modelPointKinetics_L1_powerBased

Information

For point kinetics leave nV = 1

Parameters

TypeNameDefaultDescription
SI.PowerQ_nominal1e6Total nominal reactor power (fission + decay)
BooleanspecifyPowerfalse=true to specify power (i.e., no der(P) equation)
IntegernCdata.nC# of delayed-neutron precursors groups
Units.NonDim[nC]betas_startalphas_start*Beta_startDelayed neutron precursor fractions
SI.Power[nC]Cs_start_history
SI.Energy[nDH]Es_start_history
IntegernFPfissionProducts.data.nC# of fission products
IntegernFSfissionProducts.data.nFS# of fission product sources
IntegernTfissionProducts.data.nT# of fission product types (e.g., fast/thermal)
IntegernC_add0# of additional substances (i.e., trace fluid substances)
SI.Area[nC_add]sigmasA_add_startfill(0, nC_add)Microscopic absorption cross-section for reactivity feedback
Kinetics › Inputs: Reactivity Feedback
IntegernFeedback0# of reactivity feedbacks (alpha*(val-val_ref)
Kinetics › Decay-Heat
IntegernDHdata_DH.nC# of decay-heat groups
TRANSFORM.Units.InverseTime[nDH]lambdas_dh_startdata_DH.lambdasDecay constant
Units.NonDim[nDH]efs_dh_startdata_DH.efsEffective energy fraction
Booleanuse_historyfalse=true to provide power history
SI.Powerhistoryfill(0, 0, 2)Power history up to simulation time=0, [t,Q]
BooleanincludeDHfalse=true if power history includes decay heat
Kinetics › Neutron Kinetics
Units.InverseTime[nC]lambdas_startdata.lambdasDecay constants for each precursor group
Units.NonDim[nC]alphas_startdata.alphasNormalized precursor fractions [betas = alphas*Beta]
TRANSFORM.Units.NonDimBeta_startdata.BetaEffective delayed neutron fraction [e.g., Beta = sum(beta_i)]
SI.TimeLambda_start1e-5Prompt neutron generation time
Initialization
SI.PowerQ_fission_startQ_nominal/(1 + sum(efs_dh_start))Initial reactor fission power
SI.PowerCs_start{betas_start[j]/(lambdas_start[j]*Lambda_start)*Q_fission_start for j in 1:nC}Power of the initial delayed-neutron precursor concentrations
SI.Energy[nDH]Es_start{Q_fission_start*efs_dh_start[j]/lambdas_dh_start[j] for j in 1:nDH}Initial decay heat group energy
SI.VolumeV_startVolume for fisson product concentration basis
SIadd.ExtraPropertyExtrinsic[nFP]mCs_startFunctions.Initial_FissionProducts(fissionProducts.nC, fissionProducts.nFS, fissionProducts.nT, fissionProducts.parents, fissionSources_start, fissionProducts.fissionTypes_start, fissionProducts.w_f_start, fissionProducts.SigmaF_start, fissionProducts.sigmasA_start, fissionProducts.fissionYields_start, fissionProducts.lambdas_start, fill(1e10, fissionProducts.nC), fissionProducts.Q_fission_start, fissionProducts.V_start)Number of fission product atoms per group per volume
Advanced › Dynamics
DynamicsenergyDynamicsDynamics.DynamicFreeInitialFormulation of nuclear kinetics balances
DynamicstraceDynamicsenergyDynamicsFormulation of neutron precursor balances
DynamicsdecayheatDynamicsenergyDynamicsFormulation of decay-heat balances
DynamicsfissionProductDynamicstraceDynamicsFormulation of fission product balances
Kinetics › Fission Sources
Units.NonDim[nFS]fissionSources_startfill(1/nFS, nFS)Source of fissile material fractional composition (sum=1)
Units.NonDim[nFS,nT]fissionTypes_startfill(1/nT, nFS, 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
Advanced
Real[nFP]mC_nominalfill(1e-6, nFP)Nominal fission product atoms. For numeric purposes only.
Booleantoggle_ReactivityFPtrue=true to include fission product reacitivity feedback

Components

TypeNameDefaultDescription
Datadata
Data_DHdata_DH
SI.PowerQ_fission_inputQ_nominalFission power (if specifyPower=true)
SI.PowerQ_external0Power from external source of neutrons
TRANSFORM.Units.NonDimrho_input0External Reactivity
Real[nFeedback]alphas_feedbackfill(0, nFeedback)Reactivity feedback coefficient (e.g., temperature [1/K])
Real[nFeedback]vals_feedbackvals_feedback_referenceVariable value for reactivity feedback (e.g. fuel temperature)
Real[nFeedback]vals_feedback_referencefill(1, nFeedback)Reference value for reactivity feedback (e.g. fuel reference temperature)
Units.InverseTime[nC]dlambdasfill(0, nC)Change in decay constants for each precursor group
Units.NonDim[nC]dalphasfill(0, nC)Change in normalized precursor fractions [betas = alphas*Beta]
TRANSFORM.Units.NonDimdBeta0Change in effective delayed neutron fraction [e.g., Beta = sum(beta_i)]
SI.TimedLambda0Change in prompt neutron generation time
Units.InverseTime[nC]lambdaslambdas_start + dlambdasDecay constants for each precursor group
Units.NonDim[nC]alphasalphas_start + dalphasNormalized precursor fractions [beta_i = alpha_i*Beta]
TRANSFORM.Units.NonDimBetaBeta_start + dBetaEffective delayed neutron fraction [e.g., Beta = sum(beta_i)]
SI.TimeLambdaLambda_start + dLambdaPrompt neutron generation time
Units.InverseTime[nDH]dlambdas_dhfill(0, nDH)Change in decay constant
Units.NonDim[nDH]defs_dhfill(0, nDH)Change in effective energy fraction
TRANSFORM.Units.InverseTime[nDH]lambdas_dhlambdas_dh_start + dlambdas_dhDecay constant
Units.NonDim[nDH]efs_dhefs_dh_start + defs_dhEffective energy fraction
Units.NonDim[nC]betasalphas*BetaDelayed neutron precursor fractions
TRANSFORM.Units.NonDimrhos_feedbackLinear reactivity feedback
TRANSFORM.Units.NonDimrhoTotal reactivity feedback
SI.PowerQ_totalTotal power determined from kinetics and decay-heat
SI.PowerQ_fissionFission power determined from kinetics, excluding decay-heat
SI.Power[nDH]Qs_decayDecay-heat per group
SI.PowerQ_decaysum(Qs_decay[:])Total decay-heat
TRANSFORM.Units.NonDimetaQ_decay/max(1, Q_fission)Ratio of decay heat to fisson power
SI.Power[nC]CsPower of the delayed-neutron precursor concentration
SI.Energy[nDH]EsEnergy of the decay-heat precursor group
TRANSFORM.Nuclear.ReactorKinetics.Reactivity.FissionProductsfissionProducts
Units.NonDim[nFS]dfissionSourcesfill(0, nFS)Change in source of fissile material fractional composition (sum=1)
Units.NonDim[nFS,nT]dfissionTypesfill(0, nFS, 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[nFP]dsigmasAfill(0, nFP)Change in microscopic absorption cross-section for reactivity feedback
Real[nFP,nFS,nT]dfissionYieldsfill(0, nFP, nFS, nT)Change in # fission product atoms yielded per fission per fissile source [#/fission]
Units.InverseTime[nFP]dlambdas_FPfill(0, nFP)Change in decay constants for each fission product
SI.VolumeV0.1Volume for fisson product concentration basis
SIadd.ExtraPropertyExtrinsic[nC_add]mCs_addfill(0, nC_add)Number of atoms
SI.VolumeVs_add0.1Volume for fisson product concentration basis
SI.Area[nC_add]dsigmasA_addfill(0, nC_add)Change in microscopic absorption cross-section for reactivity feedback

Contents

NameDescription
Data
Data_DH
Data_FP