.. _ch4nom:

Nomenclature
================================================================================

.. list-table::
	:header-rows: 1
	:align: center
	:widths: auto

	* - Symbol
	  - Description
	  - Units
	* -    :math:`A`
	  - Coefficient in EBR-II bowing reactivity.
	  - $
	* -    :math:`A_{\text{cr}}`
	  - Control rod driveline heat transfer area.
	  - m\ :sup:`2`
	* -    :math:`A_{\text{e}}`
	  - Nominal cross-sectional area of cladding.
	  - m\ :sup:`2`
	* -    :math:`A_{\text{f}}`
	  - Nominal cross-sectional area of fuel.
	  - m\ :sup:`2`
	* -    :math:`a`
	  - Above-core load pad elevation.
	  - m
	* -    :math:`a_{\text{cr}}`
	  - Coefficient in control rod driveline reactivity feedback.
	  - $/m
	* -    :math:`B`
	  - Coefficient in EBR-II bowing reactivity.
	  - $
	* -    :math:`b_{\text{cr}}`
	  - Coefficient in control rod driveline reactivity feedback.
	  - $/m\ :sup:`2`
	* -    :math:`C_{\text{cr}}`
	  - Control rod driveline specific heat.
	  - J/kg-K
	* -    :math:`C_{\text{i}}`
	  - Delayed neutron precursor group :math:`i` population.
	  -
	* -    :math:`C_{\text{rc}}`
	  - Coefficient in simple radial core expansion reactivity feedback.
	  - $/K
	* -    :math:`D`
	  - Hex can flat-to-flat dimension.
	  - m
	* -    :math:`D_{\text{z}}`
	  - Nominal axial node height in simple axial expansion reactivity feedback model.
	  - m
	* -    :math:`E`
	  - Modulus of elasticity.
	  - N/m\ :sup:`2`
	* -    :math:`F_{\text{cr}}`
	  - Temperature multiplier in EBR-II control rod bank expansion model.
	  -
	* -    :math:`F_{\text{LowBU}}`
	  - Fraction of fuel elements with burnup less than 2.9% in EBR-II.
	  -
	* -    :math:`f_{\text{e}}`
	  - Cladding mesh height expansion factor.
	  -
	* -    :math:`f_{\text{f}}`
	  - Fuel mesh height expansion factor.
	  -
	* -    :math:`f_{\text{i}}`
	  - Channel flag in simple radial expansion reactivity model.
	  -
	* -    :math:`H`
	  - Fuel height in EBR-II.
	  - m
	* -    :math:`h_{\text{cr}}`
	  - Coolant to control rod driveline heat transfer coefficient.
	  - W/m\ :sup:`2`-k
	* -    :math:`H_{\text{n}}`
	  - Normalized decay heat energy fraction for group :math:`n`.
	  -
	* -    :math:`I`
	  - Moment of inertia of beam cross-sectional area.
	  - m\ :sup:`4`
	* -    :math:`k`
	  - Reactor effective multiplication constant.
	  -
	* -    :math:`\delta k`
	  - Reactivity, or change in the effective reactor multiplication constant.
	  -
	* -    :math:`\delta k_{\text{cl}}`
	  - Cladding relocation reactivity.
	  -
	* -    :math:`\delta k_{\text{cr}}`
	  - Control rod drive expansion reactivity.
	  -
	* -    :math:`\delta k_{\text{cs}}`
	  - Control system reactivity.
	  -
	* -    :math:`\delta k_{\text{D}}`
	  - Fuel Doppler reactivity.
	  -
	* -    :math:`\delta k_{\text{d}}`
	  - Fuel and cladding axial expansion reactivity.
	  -
	* -    :math:`\delta k_{\text{fu}}`
	  - Fuel relocation reactivity.
	  -
	* -    :math:`\delta k_{\text{Na}}`
	  - Coolant density or voiding reactivity.
	  -
	* -    :math:`\delta k_{\text{p}}`
	  - User-programmed reactivity.
	  -
	* -    :math:`\delta k_{\text{re}}`
	  - Core radial expansion reactivity.
	  -
	* -    :math:`L`
	  - Elevation of top load pad.
	  - m
	* -    :math:`L_{\text{cr}}`
	  - Control rod driveline length.
	  - m
	* -    :math:`L_{\text{k}}`
	  - Reactor vessel wall length represented by compressible volume :math:`k` or element :math:`k`.
	  - m
	* -    :math:`M`
	  - Bending moment.
	  - N-m
	* -    :math:`M_{\text{cr}}`
	  - Control rod driveline mass.
	  - kg
	* -    :math:`M_{\text{GR}}`
	  - Applied moment at grid plate.
	  - N-m
	* -    :math:`M_{1}`
	  - Thermally induced bending moment in the core region.
	  - N-m
	* -    :math:`M_{2}`
	  - Thermally induced bending moment above the core region.
	  - N-m
	* -    :math:`m_{\text{ij}}`
	  - Fuel or cladding mass at node :math:`j` in channel :math:`i` in fuel and cladding relocation reactivity.
	  - kg
	* -    :math:`N`
	  - Fuel, sodium, or steel atom density in EBR-II reactivity model.
	  - atm/m\ :sup:`3`
	* -    :math:`N_{\text{c}}`
	  - Number of channels.
	  -
	* -    :math:`N_{\text{s}}`
	  - Number of subassemblies per channel.
	  -
	* -    :math:`P`
	  - Radial force at the above core load pad.
	  - N
	* -    :math:`P_{\text{t}}^{k}`
	  - Normalized power in interval :math:`k` of irradiation history for decay heat precursor initial condition.
	  -
	* -    :math:`Q`
	  - Space and time dependent nodal power.
	  - W
	* -    :math:`Q_{\text{t}}`
	  - Total recoverable energy per fission
	  - MeV
	* -    :math:`R_{\text{e}}`
	  - Cladding nodal reactivity worth in simple axial expansion reactivity model.
	  - kg\ :sup:`-1`
	* -    :math:`R_{\text{f}}`
	  - Fuel nodal reactivity worth in simple axial expansion reactivity model.
	  - kg\ :sup:`-1`
	* -    :math:`R_{\text{i}}`
	  - Radial fuel reactivity worth shape factor in EBR-II reactivity model.
	  -
	* -    :math:`R_{1}`
	  - Minimum core radius at above-core load pad in detailed radial expansion model.
	  - m
	* -    :math:`R_{2}`
	  - Minimum core radius at top load pad in detailed radial expansion model.
	  - m
	* -    :math:`R_{3}`
	  - Maximum core radius at restraint ring in detailed radial expansion.
	  - m
	* -    :math:`\overrightarrow{r}`
	  - Reactor spatial position vector.
	  -
	* -    :math:`S`
	  - Space-dependent steady-state nodal power.
	  - W
	* -    :math:`S_{\text{GR}}`
	  - Subassembly slope with respect to vertical at the grid plate.
	  - m/m
	* -    :math:`S_{\text{GRMAX}}`
	  - Maximum subassembly slope with respect to vertical at the grid plate.
	  - m/m
	* -    :math:`T`
	  - Temperature.
	  - K
	* -    :math:`\overline{T}`
	  - Average temperature.
	  - K
	* -    :math:`\Delta T`
	  - Hexcan flat-to-flat temperature difference.
	  - K
	* -    :math:`T_{\text{by}}`
	  - Bypass region temperature.
	  - K
	* -    :math:`T_{\text{ch}}`
	  - Reflector steel temperature.
	  - K
	* -    :math:`T_{\text{cr}}`
	  - Control rod driveline temperature.
	  - K
	* -    :math:`T_{\text{cv}1}`
	  - Inlet plenum coolant temperature.
	  - K
	* -    :math:`T_{\text{cv}2}`
	  - Outlet plenum coolant temperature.
	  - K
	* -    :math:`T_{\text{e}}`
	  - Cladding temperature.
	  - K
	* -    :math:`T_{\text{f}}`
	  - Fuel temperature.
	  - K
	* -    :math:`{\overline{T}}_{\text{f}}`
	  - Average fuel temperature.
	  - K
	* -    :math:`\Delta T_{f}`
	  - Fuel temperature change.
	  - K
	* -    :math:`\Delta{\overline{T}}_{\text{favg}}`
	  - Average fuel temperature change.
	  - K
	* -    :math:`{\overline{T}}_{\text{floc}}`
	  - Average fuel temperature for a channel.
	  - K
	* -    :math:`T_{\text{i}}`
	  - Plenum coolant temperature.
	  - K
	* -    :math:`T_{\text{in}}`
	  - Coolant inlet temperature.
	  - K
	* -    :math:`\Delta T_{\text{in}}`
	  - Coolant inlet temperature change.
	  - K
	* -    :math:`T_{\text{j}}`
	  - Reflector coolant temperature.
	  - K
	* -    :math:`{\overline{T}}_{\text{k}}`
	  - Average vessel wall temperature in :math:`k`-th compressible volume or element.
