source: CIVL/examples/xsbench/src/CalculateXS.c@ bb03188

#include "XSbench_header.h"

// Calculates the microscopic cross section for a given nuclide & energy
void calculate_micro_xs(   double p_energy, int nuc, long n_isotopes,
                           long n_gridpoints,
                           GridPoint * restrict energy_grid,
                           NuclideGridPoint ** restrict nuclide_grids,
                           int idx, double * restrict xs_vector ){
        
        // Variables
        double f;
        NuclideGridPoint * low, * high;

        // pull ptr from energy grid and check to ensure that
        // we're not reading off the end of the nuclide's grid
        if( energy_grid[idx].xs_ptrs[nuc] == n_gridpoints - 1 )
                low = &nuclide_grids[nuc][energy_grid[idx].xs_ptrs[nuc] - 1];
        else
                low = &nuclide_grids[nuc][energy_grid[idx].xs_ptrs[nuc]];
        
        high = low + 1;
        
        // calculate the re-useable interpolation factor
        f = (high->energy - p_energy) / (high->energy - low->energy);

        // Total XS
        xs_vector[0] = high->total_xs - f * (high->total_xs - low->total_xs);
        
        // Elastic XS
        xs_vector[1] = high->elastic_xs - f * (high->elastic_xs - low->elastic_xs);
        
        // Absorbtion XS
        xs_vector[2] = high->absorbtion_xs - f * (high->absorbtion_xs - low->absorbtion_xs);
        
        // Fission XS
        xs_vector[3] = high->fission_xs - f * (high->fission_xs - low->fission_xs);
        
        // Nu Fission XS
        xs_vector[4] = high->nu_fission_xs - f * (high->nu_fission_xs - low->nu_fission_xs);
        
        //test
        /*      
        if( omp_get_thread_num() == 0 )
        {
                printf("Lookup: Energy = %lf, nuc = %d\n", p_energy, nuc);
                printf("e_h = %lf e_l = %lf\n", high->energy , low->energy);
                printf("xs_h = %lf xs_l = %lf\n", high->elastic_xs, low->elastic_xs);
                printf("total_xs = %lf\n\n", xs_vector[1]);
        }
        */
        
}

// Calculates macroscopic cross section based on a given material & energy 
void calculate_macro_xs( double p_energy, int mat, long n_isotopes,
                         long n_gridpoints, int * restrict num_nucs,
                         double ** restrict concs,
                         GridPoint * restrict energy_grid,
                         NuclideGridPoint ** restrict nuclide_grids,
                         int ** restrict mats,
                         double * restrict macro_xs_vector ){
        double xs_vector[5];
        int p_nuc; // the nuclide we are looking up
        long idx = 0;   
        double conc; // the concentration of the nuclide in the material

        // cleans out macro_xs_vector
        for( int k = 0; k < 5; k++ )
                macro_xs_vector[k] = 0;

        // binary search for energy on unionized energy grid (UEG)
        idx = grid_search( n_isotopes * n_gridpoints, p_energy,
                           energy_grid);        
        
        // Once we find the pointer array on the UEG, we can pull the data
        // from the respective nuclide grids, as well as the nuclide
        // concentration data for the material
        // Each nuclide from the material needs to have its micro-XS array
        // looked up & interpolatied (via calculate_micro_xs). Then, the
        // micro XS is multiplied by the concentration of that nuclide
        // in the material, and added to the total macro XS array.
        for( int j = 0; j < num_nucs[mat]; j++ )
        {
                p_nuc = mats[mat][j];
                conc = concs[mat][j];
                calculate_micro_xs( p_energy, p_nuc, n_isotopes,
                                    n_gridpoints, energy_grid,
                                    nuclide_grids, idx, xs_vector );
                for( int k = 0; k < 5; k++ )
                        macro_xs_vector[k] += xs_vector[k] * conc;
        }
        
        //test
        /*
        for( int k = 0; k < 5; k++ )
                printf("Energy: %lf, Material: %d, XSVector[%d]: %lf\n",
                       p_energy, mat, k, macro_xs_vector[k]);
        */
}


// (fixed) binary search for energy on unionized energy grid
// returns lower index
long grid_search( long n, double quarry, GridPoint * A)
{
        long lowerLimit = 0;
        long upperLimit = n-1;
        long examinationPoint;
        long length = upperLimit - lowerLimit;

        while( length > 1 )
        {
                examinationPoint = lowerLimit + ( length / 2 );
                
                if( A[examinationPoint].energy > quarry )
                        upperLimit = examinationPoint;
                else
                        lowerLimit = examinationPoint;
                
                length = upperLimit - lowerLimit;
        }
        
        return lowerLimit;
}