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Merge pull request #736 from QingmingHe/no_nu_settings

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No nu option like nonu in MCNP
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Paul Romano 2016-10-13 08:36:11 -05:00 • committed by GitHub
commit 2aec3363f0
9 changed files with 137 additions and 3 deletions
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13
docs/source/usersguide/input.rst
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@ -872,6 +872,19 @@ displayed. This element takes the following attributes:
*Default*: 5
``<create_fission_neutrons>`` Element
-------------------------------------
The ``<create_fission_neutrons>`` element indicates whether fission neutrons
should be created or not. If this element is set to "true", fission neutrons
will be created; otherwise the fission is treated as capture and no fission
neutron will be created. Note that this option is only applied to fixed source
calculation. For eigenvalue calculation, fission will always be treated as real
fission.
*Default*: true
``<volume_calc>`` Element
-------------------------