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Merge pull request #909 from SlaybaughLab/correct-mat-index

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Corrected material index in `openmc_cell_set_temperature` routine
This commit is contained in:
Paul Romano 2017-08-07 13:43:47 -05:00 • committed by GitHub
commit a69c0d02fb
1 changed files with 4 additions and 7 deletions
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11
src/api.F90
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@ -100,7 +100,6 @@ contains
integer(C_INT) :: err ! error code
integer :: j ! looping variable
integer :: n ! number of cell instances
integer :: material_ID ! material associated with cell
integer :: material_index ! material index in materials array
integer :: num_nuclides ! num nuclides in material
integer :: nuclide_index ! index of nuclide in nuclides array
@ -121,16 +120,14 @@ contains
if (cells(index) % fill /= NONE) then
err = E_CELL_NO_MATERIAL
else
! find which material is associated with this cell
! find which material is associated with this cell (material_index
! is the index into the materials array)
if (present(instance)) then
material_ID = cells(index) % material(instance)
material_index = cells(index) % material(instance)
else
material_ID = cells(index) % material(1)
material_index = cells(index) % material(1)
end if
! index of that material into the materials array
material_index = material_dict % get_key(material_ID)
! number of nuclides associated with this material
num_nuclides = size(materials(material_index) % nuclide)