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Updated print_nuclide with more information on memory requirements.

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This commit is contained in:
Paul Romano 2012-07-04 21:54:11 -04:00
parent 2eb2e48fb4
commit 10fcba4561
1 changed files with 34 additions and 14 deletions
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48
src/output.F90
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@ -779,12 +779,15 @@ contains
type(Nuclide), pointer :: nuc
integer, optional :: unit
integer :: i ! loop index over nuclides
integer :: unit_ ! unit to write to
integer :: size_total ! memory used by nuclide (bytes)
integer :: size_xs ! memory used for cross-sections (bytes)
integer :: size_angle ! memory used for angle distributions (bytes)
integer :: size_energy ! memory used for energy distributions (bytes)
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)
type(Reaction), pointer :: rxn => null()
type(UrrData), pointer :: urr => null()
@ -795,9 +798,13 @@ contains
unit_ = OUTPUT_UNIT
end if
! Initialize totals
size_angle_total = 0
size_energy_total = 0
size_urr = 0
! Determine size of cross-sections
size_xs = (5 + nuc % n_reaction) * nuc % n_grid * 8
size_total = size_xs
! Basic nuclide information
write(unit_,*) 'Nuclide ' // trim(nuc % name)
@ -808,12 +815,10 @@ contains
write(unit_,*) ' Fissionable = ', nuc % fissionable
write(unit_,*) ' # of fission reactions = ' // trim(to_str(nuc % n_fission))
write(unit_,*) ' # of reactions = ' // trim(to_str(nuc % n_reaction))
write(unit_,*) ' Size of cross sections = ' // trim(to_str(&
size_xs)) // ' bytes'
! Information on each reaction
write(unit_,*) ' Reaction Q-value Mult IE size(angle) size(energy)'
do i = 1, nuc % n_reaction
! Information on each reaction
rxn => nuc % reactions(i)
! Determine size of angle distribution
@ -835,10 +840,12 @@ contains
rxn % IE, size_angle, size_energy
! Accumulate data size
size_total = size_total + size_angle + size_energy
size_angle_total = size_angle_total + size_angle
size_energy_total = size_energy_total + size_energy
end do
! Write information about URR probability tables
size_urr = 0
if (nuc % urr_present) then
urr => nuc % urr_data
write(unit_,*) ' Unresolved resonance probability table:'
@ -850,11 +857,24 @@ contains
write(unit_,*) ' Multiply by smooth? ', urr % multiply_smooth
write(unit_,*) ' Min energy = ', trim(to_str(urr % energy(1)))
write(unit_,*) ' Max energy = ', trim(to_str(urr % energy(urr % n_energy)))
! Calculate memory used by probability tables and add to total
size_urr = urr % n_energy * (urr % n_prob * 6 + 1) * 8
end if
! Write total memory used
write(unit_,*) ' Total memory used = ' // trim(to_str(size_total)) &
// ' bytes'
! 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_,*)