mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 06:05:58 -04:00
Added clarification regarding sampling fission reactions.
This commit is contained in:
parent
b284c39051
commit
1f66f140a4
1 changed files with 2 additions and 1 deletions
|
|
@ -797,7 +797,8 @@ second-chance fission, etc. An ACE table either lists the partial fission
|
|||
reactions with secondary energy distributions for each one, or a total fission
|
||||
reaction with a single secondary energy distribution.
|
||||
|
||||
When a fission reaction is sampled in OpenMC, the following algorithm is used to
|
||||
When a fission reaction is sampled in OpenMC (either total fission or, if data
|
||||
exists, first- or second-chance fission), the following algorithm is used to
|
||||
create and store fission sites for the following generation. First, the average
|
||||
number of prompt and delayed neutrons must be determined to decide whether the
|
||||
secondary neutrons will be prompt or delayed. This is important because delayed
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue