modelPointKinetics_L1_atomBased_external

Parameters

TypeNameDefaultDescription
IntegernV1# of discrete volumes
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
IntegernTRfissionProducts.data_TR.nC
Kinetics › Inputs: Reactivity Feedback
IntegernFeedback0# of reactivity feedbacks (alpha*(val-val_ref)
Initialization › 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)]
Kinetics › Neutron Kinetics
SI.TimeLambda_start1e-5Prompt neutron generation time
Initialization
SI.PowerQs_fission_startQ_nominalInitial reactor fission power per volume
Advanced › Dynamics
DynamicsenergyDynamicsDynamics.DynamicFreeInitialFormulation of nuclear kinetics balances
Kinetics
IntegernFPfissionProducts.data.nC# of fission products
IntegernFSfissionProducts.data.nFS# of fission product sources
IntegernTfissionProducts.data.nT# of fission product types (e.g., fast/thermal)
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

Components

TypeNameDefaultDescription
Datadata
SI.PowerQs_fission_inputQ_nominalFission power (if specifyPower=true)
Units.InverseTimeNs_external0Rate of neutrons added from an external neutron source
Units.NonDimrhos_input0External Reactivity
SI.VolumeVsVolume for atom concentration basis
SIadd.ExtraPropertyExtrinsicmCs# of neutron precursors in each volume [atoms]
SIadd.ExtraPropertyExtrinsicmCs_FP{{0 for j in 1:nFP} for i in 1:nV}Fission product number in each volume [atoms]
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.NonDim[nC]betasalphas*BetaDelayed neutron precursor fractions
TRANSFORM.Units.NonDimrhos_feedbackLinear reactivity feedback
TRANSFORM.Units.NonDimrhosTotal reactivity feedback
SI.Power[nV]QsPower determined from kinetics and decay-heat per volume
SI.PowerQ_totalsum(Qs)Total power output, including decay-heat
SI.PowerQs_fissionFission power determined from kinetics
SI.PowerQ_fission_totalQs_fissionTotal fission power output, excluding decay-heat
SI.Power[nV,nFP]Qs_decayDecay-heat per fission product per volume
SI.Power[nV]Qs_decay_total{sum(Qs_decay[i, :]) for i in 1:nV}Total decay-heat per volume
SI.PowerQ_decay_totalsum(Qs_decay_total)Total decay-heat
SIadd.NonDimetaQ_decay_total/max(1, Q_fission_total)Ratio of decay heat to fisson power
TRANSFORM.Nuclear.ReactorKinetics.Reactivity.FissionProducts_externalBalance_withTritium_withDecayHeatfissionProducts
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
SIadd.ExtraPropertyFlowRatemC_gensGeneration rate of neutron precursor groups [atoms/s]
SI.Energy[nFP]dw_near_decayfill(0, nFP)Change in energy released per decay of each fission product [J/decay] (near field - e.g., beta)
SI.Energy[nFP]dw_far_decayfill(0, nFP)Change in energy released per decay of each fission product [J/decay] (far field - e.g., gamma)
SI.Area[nTR]dsigmasA_TRfill(0, fissionProducts.nTR)Change in microscopic absorption cross-section for reactivity feedback
SI.Area[nTR]dsigmasT_TRfill(0, fissionProducts.nTR)Change in microscopic absorption cross-section for tritium generation
TRANSFORM.Units.InverseTime[nTR]dlambdas_TRfill(0, fissionProducts.nTR)Decay constants for each tritium contributor
TRANSFORM.Units.ExtraPropertyExtrinsic[nV,nTR]mCs_TR{{0 for j in 1:fissionProducts.nTR} for i in 1:fissionProducts.nV}Amount of each contributor to tritium [atoms]
SIadd.NonDim[nV]SF_Qs_fissionfill(1/nV, nV)Shape factor for Qs_fission, sum() = 1
TRANSFORM.Nuclear.ReactorKinetics.Data.summary_traceSubstancessummary_data

Contents

NameDescription
Data
Data_FP
Data_TR
Data_CP