modelRegions_3

0-D point kinetics fuel channel model with three solid media regions

Parameters

TypeNameDefaultDescription
RealnParallel1Number of identical parallel coolant channels
SI.PowerQ_nominal1e6Total nominal reactor power (fission + decay)
BooleanspecifyPowerfalse=true to specify power (i.e., no der(P) equation)
Units.NonDim[geometry.nV]SF_start_powerfill(1/geometry.nV, geometry.nV)Shape factor for the power profile, sum(SF) = 1
Kinetics › Fluid Trace Substances
SI.Area[Medium.nC]sigmasA_add_startfill(0, Medium.nC)Microscopic absorption cross-section for reactivity feedback
Parameter Change › Input: Fluid Trace Substances
SI.Area[Medium.nC]dsigmasA_addfill(0, Medium.nC)Change in microscopic absorption cross-section for reactivity feedback
Kinetics › Neutron Kinetics
SI.TimeLambda_start1e-5Prompt neutron generation time
SI.PowerQ_fission_startQ_nominal/(1 + sum(kinetics.efs_dh_start))Initial reactor fission power
SI.Power[kinetics.nC]Cs_pg_start{kinetics.betas_start[j]/(kinetics.lambdas_start[j]*Lambda_start)*Q_fission_start for j in 1:kinetics.nC}Power of the initial delayed-neutron precursor concentrations
Kinetics › Decay-Heat
Booleanuse_historyfalse=true to provide power history
SI.Power[:,2]historyfill(0, 0, 2)Power history up to simulation time=0, [t,Q]
BooleanincludeDHfalse=true if power history includes decay heat
SI.Energy[kinetics.nDH]Es_start{Q_fission_start*kinetics.efs_dh_start[j]/kinetics.lambda_dh_start[j] for j in 1:kinetics.nDH}Initial decay heat group energy
Kinetics › Fission Products
Units.ExtraPropertyExtrinsic[kinetics.nFP]mCs_fp_startfill(0, kinetics.nFP)Number of fission product atoms per group
Units.NonDim[kinetics.nFS]fissionSources_startfill(1/kinetics.nFS, kinetics.nFS)Source of fissile material fractional composition (sum=1)
Units.NonDim[kinetics.nFS,kinetics.nT]fissionTypes_startfill(1/kinetics.nT, kinetics.nFS, kinetics.nT)Fraction of fission from each fission type per fission source, sum(row) = 1
Units.NonDimnu_bar_start2.4Neutrons per fission
SI.Energyw_f_start200e6*1.6022e-19Energy released per fission
SI.MacroscopicCrossSectionSigmaF_start1Macroscopic fission cross-section of fissile material
Kinetics › Reactivity Feedback
Units.TempFeedbackCoeffalpha_fuel-2.5e-5Doppler feedback coefficient
Units.TempFeedbackCoeffalpha_coolant-20e-5Moderator feedback coefficient
SI.TemperatureTeffref_fuelFuel reference temperature
SI.TemperatureTeffref_coolantCoolant reference temperature
Fuel Element Initialization › Reference Temperatures for Start Values
SI.TemperatureT_start_1Material_1.T_defaultFuel temperature
SI.TemperatureT_start_2Material_1.T_defaultGap temperature
SI.TemperatureT_start_3Material_1.T_defaultCladding temperature
Fuel Element Initialization › Start Value: Temperature
SI.Temperature[geometry.nRs[1],geometry.nV]Ts_start_1fill(T_start_1, geometry.nRs[1], geometry.nV)Fuel temperatures
SI.Temperature[geometry.nRs[2],geometry.nV]Ts_start_2[{Ts_start_1[end, :]}; fill(T_start_2, geometry.nRs[2] - 1, geometry.nV)]Gap temperatures
SI.Temperature[geometry.nRs[3],geometry.nV]Ts_start_3[{Ts_start_2[end, :]}; fill(T_start_3, geometry.nRs[3] - 1, geometry.nV)]Cladding temperatures
Coolant Initialization › Start Value: Absolute Pressure
SI.AbsolutePressureps_startlinspace_1D(p_a_start, p_b_start, geometry.nV)Pressure
SI.AbsolutePressurep_a_startMedium.p_defaultPressure at port a
SI.AbsolutePressurep_b_startp_a_start + (if m_flow_a_start > 0 then -1e3 elseif m_flow_a_start < 0 then -1e3 else 0)Pressure at port b
Coolant Initialization › Start Value: Temperature
Booleanuse_Ts_starttrueUse T_start if true, otherwise h_start
SI.Temperature[geometry.nV]Ts_startlinspace_1D(T_a_start, T_b_start, geometry.nV)Temperature
SI.TemperatureT_a_startMedium.T_defaultTemperature at port a
SI.TemperatureT_b_startT_a_startTemperature at port b
Coolant Initialization › Start Value: Specific Enthalpy
SI.SpecificEnthalpyhs_startif not use_Ts_start then linspace_1D(h_a_start, h_b_start, geometry.nV) else {Medium.specificEnthalpy_pTX(ps_start[i], Ts_start[i], Xs_start[i, 1:Medium.nX]) for i in 1:geometry.nV}Specific enthalpy
SI.SpecificEnthalpyh_a_startMedium.specificEnthalpy_pTX(p_a_start, T_a_start, X_a_start)Specific enthalpy at port a
SI.SpecificEnthalpyh_b_startMedium.specificEnthalpy_pTX(p_b_start, T_b_start, X_b_start)Specific enthalpy at port b
Coolant Initialization › Start Value: Species Mass Fraction
SI.MassFraction[geometry.nV,Medium.nX]Xs_startlinspaceRepeat_1D(X_a_start, X_b_start, geometry.nV)Mass fraction
SI.MassFraction[Medium.nX]X_a_startMedium.X_defaultMass fraction at port a
SI.MassFraction[Medium.nX]X_b_startX_a_startMass fraction at port b
Coolant Initialization › Start Value: Trace Substances Mass Fraction
SI.MassFraction[geometry.nV,Medium.nC]Cs_startlinspaceRepeat_1D(C_a_start, C_b_start, geometry.nV)Mass fraction
SI.MassFraction[Medium.nC]C_a_startfill(0, Medium.nC)Mass fraction at port a
SI.MassFraction[Medium.nC]C_b_startC_a_startMass fraction at port b
Coolant Initialization › Start Value: Mass Flow Rate
SI.MassFlowRatem_flows_startlinspace(m_flow_a_start, -m_flow_b_start, geometry.nV + 1)Mass flow rates
SI.MassFlowRatem_flow_a_start0Mass flow rate at port_a
SI.MassFlowRatem_flow_b_start-m_flow_a_startMass flow rate at port_b
Advanced › Dynamics
DynamicsenergyDynamicsDynamics.DynamicFreeInitialFormulation of energy balances {coolant}
DynamicsenergyDynamics_fuelDynamics.DynamicFreeInitialFormulation of energy balances {fuel}
DynamicsmassDynamicsenergyDynamicsFormulation of mass balances {coolant}
DynamicstraceDynamicsmassDynamicsFormulation of trace substance balances {coolant}
DynamicsmomentumDynamicsDynamics.SteadyStateFormulation of momentum balances {coolant}
Advanced › Dynamics: Kinetics
DynamicskineticDynamicsenergyDynamics_fuelFormulation of nuclear kinetics balances
DynamicsprecursorDynamicskineticDynamicsFormulation of neutron precursor balances
DynamicsdecayheatDynamicskineticDynamicsFormulation of decay-heat balances
DynamicsfissionProductDynamicskineticDynamicsFormulation of fission product balances
Advanced › Coolant
BooleanallowFlowReversaltrue= true to allow flow reversal, false restricts to design direction (port_a -> port_b)
BooleanexposeState_atrue=true, p is calculated at port_a else m_flow
BooleanexposeState_bfalse=true, p is calculated at port_b else m_flow
BooleanuseLumpedPressurefalse=true to lump pressure states together
LumpedLocationlumpPressureAtLumpedLocation.port_aLocation of pressure for flow calculations
BooleanuseInnerPortPropertiesfalse=true to take port properties for flow models from internal control volumes
Visualization
BooleanshowNametrue
BooleanshowDesignFlowDirectiontrue

Connectors

TypeNameDefaultDescription
TRANSFORM.Fluid.Interfaces.FluidPort_Flowport_a
TRANSFORM.Fluid.Interfaces.FluidPort_Flowport_b

Components

TypeNameDefaultDescription
Geometrygeometry
SI.PowerQ_fission_inputQ_nominalFission power (if specifyPower=true)
SI.PowerQ_external0Power from external source of neutrons
Units.NonDimrho_input0External Reactivity
Units.InverseTime[kinetics.nC]dlambdasfill(0, kinetics.nC)Change in decay constants for each precursor group
Units.NonDim[kinetics.nC]dalphasfill(0, kinetics.nC)Change in normalized precursor fractions [betas = alphas*Beta]
Units.NonDimdBeta0Change in effective delayed neutron fraction [e.g., Beta = sum(beta_i)]
SI.TimedLambda0Change in prompt neutron generation time
Units.InverseTime[kinetics.nDH]dlambdas_dhfill(0, kinetics.nDH)Change in decay constant
Units.NonDim[kinetics.nDH]defs_dhfill(0, kinetics.nDH)Change in effective energy fraction
Units.NonDim[kinetics.nFS]dfissionSourcesfill(0, kinetics.nFS)Change in source of fissile material fractional composition (sum=1)
Units.NonDim[kinetics.nFS,kinetics.nT]dfissionTypesfill(0, kinetics.nFS, kinetics.nT)Change in fraction of fission from each fission type per fission source, sum(row) = 1
Units.NonDimdnu_bar0Change in neutrons per fission
SI.Energydw_f0Change in energy released per fission
SI.MacroscopicCrossSectiondSigmaF0Change in macroscopic fission cross-section of fissile material
SI.Area[kinetics.nFP]dsigmasAfill(0, kinetics.nFP)Change in microscopic absorption cross-section for reactivity feedback
Real[kinetics.nFP,kinetics.nFS,kinetics.nT]dfissionYieldsfill(0, kinetics.nFP, kinetics.nFS, kinetics.nT)Change in # fission product atoms yielded per fission per fissile source [#/fission]
Units.InverseTime[kinetics.nFP]dlambdas_FPfill(0, kinetics.nFP)Change in decay constants for each fission product
Real[geometry.nV,Medium.nC]SF_mC_add{{coolantSubchannel.mCs[i, j]/sum(coolantSubchannel.mCs[:, j]) for j in 1:Medium.nC} for i in 1:geometry.nV}
Modelica.Blocks.Sources.RealExpressionQ_totalTotal power (fission+decay heat)
TRANSFORM.Nuclear.ReactorKinetics.PointKinetics_L1_powerBasedkinetics
Fluid.Pipes.GenericPipe_MultiTransferSurfacecoolantSubchannel
FuelModels.Regions_3_FD2DCylfuelModel
Blocks.ShapeFactorshapeFactor

Contents

NameDescription
MediumCoolant medium
Material_1
Material_2
Material_3
Geometry
FlowModel
HeatTransfer
Data_PG
Data_DH
Data_FP