mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-27 13:45:36 -04:00
Changed isotropic in lab scattering tag to iso-in-lab
This commit is contained in:
parent
0a0c4c4d5f
commit
a11ccce8a3
3 changed files with 9 additions and 9 deletions
|
|
@ -1138,12 +1138,12 @@ Each ``material`` element can have the following attributes or sub-elements:
|
|||
|
||||
An optional attribute/sub-element for each nuclide is ``scattering``. This
|
||||
attribute may be set to "ace" to use the scattering laws specified in the
|
||||
ACE files (default). Alternatively, when set to "lab", the ACE scattering
|
||||
laws are used to sample the outgoing energy but an isotropic-in-lab
|
||||
distribution is used to sample the outgoing angle at each scattering
|
||||
interaction. The ``scattering`` attribute may be most useful when using
|
||||
OpenMC to compute multi-group cross-sections for deterministic transport
|
||||
codes and to quantify the effects of anisotropic scattering.
|
||||
ACE files (default). Alternatively, when set to "iso-in-lab", the ACE
|
||||
scattering laws are used to sample the outgoing energy but an
|
||||
isotropic-in-lab distribution is used to sample the outgoing angle at each
|
||||
scattering interaction. The ``scattering`` attribute may be most useful
|
||||
when using OpenMC to compute multi-group cross-sections for deterministic
|
||||
transport codes and to quantify the effects of anisotropic scattering.
|
||||
|
||||
*Default*: None
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue