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whoops, missed some code i could remove
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Adam G Nelson
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1 changed files with 0 additions and 183 deletions
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@ -24,149 +24,6 @@ contains
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! nuclides and sab_tables arrays
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!===============================================================================
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! subroutine read_mgxs()
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! integer :: i ! index in materials array
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! integer :: j ! index over nuclides in material
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! integer :: i_nuclide ! index in nuclides array
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! character(20) :: name ! name of library to load
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! integer :: representation ! Data representation
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! character(MAX_LINE_LEN) :: temp_str
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! type(Material), pointer :: mat
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! type(SetChar) :: already_read
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! integer(HID_T) :: file_id
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! integer(HID_T) :: xsdata_group
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! logical :: file_exists
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! type(VectorReal), allocatable :: temps(:)
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! character(MAX_WORD_LEN) :: word
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! integer, allocatable :: array(:)
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! ! Check if MGXS Library exists
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! inquire(FILE=path_cross_sections, EXIST=file_exists)
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! if (.not. file_exists) then
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! ! Could not find MGXS Library file
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! call fatal_error("Cross sections HDF5 file '" &
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! // trim(path_cross_sections) // "' does not exist!")
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! end if
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! call write_message("Loading cross section data...", 5)
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! ! Get temperatures
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! call get_temperatures(temps)
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! ! Open file for reading
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! file_id = file_open(path_cross_sections, 'r', parallel=.true.)
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! ! Read filetype
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! call read_attribute(word, file_id, "filetype")
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! if (word /= 'mgxs') then
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! call fatal_error("Provided MGXS Library is not a MGXS Library file.")
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! end if
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! ! Read revision number for the MGXS Library file and make sure it matches
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! ! with the current version
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! call read_attribute(array, file_id, "version")
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! if (any(array /= VERSION_MGXS_LIBRARY)) then
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! call fatal_error("MGXS Library file version does not match current &
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! &version supported by OpenMC.")
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! end if
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! ! allocate arrays for MGXS storage and cross section cache
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! allocate(nuclides_MG(n_nuclides))
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! ! ==========================================================================
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! ! READ ALL MGXS CROSS SECTION TABLES
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! ! Loop over all files
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! MATERIAL_LOOP: do i = 1, n_materials
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! mat => materials(i)
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! NUCLIDE_LOOP: do j = 1, mat % n_nuclides
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! name = mat % names(j)
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! if (.not. already_read % contains(name)) then
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! i_nuclide = mat % nuclide(j)
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! call write_message("Loading " // trim(name) // " data...", 6)
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! ! Check to make sure cross section set exists in the library
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! if (object_exists(file_id, trim(name))) then
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! xsdata_group = open_group(file_id, trim(name))
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! else
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! call fatal_error("Data for '" // trim(name) // "' does not exist in "&
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! &// trim(path_cross_sections))
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! end if
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! ! First find out the data representation
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! if (attribute_exists(xsdata_group, "representation")) then
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! call read_attribute(temp_str, xsdata_group, "representation")
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! if (trim(temp_str) == 'isotropic') then
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! representation = MGXS_ISOTROPIC
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! else if (trim(temp_str) == 'angle') then
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! representation = MGXS_ANGLE
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! else
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! call fatal_error("Invalid Data Representation!")
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! end if
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! else
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! ! Default to isotropic representation
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! representation = MGXS_ISOTROPIC
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! end if
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! ! Now allocate accordingly
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! select case(representation)
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! case(MGXS_ISOTROPIC)
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! allocate(MgxsIso :: nuclides_MG(i_nuclide) % obj)
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! case(MGXS_ANGLE)
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! allocate(MgxsAngle :: nuclides_MG(i_nuclide) % obj)
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! end select
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! ! Now read in the data specific to the type we just declared
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! call nuclides_MG(i_nuclide) % obj % from_hdf5(xsdata_group, &
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! num_energy_groups, num_delayed_groups, temps(i_nuclide), &
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! temperature_method, temperature_tolerance, max_order, &
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! legendre_to_tabular, legendre_to_tabular_points)
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! ! Add name to dictionary
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! call already_read % add(name)
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! call close_group(xsdata_group)
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! end if
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! end do NUCLIDE_LOOP
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! end do MATERIAL_LOOP
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! ! Avoid some valgrind leak errors
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! call already_read % clear()
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! ! Loop around material
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! MATERIAL_LOOP3: do i = 1, n_materials
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! ! Get material
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! mat => materials(i)
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! ! Loop around nuclides in material
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! NUCLIDE_LOOP2: do j = 1, mat % n_nuclides
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! ! Is this fissionable?
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! if (nuclides_MG(mat % nuclide(j)) % obj % fissionable) then
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! mat % fissionable = .true.
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! end if
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! if (mat % fissionable) then
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! exit NUCLIDE_LOOP2
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! end if
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! end do NUCLIDE_LOOP2
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! end do MATERIAL_LOOP3
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! call file_close(file_id)
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! end subroutine read_mgxs
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subroutine read_mgxs()
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integer :: i ! index in materials array
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integer :: j ! index over nuclides in material
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@ -248,45 +105,6 @@ contains
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! CREATE_MACRO_XS generates the macroscopic xs from the microscopic input data
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!===============================================================================
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! subroutine create_macro_xs()
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! integer :: i_mat ! index in materials array
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! type(Material), pointer :: mat ! current material
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! type(VectorReal), allocatable :: kTs(:)
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! allocate(macro_xs(n_materials))
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! ! Get temperatures to read for each material
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! call get_mat_kTs(kTs)
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! ! Force all nuclides in a material to be the same representation.
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! ! Therefore type(nuclides(mat % nuclide(1)) % obj) dictates type(macroxs).
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! ! At the same time, we will find the scattering type, as that will dictate
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! ! how we allocate the scatter object within macroxs.allocate(macro_xs(n_materials))
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! do i_mat = 1, n_materials
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! ! Get the material
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! mat => materials(i_mat)
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! ! Get the scattering type for the first nuclide
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! select type(nuc => nuclides_MG(mat % nuclide(1)) % obj)
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! type is (MgxsIso)
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! allocate(MgxsIso :: macro_xs(i_mat) % obj)
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! type is (MgxsAngle)
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! allocate(MgxsAngle :: macro_xs(i_mat) % obj)
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! end select
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! ! Do not read materials which we do not actually use in the problem to
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! ! reduce storage
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! if (allocated(kTs(i_mat) % data)) then
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! call macro_xs(i_mat) % obj % combine(kTs(i_mat), mat, nuclides_MG, &
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! num_energy_groups, num_delayed_groups, max_order, &
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! temperature_tolerance, temperature_method)
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! end if
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! end do
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! end subroutine create_macro_xs
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subroutine create_macro_xs()
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integer :: i_mat ! index in materials array
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type(Material), pointer :: mat ! current material
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@ -318,7 +136,6 @@ contains
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end subroutine create_macro_xs
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!===============================================================================
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! GET_MAT_kTs returns a list of temperatures (in eV) that each
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! material appears at in the model.
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