pyopensn.xs.MultiGroupXS

class pyopensn.xs.MultiGroupXS

Multi-group cross section.

Wrapper of opensn::MultiGroupXS.

The Python API currently has two types of methods:

Creation/loading methods such as CreateSimpleOneGroup, LoadFromOpenSn, and LoadFromOpenMC populate an existing object.
Scale mutates the current object.
Combine returns a new cross-section object and does not mutate inputs.

static Combine(combinations: list[tuple[pyopensn.xs.MultiGroupXS, float]]) → pyopensn.xs.MultiGroupXS

Return a new combined cross-section.

Parameters:: combinations (List[Tuple[pyopensn.xs.MultiGroupXS, float]]) – List of (cross_section, density) pairs. The density values are linear weights used to combine raw cross sections.
Returns:: A new combined cross-section object. The input cross sections are not modified.
Return type:: pyopensn.xs.MultiGroupXS

Notes

Let \(d_i\) be the supplied density for cross section \(i\).

Raw XS terms are density-weighted sums: \(\sigma = \sum_i d_i \sigma_i\) (e.g. total, absorption, fission, transfer, production).
Named custom 1D XS are preserved and combined with the same density weighting.
Fission spectra and precursor yields are weighted by fissile density fraction so their sums remain normalized.
All inputs must have the same number of groups.
If inverse velocity is present, all inputs must have identical values.

Examples

>>> xs_1 = MultiGroupXS()
>>> xs_1.CreateSimpleOneGroup(sigma_t=1, c=0.5)
>>> xs_2 = MultiGroupXS()
>>> xs_2.CreateSimpleOneGroup(sigma_t=2, c=1./3.)
>>> combo = [
...     ( xs_1, 0.5 ),
...     ( xs_2, 3.0 )
... ]
>>> xs_combined = MultiGroupXS.Combine(combo)

CreateSimpleOneGroup(self: pyopensn.xs.MultiGroupXS, sigma_t: float, c: float, velocity: float = 0.0) → None

Populate this object with a one-group cross section.

Parameters:

sigma_t (float) – Total cross section.
c (float) – Scattering ratio.
velocity (float, optional) – Group velocity. If provided and positive, inverse velocity is populated with 1.0/velocity.

Notes

This method mutates self by replacing its current contents.

GetScaleFactor(self: pyopensn.xs.MultiGroupXS) → float: Get the scaling factor.

LoadFromOpenMC(self: pyopensn.xs.MultiGroupXS, file_name: str, dataset_name: str, temperature: float, extra_xs_names: list[str] = []) → None

Load multi-group cross sections from an OpenMC cross-section file into this object.

Notes

This method mutates self by replacing its current contents.

LoadFromOpenSn(self: pyopensn.xs.MultiGroupXS, file_name: str) → None

Load multi-group cross sections from an OpenSn cross section input file into this object.

Format is as follows (for transfers, gprime denotes the departing group and g is the arrival group).

# Add comment lines, as needed
NUM_GROUPS ng
NUM_MOMENTS nmom

SIGMA_T_BEGIN
0 value
.
.
ng-1 value
SIGMA_T_END

SIGMA_A_BEGIN
0 value
.
.
ng-1 value
SIGMA_A_END

TRANSFER_MOMENTS_BEGIN
M_GFROM_GTO_VAL 0 0 0 value
.
M_GFROM_GTO_VAL moment gfrom gto value
.
M_GFROM_GTO_VAL nmom-1 ng-1 ng-1 value
TRANSFER_MOMENTS_END

Notes

This method mutates self by replacing its current contents.

Scale(self: pyopensn.xs.MultiGroupXS, factor: float) → None

Scale the cross sections in-place.

Notes

Scaling does not compound. Each call scales from the original baseline data. Named custom 1D XS are scaled along with the standard 1D cross-section data.

__init__(self: pyopensn.xs.MultiGroupXS) → None: Create an empty multi-group cross section.

property chi: Get neutron fission spectrum.

custom_xs_names(self: pyopensn.xs.MultiGroupXS) → list[str]: Get a list of custom XS entries.

get_custom_xs(self: pyopensn.xs.MultiGroupXS, name: str) → memoryview: Get a custom XS vector.

has_custom_xs(self: pyopensn.xs.MultiGroupXS, name: str) → bool: Check if a custom XS is available.

property inv_velocity: Get inverse velocity.

property is_fissionable: Check if the material is fissile.

property nu_delayed_sigma_f: Get delayed neutron production due to fission.

property nu_prompt_sigma_f: Get prompt neutron production due to fission.

property nu_sigma_f: Get neutron production due to fission.

property num_groups: Get number of energy groups.

property num_precursors: Get number of precursors.

property scattering_order: Get Legendre scattering order.

property sigma_a: Get absorption cross section.

property sigma_f: Get fission cross section.

property sigma_t: Get total cross section.