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MatlabTransportPack
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Defines the isotropic source from fission reactions. More...


Public Member Functions | |
| function | FissionSource (in state, in mesh, in mat) |
| Class constructor. | |
| function | initialize (in obj) |
| Initialize the fission source. | |
| function | reset (in obj) |
| function | initialized (in obj) |
| function | update (in obj) |
| Update the fission density. | |
| function | normalize (in obj) |
| Normalize the fission density. | |
| function | setup_outer (in obj, in scale) |
| Setup the fission source for an outer iteration. | |
| function | source (in obj, in g) |
| Return the fission source in a group. | |
| function | density (in obj) |
Private Attributes | |
| Property | d_state |
| State vectors. | |
| Property | d_mesh |
| Problem mesh. | |
| Property | d_mat |
| Material definitions. | |
| Property | d_nu_sigma_f |
Vector of values for dot product. | |
| Property | d_chi |
Vector values for dot product. | |
| Property | d_fission_density |
Fission density, . | |
| Property | d_fission_source |
Fission source, . | |
| Property | d_scale |
| Fission source scaling term. | |
| Property | d_angular_norm |
| Property | d_initialized |
| Are we initialized? | |
Defines the isotropic source from fission reactions.
| function FissionSource | ( | in | state, |
| in | mesh, | ||
| in | mat | ||
| ) |
Class constructor.
| mesh | Problem mesh. |
| mat | Material definitions. |
| function density | ( | in | obj | ) |
| function initialize | ( | in | obj | ) |
Initialize the fission source.
Having a separate initialization routine lets us pass around an empty fission source object, yielding more generic programming.
| function initialized | ( | in | obj | ) |
| function normalize | ( | in | obj | ) |
Normalize the fission density.
This can be useful if one wants the initial guess to be normalized.
| function reset | ( | in | obj | ) |
| function setup_outer | ( | in | obj, |
| in | scale | ||
| ) |
Setup the fission source for an outer iteration.
This sets a new scaling factor
and precomputes the quantity
.
| scale | Scaling factor (typically 1/keff) |
| function source | ( | in | obj, |
| in | g | ||
| ) |
Return the fission source in a group.
The group fission source is just that component of the density released in a particular group. Mathematically, this is just
Note, the scaling factor is actually arbitrary. For 2-D and 3-D, it is
, possibly with the eigenvalue
. The client sets this in update.
Note also that this returns a discrete source, ready for use in sweeping.
| g | Group of the source |
| function update | ( | in | obj | ) |
Update the fission density.
The fission source density is defined
This density is updated at the beginning of an outer iteration when a new (or initial) scalar flux is known. At this time, a scaling factor can be set. Most often, this is based on an updated eigenvalue estimate (for reactor problems), or may be any other arbitrary value as needed for a variety of problems.
| scale | Scaling factor (typically 1/keff) |
Property d_angular_norm [private] |
Property d_chi [private] |
Vector
values for dot product.
Property d_fission_density [private] |
Fission density,
.
Property d_fission_source [private] |
Fission source,
.
Property d_initialized [private] |
Are we initialized?
Property d_mat [private] |
Material definitions.
Property d_mesh [private] |
Problem mesh.
Property d_nu_sigma_f [private] |
Vector of
values for dot product.
Property d_scale [private] |
Fission source scaling term.
1.7.3