	  - K
	* -    :math:`{\overline{T}}_{\text{lr}}`
	  - Average coolant temperature in lower reflector.
	  - K
	* -    :math:`T_{\text{mm}}`
	  - Mixed mean coolant core outlet temperature.
	  - K
	* -    :math:`{\overline{T}}_{\text{Na}}`
	  - Average coolant temperature.
	  - K
	* -    :math:`{\overline{T}}_{\text{rr}}`
	  - Average radial reflector coolant temperature.
	  - K
	* -    :math:`T_{\text{SLP}}`
	  - Space and time dependent structure temperature.
	  - K
	* -    :math:`{\overline{T}}_{\text{SLP}}`
	  - Space-average, time dependent structure temperature.
	  - K
	* -    :math:`{\Delta\overline{T}}_{\text{SLP}}`
	  - Change in space-averaged structure temperature.
	  - K
	* -    :math:`\Delta T_{\text{ss}}`
	  - Cladding temperature change.
	  - K
	* -    :math:`{\overline{T}}_{\text{ss}}`
	  - Average cladding temperature.
	  - K
	* -    :math:`T_{\text{ui}}`
	  - Coolant temperature in the upper internal structure region.
	  - K
	* -    :math:`{\overline{T}}_{\text{ur}}`
	  - Average coolant temperature in the upper reflector.
	  - K
	* -    :math:`t`
	  - Time.
	  - s
	* -    :math:`\Delta t`
	  - Change in time.
	  - s
	* -    :math:`V_{\text{by}}`
	  - Bypass region volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{c}}h`
	  - Channel steel volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{cv}1}`
	  - Inlet plenum volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{cv}2}`
	  - Outlet plenum volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{f}}`
	  - Fuel volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{GR}}`
	  - Radial reaction at the grid plate.
	  -
	* -    :math:`V_{\text{i}}`
	  - Plenum coolant volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{i}}`
	  - Channel volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{j}}`
	  - Reflector coolant volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{k}}`
	  - Nodal volume at :math:`k` in channel.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{Na}}`
	  - Sodium volume in fuel/cladding gap.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{ss}}`
	  - Cladding volume.
	  - m\ :sup:`3`
	* -    :math:`V_{\text{ui}}`
	  - Coolant volume in upper internal structure.
	  - m\ :sup:`3`
	* -    :math:`w_{\text{c}}`
	  - Core outlet flow rate.
	  - kg/s
	* -    :math:`w_{\text{k}}`
	  - Core volume weighting for decay heat curve :math:`k`.
	  -
	* -    :math:`\text{XAC}`
	  - Distance from subassembly nozzle support to above core load pad.
	  - m
	* -    :math:`\text{XMC}`
	  - Distance from subassembly nozzle support to core midplane.
	  - m
	* -    :math:`x`
	  - Axial elevation in detailed radial core expansion model.
	  - m
	* -    :math:`x_{1}`
	  - Elevation of lower axial blanket/lower reflector interface.
	  - m
	* -    :math:`x_{\text{i}}`
	  - Fraction of total fission power from isotope :math:`i`.
	  -
	* -    :math:`Y`
	  - Fraction of full power temperature rise.
	  -
	* -    :math:`Y_{\text{e}}`
	  - Cladding Young's modulus.
	  -
	* -    :math:`Y_{\text{f}}`
	  - Fuel Young's modulus.
	  -
	* -    :math:`Y_{\text{ss}}`
	  - Cladding Young's modulus.
	  -
	* -    :math:`y`
	  - Radial displacement with respect to the core radius at the grid plate.
	  - m
	* -    :math:`Z_{\text{k}}`
	  - Axial fuel reactivity worth shape.
	  -
	* -    :math:`\Delta z_{\text{cr}}`
	  - Control rod driveline expansion.
	  - m
	* -    :math:`z_{0}`
	  - Unexpanded axial mesh elevation.
	  - m
	* -    :math:`\Delta z_{\text{n}}`
	  - Net control rod movement.
	  - m
	* -    :math:`z_{\text{ne}}`
	  - Expanded cladding mesh elevation.
	  - m
	* -    :math:`z_{\text{nf}}`
	  - Expanded fuel mesh elevation.
	  - m
	* -    :math:`\Delta z_{\text{v}}`
	  - Reactor vessel expansion.
	  - m
	* -    :math:`\alpha`
	  - Subassembly hex can thermal expansion coefficient.
	  - 1/K
	* -    :math:`\alpha_{\text{cr}}`
	  - Control rod driveline thermal expansion coefficients.
