mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 22:26:08 -04:00
Added ability to list 'total' in <nuclides> element.
This commit is contained in:
parent
7af2cfcc63
commit
5eebbc0a23
1 changed files with 6 additions and 0 deletions
|
|
@ -1346,6 +1346,12 @@ contains
|
|||
! Any other case, e.g. <nuclides>U-235 Pu-239</nuclides>
|
||||
allocate(t % nuclide_bins(n_words))
|
||||
do j = 1, n_words
|
||||
! Check if total material was specified
|
||||
if (words(j) == 'total') then
|
||||
t % nuclide_bins(j) % scalar = -1
|
||||
cycle
|
||||
end if
|
||||
|
||||
! Check if xs specifier was given
|
||||
if (ends_with(words(j), 'c')) then
|
||||
word = words(j)
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue