak out of the system. **Links:** #. `Wikipedia `__. Symbol: :code:`k_inf` Latex: :math:`k_{\infty}` Dimension: :code:`dimensionless` .. py:data:: 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:** #. `Wikipedia `__. Symbol: :code:`k_eff` Latex: :math:`k_\text{eff}` Dimension: :code:`dimensionless` .. py:data:: 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:** #. `NuclearPower `__. Symbol: :code:`L^2` Latex: :math:`L^{2}` Dimension: :code:`area` .. py:data:: neutron_flux **Neutron flux** is a scalar quantity defined as the total distance traveled by all free neutrons per unit time and volume. **Links:** #. `Wikipedia `__. Symbol: :code:`Phi` Latex: :math:`\Phi` Dimension: :code:`1/(area*time)` .. py:data:: material_buckling **Material buckling** is a measure of the difference between neutron production and neutron absorption in a nuclear reactor. **Links:** #. `Wikipedia `__. Symbol: :code:`B_m^2` Latex: :math:`B_\text{m}^2` Dimension: :code:`1/area` .. py:data:: 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: :code:`P_FNL` Latex: :math:`P_\text{FNL}` Dimension: :code:`dimensionless` .. py:data:: 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: :code:`P_TNL` Latex: :math:`P_\text{TNL}` Dimension: :code:`dimensionless` .. py:data:: 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:** #. `Wikipedia, see row 4 of the table `__. Symbol: :code:`epsilon` Latex: :math:`\varepsilon` Dimension: :code:`dimensionless` .. py:data:: 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:** #. `Wikipedia `__. Symbol: :code:`p` Latex: :math:`p` Dimension: :code:`dimensionless` .. py:data:: fast_absorption_fission_probability **Fast absorption fission probability** is the probability that a fast neutron absorption in fuel causes fission. **Links:** #. `Wikipedia, see list under the table `__. Symbol: :code:`P_FAF` Latex: :math:`P_\text{FAF}` Dimension: :code:`dimensionless` .. py:data:: thermal_absorption_fission_probability **Thermal absorption fission probability** is the probability that a thermal neutron absorption in fuel causes fission. **Links:** #. `Wikipedia, see list under the table `__. Symbol: :code:`P_TAF` Latex: :math:`P_\text{TAF}` Dimension: :code:`dimensionless` .. py:data:: 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:** #. `Wikipedia, second row of the table `__. Symbol: :code:`f` Latex: :math:`f` Dimension: :code:`dimensionless` .. py:data:: fast_utilization **Fast utilization** is the probability that a fast neutron is absorbed in fuel. **Links:** #. `Wikipedia, see list under the table `__. Symbol: :code:`u_f` Latex: :math:`u_\text{f}` Dimension: :code:`dimensionless` .. py:data:: 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 :attr:`~symplyphysics.symbols.nuclear.neutron_diffusion_area`. Symbol: :code:`tau` Latex: :math:`\tau` Dimension: :code:`area` .. py:data:: 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:** #. `Wikipedia, first line in table `__. Symbol: :code:`eta` Latex: :math:`\eta` Dimension: :code:`dimensionless` .. py:data:: half_life **Half-life** is the time required for a quantity to reduce to half of its initial value. **Links:** #. `Wikipedia `__. Symbol: :code:`t_1/2` Latex: :math:`t_{1/2}` Dimension: :code:`time` .. py:data:: 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:** #. `ScienceDirect `__. Symbol: :code:`Sigma` Latex: :math:`\Sigma` Dimension: :code:`1/length` .. py:data:: 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:** #. `NuclearPower `__. Symbol: :code:`D` Latex: :math:`D` Dimension: :code:`length` .. py:data:: 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: :code:`M^2` Latex: :math:`M^{2}` Dimension: :code:`area` .. py:data:: 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:** #. `Wikipedia, first row in table `__. Symbol: :code:`eta` Latex: :math:`\eta` Dimension: :code:`dimensionless`