	  - 1/K
	* -    :math:`\alpha_{\text{D}}`
	  - Local fuel Doppler coefficient.
	  -
	* -    :math:`\alpha_{\text{e}}`
	  - Cladding thermal expansion coefficient.
	  - 1/K
	* -    :math:`\alpha_{\text{f}}`
	  - Fuel thermal expansion coefficient.
	  - 1/K
	* -    :math:`\alpha_{\text{jI}}`
	  - Average coolant void fraction in axial node :math:`j` of channel :math:`I`.
	  -
	* -    :math:`\alpha_{\text{k}}`
	  - Reactor vessel thermal expansion coefficient.
	  - 1/K
	* -    :math:`\alpha_{\text{Lf}}`
	  - Fuel thermal expansion coefficient.
	  - 1/K
	* -    :math:`\alpha_{\text{Lss}}`
	  - Cladding thermal expansion coefficient.
	  - 1/K
	* -    :math:`\alpha_{\text{VNa}}`
	  - Sodium volumetric thermal expansion coefficient.
	  - 1/K
	* -    :math:`\alpha_{\text{n}}`
	  - Contribution of group :math:`n` to immediate decay heat from a single fission event
	  - MeV
	* -    :math:`\beta`
	  - Total effective delayed-neutron fraction
	  -
	* -    :math:`\beta_{\text{n}}`
	  - Effective decay-heat power fraction for group :math:`n`.
	  -
	* -    :math:`\beta_{\text{i}}`
	  - Effective delayed-neutron precursor group :math:`i` fraction.
	  -
	* -    :math:`\delta_{\text{e}}`
	  - Cladding axial expansion.
	  - m
	* -    :math:`\delta_{\text{f}}`
	  - Fuel axial expansion.
	  - m
	* -    :math:`\epsilon_{\text{d}}`
	  - Sodium density multiplier.
	  -	 	  
	* -    :math:`\epsilon_{\text{e}}`
	  - Cladding fractional thermal expansion.
	  -
	* -    :math:`\epsilon_{\text{ex}}`
	  - Effective axial expansion multiplier.
	  -
	* -    :math:`\epsilon_{\text{f}}`
	  - Fuel fractional thermal expansion.
	  -
	* -    :math:`\zeta`
	  - EBR-II reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{bw}}`
	  - EBR-II bowing reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{c}}`
	  - EBR-II coolant reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{cr}}`
	  - EBR-II control rod driveline reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{fa}}`
	  - EBR-II axial fuel expansion reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{fr}}`
	  - EBR-II radial fuel expansion reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{lr}}`
	  - EBR-II lower reflector reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{rr}}`
	  - EBR-II radial reflector reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{ssa}}`
	  - EBR-II axial cladding expansion reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{ssr}}`
	  - EBR-II radial cladding expansion reactivity parameter.
	  - $
	* -    :math:`\zeta_{\text{ur}}`
	  - EBR-II upper reflector reactivity parameter.
	  - $
	* -    :math:`\Lambda`
	  - Prompt neutron lifetime.
	  - s
	* -    :math:`\lambda_{\text{n}}`
	  - Decay heat group effective decay constant for group :math:`n`.
	  - 1/s
	* -    :math:`\lambda_{\text{i}}`
	  - Delayed neutron precursor group :math:`i` decay constant.
	  - 1/s
	* -    :math:`\rho_{\text{c}}`
	  - Local coolant void reactivity worth.
	  - g\ :sup:`-1`
	* -    :math:`\Delta\rho_{\text{e}}`
	  - Cladding axial expansion reactivity.
	  -
	* -    :math:`\Delta\rho_{\text{f}}`
	  - Fuel axial expansion reactivity.
	  -
	* -    :math:`\rho_{\text{u}}`
	  - Sodium density in outlet plenum.
	  - kg/m\ :sup:`3`
	* -    :math:`\phi`
	  - Normalized fission power amplitude.
	  -
	* -    :math:`\phi_{1}`
	  - First order coefficient in normalized fission power amplitude expansion.
	  - s\ :sup:`-1`
	* -    :math:`\phi_{2}`
	  - Second order coefficient in normalized fission power amplitude expansion.
	  - s\ :sup:`-2`
	* -    :math:`\psi_{\text{f}}`
	  - Normalized fission power.
	  -
	* -    :math:`\psi_{\text{h}}`
	  - Normalized decay heat power.
	  -
	* -    :math:`\psi_{\text{t}}`
	  - Normalized total power.
	  -