7.17.1.31.4. Fission

Syntax

Source For Neutron [{of} SpeciesName | {in} MaterialPhaseName | {ls} {a | b | c}] {@ | at | for | on | over} MeshPartIdentifier = Fission [Beta = beta | N_F = n_f]

Summary

Fission source for neutron equation

Parameter

Value

Default

{of}

{of | species | subindex}

–

SpeciesName

string

–

{in}

{in | material_phase}

–

MaterialPhaseName

string

–

{ls}

{levelset_phase | ls}

–

MeshPartIdentifier

string

–

beta

real

–

n_f

real

–