mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 22:26:08 -04:00
Removed many unused variables.
This commit is contained in:
parent
f0e1337e30
commit
404b487591
14 changed files with 55 additions and 91 deletions
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@ -43,9 +43,6 @@ contains
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character(10) :: key ! name of isotope, e.g. 92235.03c
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character(MAX_LINE_LEN) :: msg ! output/error message
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type(Material), pointer :: mat => null()
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type(xsData), pointer :: iso => null()
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type(Nuclide), pointer :: ace_cont => null()
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type(SAB_Table), pointer :: ace_thermal => null()
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type(DictionaryCI), pointer :: temp_dict => null()
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call dict_create(nuclide_dict)
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@ -276,7 +273,7 @@ contains
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type(Nuclide), pointer :: nuc
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integer :: i, j ! loop indices
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integer :: i ! loop index
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integer :: JXS2 ! location for fission nu data
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integer :: JXS24 ! location for delayed neutron data
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integer :: KNU ! location for nu data
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@ -672,7 +669,7 @@ contains
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integer :: loc ! locator
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integer :: length ! length of data to allocate
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integer :: length_interp_data ! length of interpolation data
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integer :: i, j, k, l ! indices
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integer :: i ! loop index
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type(Reaction), pointer :: rxn => null()
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LED = JXS(10)
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@ -887,7 +884,6 @@ contains
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integer :: M ! # of probabilities
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integer :: i ! index over incoming energies
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integer :: j ! index over values
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integer :: k ! index over cumulative probabilities
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! determine locator for URR data
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JXS23 = JXS(23)
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@ -1184,15 +1180,15 @@ contains
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xs = ZERO
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! find material atom density
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density = cMaterial%atom_density
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density = mat % atom_density
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! loop over all nuclides in material
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n_nuclides = cMaterial % n_nuclides
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n_nuclides = mat % n_nuclides
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do i = 1, n_nuclides
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nuc => nuclides(cMaterial % nuclide(i))
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nuc => nuclides(mat % nuclide(i))
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! determine nuclide atom density
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density_i = cMaterial%atom_percent(i) * density
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density_i = mat % atom_percent(i) * density
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! search nuclide energy grid
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IE = nuc%grid_index(p % IE)
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@ -1240,7 +1236,7 @@ contains
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character(MAX_LINE_LEN) :: msg
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character(MAX_WORD_LEN) :: words(MAX_WORDS)
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character(MAX_WORD_LEN) :: filename
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integer :: i, n
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integer :: n
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integer :: in = 7
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logical :: file_exists
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character(7) :: readable
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@ -1347,7 +1343,6 @@ contains
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integer :: i, j, k
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integer :: index
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integer :: IE
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real(8) :: xs
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real(8) :: density
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real(8) :: density_i
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real(8) :: val
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@ -846,7 +846,6 @@ contains
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character(*), intent(in) :: key
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integer :: value
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type(KeyValueCI) :: data
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type(ListKeyValueCI), pointer :: elem
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elem => dict_get_elem(dict, key)
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@ -872,7 +871,6 @@ contains
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integer, intent(in) :: key
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integer :: value
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type(KeyValueII) :: data
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type(ListKeyValueII), pointer :: elem
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elem => dict_get_elem(dict, key)
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@ -990,14 +988,13 @@ contains
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function dict_ci_hashkey(key) result(val)
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character(*), intent(in) :: key
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integer :: val
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integer :: val
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integer :: hash
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integer :: i
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val = 0
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do i = 1,len(key)
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do i = 1, len(key)
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val = HASH_MULTIPLIER * val + ichar(key(i:i))
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enddo
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@ -1016,10 +1013,7 @@ contains
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function dict_ii_hashkey(key) result(val)
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integer, intent(in) :: key
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integer :: val
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integer :: hash
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integer :: i
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integer :: val
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val = 0
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@ -1040,7 +1034,7 @@ contains
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type(ListKeyValueCI), pointer :: current => null()
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type(ListKeyValueCI), pointer :: elem => null()
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integer :: i, j
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integer :: i
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head => null()
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@ -1072,7 +1066,7 @@ contains
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type(ListKeyValueII), pointer :: current => null()
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type(ListKeyValueII), pointer :: elem => null()
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integer :: i, j
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integer :: i
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head => null()
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@ -22,7 +22,6 @@ contains
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type(ListReal), pointer :: current => null()
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type(Material), pointer :: mat => null()
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type(Nuclide), pointer :: nuc => null()
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type(Reaction), pointer :: rxn => null()
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integer :: i, j
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integer :: n
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character(MAX_LINE_LEN) :: msg
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@ -84,7 +84,6 @@ contains
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integer :: n ! number of words on a line
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integer :: count ! number of cells in a universe
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integer :: universe_num ! user-specified universe #
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character(MAX_LINE_LEN) :: line ! a line of words in input file
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character(MAX_LINE_LEN) :: msg ! output/error message
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character(MAX_WORD_LEN) :: words(MAX_WORDS) ! words on a line
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type(ListKeyValueII), pointer :: key_list => null()
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@ -235,7 +234,6 @@ contains
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integer :: index_material ! index in materials array
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integer :: index_source ! index in source array (?)
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integer :: index_tally ! index in tally array
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character(MAX_LINE_LEN) :: line ! a line of words
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character(MAX_LINE_LEN) :: msg ! output/error message
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character(MAX_WORD_LEN) :: words(MAX_WORDS) ! words on a single line
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@ -470,7 +468,6 @@ contains
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character(*), intent(in) :: words(n_words) ! words on cell card entry
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integer, intent(in) :: n_words ! number of words
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integer :: ioError ! error status for file access
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integer :: i ! index for surface list in a cell
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integer :: universe_num ! user-specified universe number
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integer :: n_surfaces ! number of surfaces in a cell
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@ -564,7 +561,6 @@ contains
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character(*), intent(in) :: words(n_words) ! words in surface card entry
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integer, intent(in) :: n_words ! number of words
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integer :: ioError ! error status for file access
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integer :: i ! index for surface coefficients
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integer :: coeffs_reqd ! number of coefficients are required
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character(MAX_LINE_LEN) :: msg ! output/error message
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@ -574,8 +570,8 @@ contains
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surf => surfaces(index)
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! Read surface identifier
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read(words(2), FMT='(I8)', IOSTAT=ioError) surf % uid
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if (ioError > 0) then
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surf % uid = str_to_int(words(2))
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if (surf % uid == ERROR_INT) then
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msg = "Invalid surface name: " // trim(words(2))
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call fatal_error(msg)
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end if
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@ -782,7 +778,6 @@ contains
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integer, intent(in) :: n_words ! number of words
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integer :: i ! index in values list
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integer :: ioError ! error status for file access
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integer :: values_reqd ! # of values required to specify source
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character(MAX_LINE_LEN) :: msg ! output/error message
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character(MAX_WORD_LEN) :: word ! single word
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@ -980,7 +975,6 @@ contains
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integer, intent(in) :: n_words ! number of words
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integer :: i ! index over nuclides
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integer :: ioError ! error status for file access
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integer :: n_nuclides ! number of nuclides in material
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character(MAX_LINE_LEN) :: msg ! output/error message
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type(Material), pointer :: mat => null()
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@ -997,8 +991,8 @@ contains
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mat % n_nuclides = n_nuclides
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! Read surface identifier
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read(words(2), FMT='(I8)', IOSTAT=ioError) mat % uid
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if (ioError > 0) then
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mat % uid = str_to_int(words(2))
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if (mat % uid == ERROR_INT) then
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msg = "Invalid surface name: " // trim(words(2))
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call fatal_error(msg)
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end if
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@ -1032,16 +1026,14 @@ contains
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integer :: j ! index over nuclides in material
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real(8) :: sum_percent !
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real(8) :: awr ! atomic weight ratio
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real(8) :: w ! weight percent
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real(8) :: x ! atom percent
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logical :: percent_in_atom ! nuclides specified in atom percent?
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logical :: density_in_atom ! density specified in atom/b-cm?
