/**
* @brief Set the Material's array of absorption scattering cross-sections.
* @details This method is a helper function to allow OpenMOC users to assign
* the Material's nuclear data in Python. A user must initialize a
* NumPy array of the correct size (i.e., a float64 array the length
* of the number of energy groups) as input to this function. This
* function then fills the NumPy array with the data values for the
* Material's absorption cross-sections. An example of how this
* function might be called in Python is as follows:
*
* @code
* sigma_a = numpy.array([0.05, 0.1, 0.15, ... ])
* material = openmoc.Material(openmoc.material_id())
* material.setSigmaA(sigma_a)
* @endcode
*
* @param xs the array of absorption scattering cross-sections
* @param num_groups the number of energy groups
*/
void Material::setSigmaA(double* xs, int num_groups) {
if (_num_groups != num_groups)
log_printf(ERROR, "Unable to set sigma_a with %d groups for Material "
"%d which contains %d energy groups", num_groups, _id, _num_groups);
for (int i=0; i < _num_groups; i++){
_sigma_a[i] = FP_PRECISION(xs[i]);
if (_buckling != NULL & _dif_coef != NULL)
_sigma_a[i] += FP_PRECISION(_buckling[i] * _dif_coef[i]);
}
}
/**
* @brief Set the Material's total cross-section for some energy group.
* @param xs the total cross-section
* @param group the energy group
*/
void Material::setSigmaTByGroup(double xs, int group) {
if (group <= 0 || group > _num_groups)
log_printf(ERROR, "Unable to set sigma_t for group %d for Material "
"%d which contains %d energy groups", group, _id, _num_groups);
/* If the cross-section is near zero (e.g., within (-1E-10, 1E-10)) */
if (fabs(xs) < ZERO_SIGMA_T) {
log_printf(INFO, "Overriding zero cross-section in "
"group %d for Material %d with 1E-10", group, _id);
_sigma_t[group-1] = FP_PRECISION(ZERO_SIGMA_T);
}
else
_sigma_t[group-1] = FP_PRECISION(xs);
}
/**
* @brief Set the Material's array of total cross-sections.
* @details This method is a helper function to allow OpenMOC users to assign
* the Material's nuclear data in Python. A user must initialize a
* NumPy array of the correct size (i.e., a float64 array the length
* of the number of energy groups) as input to this function. This
* function then fills the NumPy array with the data values for the
* Material's total cross-sections. An example of how this function
* might be called in Python is as follows:
*
* @code
* sigma_t = numpy.array([0.05, 0.1, 0.15, ... ])
* material = openmoc.Material(openmoc.material_id())
* material.setSigmaT(sigma_t)
* @endcode
*
* @param xs the array of total cross-sections
* @param num_groups the number of energy groups
*/
void Material::setSigmaT(double* xs, int num_groups) {
if (_num_groups != num_groups)
log_printf(ERROR, "Unable to set sigma_t with %d groups for Material "
"%d which contains %d energy groups", num_groups, _id, _num_groups);
for (int i=0; i < _num_groups; i++)
_sigma_t[i] = FP_PRECISION(xs[i]);
}
/**
* @brief Set the Material's array of total cross-sections.
* @details This method is a helper function to allow OpenMOC users to assign
* the Material's nuclear data in Python. A user must initialize a
* NumPy array of the correct size (e.g., a float64 array the length
* of the number of energy groups) as input to this function. This
* function then fills the NumPy array with the data values for the
* Material's total cross-sections. An example of how this function
* might be called in Python is as follows:
*
* @code
* sigma_t = numpy.array([0.05, 0.1, 0.15, ... ])
* material = openmoc.Material(openmoc.material_id())
* material.setSigmaT(sigma_t)
* @endcode
*
* NOTE: This routine will override an zero-valued cross-sections
* (e.g., in void or gap regions) with a minimum value of 1E-10 to
* void numerical issues in the MOC solver.
*
* @param xs the array of total cross-sections
* @param num_groups the number of energy groups
*/
void Material::setSigmaT(double* xs, int num_groups) {
if (_num_groups != num_groups)
log_printf(ERROR, "Unable to set sigma_t with %d groups for Material "
"%d which contains %d energy groups", num_groups,
_id, _num_groups);
for (int i=0; i < _num_groups; i++) {
/* If the cross-section is near zero (e.g., within (-1E-10, 1E-10)) */
if (fabs(xs[i]) < ZERO_SIGMA_T) {
log_printf(INFO, "Overriding zero cross-section in "
"group %d for Material %d with 1E-10", i, _id);
_sigma_t[i] = FP_PRECISION(ZERO_SIGMA_T);
}
else
_sigma_t[i] = FP_PRECISION(xs[i]);
}
}
