mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-25 04:25:29 -04:00
Add ConstantFissionYieldHelper concrete class
Given a requested energy, will take fission yields from that energy on all nuclides and hold them as constant throughout the simulation. If the requested energy is not found for a specific nuclide, then the closest energy is used. The default is to take the thermal 0.0253 eV yields. This is now the helper attached to the Operator. The user can select what energy of yields they would like to use.
This commit is contained in:
parent
2cfbb21858
commit
d8b9f5db54
5 changed files with 99 additions and 225 deletions
|
|
@ -78,6 +78,7 @@ data, such as number densities and reaction rates for each material.
|
|||
|
||||
AtomNumber
|
||||
ChainFissionHelper
|
||||
ConstantFissionYieldHelper
|
||||
DirectReactionRateHelper
|
||||
OperatorResult
|
||||
ReactionRates
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue