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Remove comment and mgxs print routines
This commit is contained in:
Paul Romano
parent
3d29075022
commit
c4357ba177
2 changed files with 1 additions and 163 deletions
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@ -4,7 +4,7 @@ module initialize
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use constants
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use dict_header, only: DictIntInt, ElemKeyValueII
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use set_header, only: SetInt
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use energy_grid, only: logarithmic_grid, grid_method ! , unionized_grid
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use energy_grid, only: logarithmic_grid, grid_method
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use error, only: fatal_error, warning
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use geometry, only: neighbor_lists, count_instance, calc_offsets, &
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maximum_levels
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@ -28,7 +28,6 @@ module mgxs_header
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contains
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procedure(mgxs_init_file_), deferred :: init_file ! Initialize the data
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procedure(mgxs_print_), deferred :: print ! Writes object info
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procedure(mgxs_get_xs_), deferred :: get_xs ! Get the requested xs
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procedure(mgxs_combine_), deferred :: combine ! initializes object
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! Sample the outgoing energy from a fission event
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@ -63,12 +62,6 @@ module mgxs_header
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integer, intent(in) :: max_order ! Maximum requested order
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end subroutine mgxs_init_file_
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subroutine mgxs_print_(this, unit)
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import Mgxs
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class(Mgxs),intent(in) :: this
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integer, optional, intent(in) :: unit
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end subroutine mgxs_print_
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pure function mgxs_get_xs_(this,xstype,gin,gout,uvw,mu) result(xs)
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import Mgxs
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class(Mgxs), intent(in) :: this
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@ -149,7 +142,6 @@ module mgxs_header
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contains
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procedure :: init_file => mgxsiso_init_file ! Initialize Nuclidic MGXS Data
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procedure :: print => mgxsiso_print ! Writes nuclide info
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procedure :: get_xs => mgxsiso_get_xs ! Gets Size of Data w/in Object
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procedure :: combine => mgxsiso_combine ! inits object
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procedure :: sample_fission_energy => mgxsiso_sample_fission_energy
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@ -180,7 +172,6 @@ module mgxs_header
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contains
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procedure :: init_file => mgxsang_init_file ! Initialize Nuclidic MGXS Data
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procedure :: print => mgxsang_print ! Writes nuclide info
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procedure :: get_xs => mgxsang_get_xs ! Gets Size of Data w/in Object
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procedure :: combine => mgxsang_combine ! inits object
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procedure :: sample_fission_energy => mgxsang_sample_fission_energy
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@ -951,159 +942,6 @@ module mgxs_header
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end subroutine mgxsang_init_file
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!===============================================================================
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! MGXS*_PRINT displays information about a continuous-energy neutron
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! cross_section table and its reactions and secondary angle/energy distributions
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!===============================================================================
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subroutine mgxs_print(this, unit_)
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class(Mgxs), intent(in) :: this
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integer, intent(in) :: unit_
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character(MAX_LINE_LEN) :: temp_str
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! Basic nuclide information
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write(unit_,*) 'MGXS Entry: ' // trim(this % name)
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if (this % awr > ZERO) then
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write(unit_,*) ' AWR = ' // trim(to_str(this % awr))
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end if
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if (this % kT > ZERO) then
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write(unit_,*) ' kT = ' // trim(to_str(this % kT))
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end if
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if (this % scatt_type == ANGLE_LEGENDRE) then
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temp_str = "Legendre"
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write(unit_,*) ' Scattering Type = ' // trim(temp_str)
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select type(this)
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type is (MgxsIso)
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temp_str = to_str(size(this % scatter % dist(1) % data,dim=1) - 1)
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end select
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write(unit_,*) ' Scattering Order = ' // trim(temp_str)
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else if (this % scatt_type == ANGLE_HISTOGRAM) then
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temp_str = "Histogram"
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write(unit_,*) ' Scattering Type = ' // trim(temp_str)
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select type(this)
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type is (MgxsIso)
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temp_str = to_str(size(this % scatter % dist(1) % data,dim=1))
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end select
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write(unit_,*) ' Num. Distribution Bins = ' // trim(temp_str)
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else if (this % scatt_type == ANGLE_TABULAR) then
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temp_str = "Tabular"
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write(unit_,*) ' Scattering Type = ' // trim(temp_str)
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select type(this)
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type is (MgxsIso)
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temp_str = to_str(size(this % scatter % dist(1) % data,dim=1))
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end select
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write(unit_,*) ' Num. Distribution Points = ' // trim(temp_str)
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end if
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write(unit_,*) ' Fissionable = ', this % fissionable
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end subroutine mgxs_print
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subroutine mgxsiso_print(this, unit)
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class(MgxsIso), intent(in) :: this
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integer, optional, intent(in) :: unit
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integer :: unit_ ! unit to write to
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integer :: size_total, size_scattmat, size_mgxs
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integer :: gin
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! set default unit for writing information
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if (present(unit)) then
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unit_ = unit
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else
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unit_ = OUTPUT_UNIT
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end if
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! Write Basic Nuclide Information
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call mgxs_print(this, unit_)
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! Determine size of mgxs and scattering matrices
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size_scattmat = 0
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do gin = 1, size(this % scatter % energy)
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size_scattmat = size_scattmat + &
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2 * size(this % scatter % energy(gin) % data) + &
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size(this % scatter % dist(gin) % data)
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end do
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size_scattmat = size_scattmat + size(this % scatter % scattxs)
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size_scattmat = size_scattmat * 8
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size_mgxs = size(this % total) + size(this % absorption) + &
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size(this % nu_fission) + size(this % k_fission) + &
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size(this % fission) + size(this % chi)
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size_mgxs = size_mgxs * 8
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! Calculate total memory
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size_total = size_scattmat + size_mgxs
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! Write memory used
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write(unit_,*) ' Memory Requirements'
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write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes'
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write(unit_,*) ' Scattering Matrices = ' // &
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trim(to_str(size_scattmat)) // ' bytes'
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write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes'
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! Blank line at end of nuclide
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write(unit_,*)
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end subroutine mgxsiso_print
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subroutine mgxsang_print(this, unit)
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class(MgxsAngle), intent(in) :: this
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integer, optional, intent(in) :: unit
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integer :: unit_ ! unit to write to
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integer :: size_total, size_scattmat, size_mgxs
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integer :: ipol, iazi, gin
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! set default unit for writing information
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if (present(unit)) then
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unit_ = unit
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else
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unit_ = OUTPUT_UNIT
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end if
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! Write Basic Nuclide Information
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call mgxs_print(this, unit_)
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write(unit_,*) ' # of Polar Angles = ' // trim(to_str(this % n_pol))
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write(unit_,*) ' # of Azimuthal Angles = ' // trim(to_str(this % n_azi))
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! Determine size of mgxs and scattering matrices
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size_scattmat = 0
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do ipol = 1, this % n_pol
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do iazi = 1, this % n_azi
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do gin = 1, size(this % scatter(iazi, ipol) % obj % energy)
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size_scattmat = size_scattmat + &
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2 * size(this % scatter(iazi, ipol) % obj % energy(gin) % data) + &
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size(this % scatter(iazi, ipol) % obj % dist(gin) % data)
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end do
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size_scattmat = size_scattmat + &
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size(this % scatter(iazi, ipol) % obj % scattxs)
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end do
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end do
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size_scattmat = size_scattmat * 8
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size_mgxs = size(this % total) + size(this % absorption) + &
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size(this % nu_fission) + size(this % k_fission) + &
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size(this % fission) + size(this % chi)
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size_mgxs = size_mgxs * 8
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! Calculate total memory
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size_total = size_scattmat + size_mgxs
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! Write memory used
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write(unit_,*) ' Memory Requirements'
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write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes'
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write(unit_,*) ' Scattering Matrices = ' // &
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trim(to_str(size_scattmat)) // ' bytes'
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write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes'
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! Blank line at end of nuclide
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write(unit_,*)
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end subroutine mgxsang_print
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!===============================================================================
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! MGXS*_GET_XS returns the requested data cross section data
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!===============================================================================
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