mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-27 13:45:36 -04:00
added documentation for fission box source
This commit is contained in:
parent
6b4fbd7877
commit
a3df011e7c
1 changed files with 6 additions and 0 deletions
|
|
@ -311,6 +311,12 @@ attributes/sub-elements:
|
|||
parallelepiped and the last three of which specify the upper-right
|
||||
corner. Source sites are sampled uniformly through that parallelepiped.
|
||||
|
||||
To filter a "box" spatial distribution by fissionable material, specify
|
||||
"fission" tag instead of "box". The ``parameters`` should be given as six
|
||||
real numbers, the first three of which specify the lower-left corner of a
|
||||
parallelepiped and the last three of which specify the upper-right
|
||||
corner. Source sites are sampled uniformly through that parallelepiped.
|
||||
|
||||
For a "point" spatial distribution, ``parameters`` should be given as
|
||||
three real numbers which specify the (x,y,z) location of an isotropic
|
||||
point source
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue