modelPointKineticMoltenSaltReactor

Component for point reactor simulation

Parameters

TypeNameDefaultDescription
IntegerNd6number of delayed neutron groups
DelayedNeutronFractionbeta303.6e-5total fraction of delayed Neutrons
DelayedNeutronFraction[Nd]bet{23.9e-5, 59.1e-5, 62.6e-5, 115.5e-5, 31.6e-5, 10.9e-5}fraction of delayed neutron precursors
DecayConstant[Nd]landa{1.272e-2, 31.74e-2, 0.116e-1, 1.33e-1, 1.4, 3.87}decay constant of the jth precursor group
DecayConstantlTransit1./4.5inverse core transit time
GenerationTimeLamda0.36/1000mean neutron generation time
Realalpha00reactor heat port heat transfer coefficient
RealT_refModelica.SIunits.Conversions.from_degC(650)reactor heat port reference temperature
Reactivityrho0NullReactivity(beta, bet, landa, 6, lTransit)initial reactivity
RealEnergyPerFission200.0*1.6021766e-13energy release per fission in Joules
RealNominalPower20.0nominal power of reactor in MW
RealReactorFuelTemperature700.0average reactor fuel temperature

Connectors

TypeNameDefaultDescription
Modelica.Blocks.Interfaces.RealInputrhotime dependent reactivity input in pcm
Modelica.Thermal.HeatTransfer.Interfaces.HeatPort_bport_b
Modelica.Blocks.Interfaces.RealOutputReactorPowerOutput

Components

TypeNameDefaultDescription
NeutronPopulationN
DelayedNeutronFraction[Nd]C

Contents

NameDescription
NeutronPopulation
PrecurserConcentration
Reactivity
DelayedNeutronFraction
DecayConstant
GenerationTime