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Cut down on print_nuclide routine

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This commit is contained in:
Paul Romano 2016-01-22 08:59:54 -06:00
parent 615d733cc8
commit 7bd0b2fe97
1 changed files with 3 additions and 40 deletions
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43
src/output.F90
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@ -322,14 +322,8 @@ contains
integer :: i ! loop index over nuclides
integer :: unit_ ! unit to write to
integer :: size_total ! memory used by nuclide (bytes)
integer :: size_angle_total ! total memory used for angle dist. (bytes)
integer :: size_energy_total ! total memory used for energy dist. (bytes)
integer :: size_xs ! memory used for cross-sections (bytes)
integer :: size_angle ! memory used for an angle distribution (bytes)
integer :: size_energy ! memory used for a energy distributions (bytes)
integer :: size_urr ! memory used for probability tables (bytes)
character(11) :: law ! secondary energy distribution law
type(UrrData), pointer :: urr
! set default unit for writing information
@ -340,8 +334,6 @@ contains
end if
! Initialize totals
size_angle_total = 0
size_energy_total = 0
size_urr = 0
size_xs = 0
@ -356,36 +348,15 @@ contains
write(unit_,*) ' # of reactions = ' // trim(to_str(nuc % n_reaction))
! Information on each reaction
write(unit_,*) ' Reaction Q-value COM Law IE size(angle) size(energy)'
write(unit_,*) ' Reaction Q-value COM IE'
do i = 1, nuc % n_reaction
associate (rxn => nuc % reactions(i))
!!$ ! Determine size of angle distribution
!!$ if (rxn % has_angle_dist) then
!!$ size_angle = rxn % adist % n_energy * 16 + size(rxn % adist % data) * 8
!!$ else
!!$ size_angle = 0
!!$ end if
size_angle = 0
!!$ ! Determine size of energy distribution and law
!!$ if (rxn % has_energy_dist) then
!!$ size_energy = size(rxn % edist % data) * 8
!!$ law = to_str(rxn % edist % law)
!!$ else
!!$ size_energy = 0
!!$ law = 'None'
!!$ end if
size_energy = 0
law = 'None'
write(unit_,'(3X,A11,1X,F8.3,3X,L1,3X,A4,1X,I6,1X,I11,1X,I11)') &
write(unit_,'(3X,A11,1X,F8.3,3X,L1,3X,I6)') &
reaction_name(rxn % MT), rxn % Q_value, rxn % scatter_in_cm, &
law(1:4), rxn % threshold, size_angle, size_energy
rxn % threshold
! Accumulate data size
size_xs = size_xs + (nuc % n_grid - rxn%threshold + 1) * 8
size_angle_total = size_angle_total + size_angle
size_energy_total = size_energy_total + size_energy
end associate
end do
@ -411,19 +382,11 @@ contains
size_urr = urr % n_energy * (urr % n_prob * 6 + 1) * 8
end if
! Calculate total memory
size_total = size_xs + size_angle_total + size_energy_total + size_urr
! Write memory used
write(unit_,*) ' Memory Requirements'
write(unit_,*) ' Cross sections = ' // trim(to_str(size_xs)) // ' bytes'
write(unit_,*) ' Secondary angle distributions = ' // &
trim(to_str(size_angle_total)) // ' bytes'
write(unit_,*) ' Secondary energy distributions = ' // &
trim(to_str(size_energy_total)) // ' bytes'
write(unit_,*) ' Probability Tables = ' // &
trim(to_str(size_urr)) // ' bytes'
write(unit_,*) ' Total = ' // trim(to_str(size_total)) // ' bytes'
! Blank line at end of nuclide
write(unit_,*)