diff --git a/src/initialize.F90 b/src/initialize.F90 index f05b4f2b99..2bcf2e01f2 100644 --- a/src/initialize.F90 +++ b/src/initialize.F90 @@ -4,7 +4,7 @@ module initialize use constants use dict_header, only: DictIntInt, ElemKeyValueII use set_header, only: SetInt - use energy_grid, only: logarithmic_grid, grid_method ! , unionized_grid + use energy_grid, only: logarithmic_grid, grid_method use error, only: fatal_error, warning use geometry, only: neighbor_lists, count_instance, calc_offsets, & maximum_levels diff --git a/src/mgxs_header.F90 b/src/mgxs_header.F90 index 5947d2562d..9409398b3e 100644 --- a/src/mgxs_header.F90 +++ b/src/mgxs_header.F90 @@ -28,7 +28,6 @@ module mgxs_header contains procedure(mgxs_init_file_), deferred :: init_file ! Initialize the data - procedure(mgxs_print_), deferred :: print ! Writes object info procedure(mgxs_get_xs_), deferred :: get_xs ! Get the requested xs procedure(mgxs_combine_), deferred :: combine ! initializes object ! Sample the outgoing energy from a fission event @@ -63,12 +62,6 @@ module mgxs_header integer, intent(in) :: max_order ! Maximum requested order end subroutine mgxs_init_file_ - subroutine mgxs_print_(this, unit) - import Mgxs - class(Mgxs),intent(in) :: this - integer, optional, intent(in) :: unit - end subroutine mgxs_print_ - pure function mgxs_get_xs_(this,xstype,gin,gout,uvw,mu) result(xs) import Mgxs class(Mgxs), intent(in) :: this @@ -149,7 +142,6 @@ module mgxs_header contains procedure :: init_file => mgxsiso_init_file ! Initialize Nuclidic MGXS Data - procedure :: print => mgxsiso_print ! Writes nuclide info procedure :: get_xs => mgxsiso_get_xs ! Gets Size of Data w/in Object procedure :: combine => mgxsiso_combine ! inits object procedure :: sample_fission_energy => mgxsiso_sample_fission_energy @@ -180,7 +172,6 @@ module mgxs_header contains procedure :: init_file => mgxsang_init_file ! Initialize Nuclidic MGXS Data - procedure :: print => mgxsang_print ! Writes nuclide info procedure :: get_xs => mgxsang_get_xs ! Gets Size of Data w/in Object procedure :: combine => mgxsang_combine ! inits object procedure :: sample_fission_energy => mgxsang_sample_fission_energy @@ -951,159 +942,6 @@ module mgxs_header end subroutine mgxsang_init_file -!=============================================================================== -! MGXS*_PRINT displays information about a continuous-energy neutron -! cross_section table and its reactions and secondary angle/energy distributions -!=============================================================================== - - subroutine mgxs_print(this, unit_) - class(Mgxs), intent(in) :: this - integer, intent(in) :: unit_ - - character(MAX_LINE_LEN) :: temp_str - - ! Basic nuclide information - write(unit_,*) 'MGXS Entry: ' // trim(this % name) - if (this % awr > ZERO) then - write(unit_,*) ' AWR = ' // trim(to_str(this % awr)) - end if - if (this % kT > ZERO) then - write(unit_,*) ' kT = ' // trim(to_str(this % kT)) - end if - if (this % scatt_type == ANGLE_LEGENDRE) then - temp_str = "Legendre" - write(unit_,*) ' Scattering Type = ' // trim(temp_str) - select type(this) - type is (MgxsIso) - temp_str = to_str(size(this % scatter % dist(1) % data,dim=1) - 1) - end select - write(unit_,*) ' Scattering Order = ' // trim(temp_str) - else if (this % scatt_type == ANGLE_HISTOGRAM) then - temp_str = "Histogram" - write(unit_,*) ' Scattering Type = ' // trim(temp_str) - select type(this) - type is (MgxsIso) - temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) - end select - write(unit_,*) ' Num. Distribution Bins = ' // trim(temp_str) - else if (this % scatt_type == ANGLE_TABULAR) then - temp_str = "Tabular" - write(unit_,*) ' Scattering Type = ' // trim(temp_str) - select type(this) - type is (MgxsIso) - temp_str = to_str(size(this % scatter % dist(1) % data,dim=1)) - end select - write(unit_,*) ' Num. Distribution Points = ' // trim(temp_str) - end if - write(unit_,*) ' Fissionable = ', this % fissionable - - end subroutine mgxs_print - - subroutine mgxsiso_print(this, unit) - - class(MgxsIso), intent(in) :: this - integer, optional, intent(in) :: unit - - integer :: unit_ ! unit to write to - integer :: size_total, size_scattmat, size_mgxs - integer :: gin - - ! set default unit for writing information - if (present(unit)) then - unit_ = unit - else - unit_ = OUTPUT_UNIT - end if - - ! Write Basic Nuclide Information - call mgxs_print(this, unit_) - - ! Determine size of mgxs and scattering matrices - size_scattmat = 0 - do gin = 1, size(this % scatter % energy) - size_scattmat = size_scattmat + & - 2 * size(this % scatter % energy(gin) % data) + & - size(this % scatter % dist(gin) % data) - end do - size_scattmat = size_scattmat + size(this % scatter % scattxs) - size_scattmat = size_scattmat * 8 - - size_mgxs = size(this % total) + size(this % absorption) + & - size(this % nu_fission) + size(this % k_fission) + & - size(this % fission) + size(this % chi) - size_mgxs = size_mgxs * 8 - - ! Calculate total memory - size_total = size_scattmat + size_mgxs - - ! Write memory used - write(unit_,*) ' Memory Requirements' - write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes' - write(unit_,*) ' Scattering Matrices = ' // & - trim(to_str(size_scattmat)) // ' bytes' - write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes' - - ! Blank line at end of nuclide - write(unit_,*) - - end subroutine mgxsiso_print - - subroutine mgxsang_print(this, unit) - - class(MgxsAngle), intent(in) :: this - integer, optional, intent(in) :: unit - - integer :: unit_ ! unit to write to - integer :: size_total, size_scattmat, size_mgxs - integer :: ipol, iazi, gin - - ! set default unit for writing information - if (present(unit)) then - unit_ = unit - else - unit_ = OUTPUT_UNIT - end if - - ! Write Basic Nuclide Information - call mgxs_print(this, unit_) - - write(unit_,*) ' # of Polar Angles = ' // trim(to_str(this % n_pol)) - write(unit_,*) ' # of Azimuthal Angles = ' // trim(to_str(this % n_azi)) - - ! Determine size of mgxs and scattering matrices - size_scattmat = 0 - do ipol = 1, this % n_pol - do iazi = 1, this % n_azi - do gin = 1, size(this % scatter(iazi, ipol) % obj % energy) - size_scattmat = size_scattmat + & - 2 * size(this % scatter(iazi, ipol) % obj % energy(gin) % data) + & - size(this % scatter(iazi, ipol) % obj % dist(gin) % data) - end do - size_scattmat = size_scattmat + & - size(this % scatter(iazi, ipol) % obj % scattxs) - end do - end do - size_scattmat = size_scattmat * 8 - - size_mgxs = size(this % total) + size(this % absorption) + & - size(this % nu_fission) + size(this % k_fission) + & - size(this % fission) + size(this % chi) - size_mgxs = size_mgxs * 8 - - ! Calculate total memory - size_total = size_scattmat + size_mgxs - - ! Write memory used - write(unit_,*) ' Memory Requirements' - write(unit_,*) ' Cross sections = ' // trim(to_str(size_mgxs)) // ' bytes' - write(unit_,*) ' Scattering Matrices = ' // & - trim(to_str(size_scattmat)) // ' bytes' - write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes' - - ! Blank line at end of nuclide - write(unit_,*) - end subroutine mgxsang_print - !=============================================================================== ! MGXS*_GET_XS returns the requested data cross section data !===============================================================================