mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-27 21:55:41 -04:00
merged with upstream/develop
This commit is contained in:
commit
9035f6951e
9 changed files with 137 additions and 3 deletions
|
|
@ -902,6 +902,19 @@ displayed. This element takes the following attributes:
|
|||
|
||||
*Default*: 5
|
||||
|
||||
``<create_fission_neutrons>`` Element
|
||||
-------------------------------------
|
||||
|
||||
The ``<create_fission_neutrons>`` element indicates whether fission neutrons
|
||||
should be created or not. If this element is set to "true", fission neutrons
|
||||
will be created; otherwise the fission is treated as capture and no fission
|
||||
neutron will be created. Note that this option is only applied to fixed source
|
||||
calculation. For eigenvalue calculation, fission will always be treated as real
|
||||
fission.
|
||||
|
||||
*Default*: true
|
||||
|
||||
|
||||
``<volume_calc>`` Element
|
||||
-------------------------
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue