OpenMC/docs/source/pythonapi
Andrew Johnson 2cfbb21858
Provide abstract FissionYieldHelper class
API used by the Operator:
- generate_tallies
- weighted_yields [abstract]
- update_nuclides_from_operator
- unpack

generate_tallies and unpack are empty methods, provided
so that a consistent API can be found on helpers
with tallies.

Sorts nuclides into two dictionaries: those with a single
set of fission yields, and those with multiple sets.
The former can is exposed through the
constant_yields property, returning a copy of the fission
yield dictionary {parent: {product: yield}}

The Operator now looks for/uses the weighted_yields and
update_nuclides_from_operator methods instead of the old
compute_yields and set_fissionable_nuclides methods
2019-08-13 15:30:14 -05:00
..
base.rst Change Python Mesh class to RegularMesh 2019-06-07 08:51:09 -04:00
capi.rst Fix name of capi.RegularMesh in documentation 2019-06-14 12:13:34 -05:00
data.rst Respond to @nelsonag comments on #1271 2019-07-01 07:09:10 -05:00
deplete.rst Provide abstract FissionYieldHelper class 2019-08-13 15:30:14 -05:00
examples.rst Respond to @wbinventor comments on #852 2017-04-10 07:16:17 -05:00
index.rst Improve display of Python API in generated HTML documentation 2019-06-14 14:35:39 -05:00
mgxs.rst Get GROUP_STRUCTURES to show up in documentation 2018-11-07 07:36:08 -06:00
model.rst Add opemc.model.pin to python api documentation 2019-07-09 20:25:34 -05:00
openmoc.rst Respond to comments on #850 2017-04-05 11:13:21 -05:00
stats.rst Missing one review comment, and followed style for generic normal distribution from uniform distribuion 2018-12-13 15:37:47 +00:00