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character(10) :: key ! name of nuclide, e.g. 92235.03c
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character(MAX_LINE_LEN) :: msg ! output/error message
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type(xsData), pointer :: iso => null()
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type(Material), pointer :: mat => null()
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! first find the index in the xsdata array for each isotope in each material
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! first find the index in the xsdata array for each nuclide in each material
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do i = 1, n_materials
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mat => materials(i)
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@ -1249,7 +1241,6 @@ contains
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integer :: i ! line index
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integer :: loc ! locator for array
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integer :: ioError ! error status
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loc = 0
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do i = 1, lines
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@ -1277,7 +1268,6 @@ contains
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integer :: i ! line index
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integer :: loc ! locator for array
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integer :: ioError ! error status
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loc = 0
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do i = 1, lines
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@ -30,7 +30,6 @@ contains
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integer :: i ! index of surfaces in cell
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integer :: surf_num ! index in surfaces array (with sign)
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integer :: current_surface ! current surface of particle (with sign)
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character(MAX_LINE_LEN) :: msg ! output/error message
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type(Surface), pointer :: surf => null()
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current_surface = p%surface
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@ -135,7 +135,9 @@ contains
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subroutine free_memory()
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#ifdef MPI
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integer :: ierr
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#endif
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! Deallocate cells, surfaces, materials
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if (allocated(cells)) deallocate(cells)
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13
src/main.f90
13
src/main.f90
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@ -26,8 +26,6 @@ program main
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implicit none
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character(max_word_len) :: filename
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character(max_line_len) :: msg
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type(Universe), pointer :: univ
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! Start timers
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@ -117,15 +115,10 @@ contains
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subroutine run_problem()
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integer :: i, j
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integer :: ierr
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integer :: i_cycle ! cycle index
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integer(8) :: i_particle ! history index
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integer :: total_bank ! total number of particles banked
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real(8) :: t0
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real(8) :: t1
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integer :: i_cycle ! cycle index
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integer(8) :: i_particle ! history index
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character(MAX_LINE_LEN) :: msg ! output/error message
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type(Particle), pointer :: p => null()
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character(max_line_len) :: msg
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if (master) call header("BEGIN SIMULATION", 1)
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@ -285,7 +285,7 @@ CONTAINS
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integer(I8) :: itemp1, itemp2, itemp3, itemp4
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if( new_standard_gen<1 .or. new_standard_gen>n_RN_GEN ) then
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call expire( 0, 'RN_init_problem', &
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call expire( 'RN_init_problem', &
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& ' ***** ERROR: illegal index for built-in RN generator')
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endif
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@ -334,7 +334,7 @@ CONTAINS
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! double-check on number of bits in a long int
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if( bit_size(RN_SEED)<64 ) then
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call expire( 0, 'RN_init_problem', &
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call expire( 'RN_init_problem', &
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& ' ***** ERROR: <64 bits in long-int, can-t generate RN-s')
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endif
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itemp1 = 5_I8**25
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@ -342,7 +342,7 @@ CONTAINS
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itemp3 = ishft(2_I8**62-1_I8,1) + 1_I8
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itemp4 = itemp1*itemp2
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if( iand(itemp4,itemp3)/=8443747864978395601_I8 ) then
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call expire( 0, 'RN_init_problem', &
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call expire( 'RN_init_problem', &
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& ' ***** ERROR: can-t do 64-bit integer ops for RN-s')
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endif
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@ -502,8 +502,7 @@ CONTAINS
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!-------------------------------------------------------------------
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subroutine expire( i, c1, c2 )
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integer, intent(in) :: i
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subroutine expire( c1, c2 )
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character(len=*), intent(in) :: c1, c2
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write(*,*) ' ********** error: ',c1
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write(*,*) ' ********** error: ',c2
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@ -610,7 +609,7 @@ CONTAINS
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write(jtty,"(a,i20,z20)") " RN_MASK = ", RN_MASK, RN_MASK
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write(jtty,"(a,i20)") " RN_BITS = ", RN_BITS
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write(jtty,"(a,i20)") " RN_PERIOD = ", RN_PERIOD
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write(jtty,"(a,es20.14)") " RN_NORM = ", RN_NORM
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write(jtty,"(a,es20.13)") " RN_NORM = ", RN_NORM
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write(jtty,"(a)") " "
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do i = 1,10
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j = i
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@ -107,11 +107,7 @@ contains
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integer, intent(in) :: i_cycle
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integer :: i, j, k ! loop indices
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#ifdef MPI
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integer :: status(MPI_STATUS_SIZE) ! message status
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#endif
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integer :: ierr
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integer :: i, j, k ! loop indices
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integer(8) :: start ! starting index in local fission bank
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integer(8) :: finish ! ending index in local fission bank
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integer(8) :: total ! total sites in global fission bank
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@ -120,18 +116,22 @@ contains
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integer :: send_to_left ! # of bank sites to send/recv to or from left
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integer :: send_to_right ! # of bank sites to send/recv to or from right
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integer(8) :: sites_needed ! # of sites to be sampled
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integer(8) :: sites_remaining ! # of sites left in fission bank
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integer :: request ! communication request for sending sites
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integer :: request_left ! communication request for recv sites from left
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integer :: request_right ! communication request for recv sites from right
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real(8) :: p_sample ! probability of sampling a site
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real(8) :: t0, t1, t2, t3, t4
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type(Bank), allocatable :: &
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& temp_sites(:), & ! local array of extra sites on each node
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& left_bank(:), & ! bank sites to send/recv to or from left node
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& right_bank(:) ! bank sites to send/recv to or fram right node
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character(MAX_LINE_LEN) :: msg
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#ifdef MPI
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integer :: ierr
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integer :: status(MPI_STATUS_SIZE) ! message status
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integer :: request ! communication request for sending sites
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integer :: request_left ! communication request for recv sites from left
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integer :: request_right ! communication request for recv sites from right
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real(8) :: t0, t1, t2, t3, t4
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#endif
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msg = "Collecting number of fission sites..."
