mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-29 06:35:48 -04:00
Remove n_reaction and n_product attributes in HDF5 data. Add /nuclide/reactions/
group, change reaction group names (reaction_MT).
This commit is contained in:
parent
3d68c07625
commit
8952865c09
7 changed files with 70 additions and 37 deletions
|
|
@ -12,15 +12,16 @@ Incident Neutron Data
|
|||
**/<nuclide name>/**
|
||||
|
||||
:Attributes: - **Z** (*int*) -- Atomic number
|
||||
- **A** (*int*) -- Mass number
|
||||
- **metastable** (*int*) -- Metastable state
|
||||
- **A** (*int*) -- Mass number. For a natural element, A=0 is given.
|
||||
- **metastable** (*int*) -- Metastable state (0=ground, 1=first
|
||||
excited, etc.)
|
||||
- **atomic_weight_ratio** (*double*) -- Mass in units of neutron masses
|
||||
- **temperature** (*double*) -- Temperature in MeV
|
||||
- **n_reaction** (*int*) -- Number of reactions
|
||||
|
||||
:Datasets: - **energy** (*double[]*) -- Energy points at which cross sections are tabulated
|
||||
|
||||
**/<nuclide name>/reaction_<i>/**
|
||||
**/<nuclide name>/reactions/reaction_<mt>/**
|
||||
|
||||
:Attributes: - **mt** (*int*) -- ENDF MT reaction number
|
||||
- **label** (*char[]*) -- Name of the reaction
|
||||
|
|
@ -33,7 +34,7 @@ Incident Neutron Data
|
|||
|
||||
:Datasets: - **xs** (*double[]*) -- Cross section values tabulated against the nuclide energy grid
|
||||
|
||||
**/<nuclide name>/reaction_<i>/product_<j>/**
|
||||
**/<nuclide name>/reactions/reaction_<mt>/product_<j>/**
|
||||
|
||||
Reaction product data is described in :ref:`product`.
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue