crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-27 13:45:36 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

Got rid of unused Isotope derived type.

Browse source
This commit is contained in:
Paul Romano 2011-08-01 17:00:59 -04:00
parent 36cb96895a
commit b1c213d5ec
2 changed files with 0 additions and 14 deletions
Download patch file Download diff file Expand all files Collapse all files

1
src/global.f90
View file

@ -20,7 +20,6 @@ module global
type(Lattice), allocatable, target :: lattices(:)
type(Surface), allocatable, target :: surfaces(:)
type(Material), allocatable, target :: materials(:)
type(Isotope), allocatable, target :: isotopes(:)
type(xsData), allocatable, target :: xsdatas(:)
type(Tally), allocatable, target :: tallies(:)
type(Tally), allocatable, target :: tallies_global(:)

13
src/types.f90
View file

@ -143,19 +143,6 @@ module types
type(TallyScore), allocatable :: score(:,:,:)
end type Tally
!===============================================================================
! ISOTOPE describes an isotope, e.g. U-235, within a material. Note that two
! separate variables must be used for the same isotope in two different
! materials since they will generally have different densities
!===============================================================================
type Isotope
integer :: uid ! unique identifier
integer :: zaid ! ZAID, e.g. 92235
character(3) :: xs ! cross section identifier, e.g. 70c
real(8) :: density ! density in atom/b-cm
end type Isotope
!===============================================================================
! MATERIAL describes a material by its constituent isotopes
!===============================================================================