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call message(msg, 8)
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@ -214,8 +214,6 @@ contains
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type(Particle), pointer :: p
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integer :: i
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character(max_line_len) :: string
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type(Cell), pointer :: c => null()
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type(Surface), pointer :: s => null()
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type(Universe), pointer :: u => null()
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@ -478,7 +476,6 @@ contains
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type(Material), pointer :: mat
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integer :: i
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integer :: n_lines
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real(8) :: density
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character(max_line_len) :: string
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type(Nuclide), pointer :: nuc => null()
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@ -281,7 +281,6 @@ contains
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type(Reaction), pointer :: rxn
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real(8) :: awr ! atomic weight ratio of target
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real(8) :: phi ! azimuthal angle
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real(8) :: mu ! cosine of polar angle
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real(8) :: vx ! velocity of neutron in x-direction
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real(8) :: vy ! velocity of neutron in y-direction
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@ -653,7 +652,6 @@ contains
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real(8) :: E_cm ! outgoing energy in center-of-mass
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real(8) :: u,v,w ! direction cosines
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real(8) :: Q ! Q-value of reaction
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character(MAX_LINE_LEN) :: msg ! error message
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! copy energy of neutron
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E_in = p % E
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@ -724,7 +722,6 @@ contains
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real(8) :: E_cm ! outgoing energy in center-of-mass
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real(8) :: u,v,w ! direction cosines
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real(8) :: Q ! Q-value of reaction
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character(MAX_LINE_LEN) :: msg ! error message
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! copy energy of neutron
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E_in = p % E
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@ -24,15 +24,16 @@ contains
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integer, intent(in) :: i_cycle ! index of current cycle
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integer(8) :: total_bank
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integer :: n
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integer(8) :: total_bank ! total number of source sites
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integer :: n ! active cycle number
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real(8) :: kcoll ! keff collision estimator
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real(8), save :: k1 = 0. ! accumulated keff
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real(8), save :: k2 = 0. ! accumulated keff**2
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real(8) :: std ! stdev of keff over active cycles
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character(MAX_LINE_LEN) :: msg ! output/error message
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#ifdef MPI
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integer :: ierr
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real(8) :: kcoll ! keff collision estimator
|
||||
real(8) :: ktemp ! MPI-reduced keff and stdev
|
||||
real(8), save :: k1 = 0. ! accumulated keff
|
||||
real(8), save :: k2 = 0. ! accumulated keff**2
|
||||
real(8) :: std ! stdev of keff over active cycles
|
||||
character(max_line_len) :: msg
|
||||
#endif
|
||||
|
||||
msg = "Calculate cycle keff..."
|
||||
call message(msg, 8)
|
||||
|
|
@ -101,7 +102,7 @@ contains
|
|||
real(8) :: E ! energy of particle
|
||||
real(8) :: val ! value to score
|
||||
real(8) :: Sigma ! macroscopic cross section of reaction
|
||||
character(max_line_len) :: msg ! output/error message
|
||||
character(MAX_LINE_LEN) :: msg ! output/error message
|
||||
type(Cell), pointer :: c => null()
|
||||
type(Tally), pointer :: t => null()
|
||||
|
||||
|
|
|
|||
|
|
@ -137,10 +137,10 @@ contains
|
|||
! ADD_BANK_SITES
|
||||
!===============================================================================
|
||||
|
||||
subroutine add_bank_sites(p, table, n)
|
||||
subroutine add_bank_sites(p, nuc, n)
|
||||
|
||||
type(Particle), pointer :: p
|
||||
type(Nuclide), pointer :: table
|
||||
type(Nuclide), pointer :: nuc
|
||||
integer, intent(in) :: n
|
||||
|
||||
integer :: i
|
||||
|
|
|
|||
|
|
@ -272,14 +272,12 @@ contains
|
|||
character(*), intent(in) :: string
|
||||
real(8) :: num
|
||||
|
||||
integer :: index_decimal ! index of decimal point
|
||||
integer :: index_exponent ! index of exponent character
|
||||
integer :: w ! total field width
|
||||
integer :: d ! number of digits to right of decimal point
|
||||
integer :: ioError
|
||||
|
||||
character(8) :: fmt ! format for reading string
|
||||
character(MAX_LINE_LEN) :: msg ! error message
|
||||
integer :: index_decimal ! index of decimal point
|
||||
integer :: index_exponent ! index of exponent character
|
||||
integer :: w ! total field width
|
||||
integer :: d ! number of digits to right of decimal point
|
||||
integer :: ioError
|
||||
character(8) :: fmt ! format for reading string
|
||||
|
||||
! Determine total field width
|
||||
w = len_trim(string)
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue