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An open source method of characteristics neutron transport code.
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A Material's nuclear data to be stored on a GPU. More...
#include <DeviceMaterial.h>
Public Member Functions | |
| dev_material () | |
| Constructor for a dev_material struct on a GPU. | |
| ~dev_material () | |
| Destructor releases data for all Material's cross-sections on GPU. | |
Public Attributes | |
| int | _id |
| FP_PRECISION * | _sigma_t |
| FP_PRECISION * | _sigma_f |
| FP_PRECISION * | _nu_sigma_f |
| FP_PRECISION * | _chi |
| FP_PRECISION * | _fiss_matrix |
| FP_PRECISION * | _sigma_s |
A Material's nuclear data to be stored on a GPU.
| FP_PRECISION* dev_material::_chi |
An array of the chi
values for each energy group
| FP_PRECISION* dev_material::_fiss_matrix |
A 2D array of the fission matrix from/into each group
| int dev_material::_id |
A user-defined ID for each Material created
| FP_PRECISION* dev_material::_nu_sigma_f |
An array of the fission cross-sections multiplied by nu
for each energy group
| FP_PRECISION* dev_material::_sigma_f |
A 2D array of the scattering cross-section matrix. The first index is row number and second index is column number
| FP_PRECISION* dev_material::_sigma_s |
A 2D array of the scattering cross-section matrix from/into each group
| FP_PRECISION* dev_material::_sigma_t |
An array of the total cross-sections for each energy group