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Convert ACE data from MeV to eV

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This commit is contained in:
Paul Romano 2016-10-24 18:44:51 -05:00
parent b50a9db628
commit 6da9f16d29
44 changed files with 219 additions and 212 deletions
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8
docs/source/io_formats/mgxs_library.rst
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@ -30,7 +30,7 @@ MGXS Library Specification
:Attributes: - **groups** (*int*) -- Number of energy groups
- **group structure** (*double[]*) -- Monotonically increasing
list of group boundaries, in units of MeV. The length of this
list of group boundaries, in units of eV. The length of this
array should be the number of groups plus 1.
**/<library name>/**
@ -77,8 +77,8 @@ data for the nuclide or material that it represents.
**/<library name>/kTs/**
:Datasets:
- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
:Datasets:
- **<TTT>K** (*double*) -- kT values (in eV) for each temperature
TTT (in Kelvin), rounded to the nearest integer
**/<library name>/<TTT>K/**
@ -161,4 +161,4 @@ Data specific to neutron scattering for the temperature <TTT>K
1.0) will be assumed.
The pre-flattened array is shapes consistent with `scatter_matrix`
except the "[Order]" dimension in `scatter_shape` is ignored since
this data is assumed isotropic.
this data is assumed isotropic.

18
docs/source/io_formats/nuclear_data.rst
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@ -27,14 +27,14 @@ temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Datasets:
- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
- **<TTT>K** (*double*) -- kT values (in eV) for each temperature
TTT (in Kelvin)
**/<nuclide name>/reactions/reaction_<mt>/**
:Attributes: - **mt** (*int*) -- ENDF MT reaction number
- **label** (*char[]*) -- Name of the reaction
- **Q_value** (*double*) -- Q value in MeV
- **Q_value** (*double*) -- Q value in eV
- **center_of_mass** (*int*) -- Whether the reference frame for
scattering is center-of-mass (1) or laboratory (0)
- **n_product** (*int*) -- Number of reaction products
@ -129,7 +129,7 @@ temperature-dependent data set. For example, the data set corresponding to
300 Kelvin would be located at `300K`.
:Datasets:
- **<TTT>K** (*double*) -- kT values (in MeV) for each Temperature
- **<TTT>K** (*double*) -- kT values (in eV) for each temperature
TTT (in Kelvin)
**/<thermal name>/elastic/<TTT>K/**
@ -333,7 +333,7 @@ N-Body Phase Space
- **n_particles** (*int*) -- Number of product particles
- **atomic_weight_ratio** (*double*) -- Atomic weight ratio of the
target nuclide in neutron masses
- **q_value** (*double*) -- Q value for the reaction in MeV
- **q_value** (*double*) -- Q value for the reaction in eV
.. _energy_distribution:
@ -346,7 +346,7 @@ Maxwell
:Object type: Group
:Attributes: - **type** (*char[]*) -- 'maxwell'
- **u** (*double*) -- Restriction energy in MeV
- **u** (*double*) -- Restriction energy in eV
:Datasets:
- **theta** (:ref:`tabulated <1d_tabulated>`) -- Maxwellian
temperature as a function of energy
@ -356,7 +356,7 @@ Evaporation
:Object type: Group
:Attributes: - **type** (*char[]*) -- 'evaporation'
- **u** (*double*) -- Restriction energy in MeV
- **u** (*double*) -- Restriction energy in eV
:Datasets:
- **theta** (:ref:`tabulated <1d_tabulated>`) -- Evaporation
temperature as a function of energy
@ -366,7 +366,7 @@ Watt Fission Spectrum
:Object type: Group
:Attributes: - **type** (*char[]*) -- 'watt'
- **u** (*double*) -- Restriction energy in MeV
- **u** (*double*) -- Restriction energy in eV
:Datasets: - **a** (:ref:`tabulated <1d_tabulated>`) -- Watt parameter :math:`a`
as a function of incident energy
- **b** (:ref:`tabulated <1d_tabulated>`) -- Watt parameter :math:`b`
@ -386,7 +386,7 @@ Discrete Photon
:Object type: Group
:Attributes: - **type** (*char[]*) -- 'discrete_photon'
- **primary_flag** (*int*) -- Whether photon is a primary
- **energy** (*double*) -- Photon energy in MeV
- **energy** (*double*) -- Photon energy in eV
- **atomic_weight_ratio** (*double*) -- Atomic weight ratio of
target nuclide in neutron masses
@ -396,7 +396,7 @@ Level Inelastic
:Object type: Group
:Attributes: - **type** (*char[]*) -- 'level'
- **threshold** (*double*) -- Energy threshold in the laboratory
system in MeV
system in eV
- **mass_ratio** (*double*) -- :math:`(A/(A + 1))^2`
Continuous Tabular

2
docs/source/io_formats/particle_restart.rst
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@ -46,7 +46,7 @@ The current revision of the particle restart file format is 1.
**/energy** (*double*)
Energy of the particle in MeV for continuous-energy mode, or the energy
Energy of the particle in eV for continuous-energy mode, or the energy
group of the particle for multi-group mode.
**/xyz** (*double[3]*)

12
docs/source/usersguide/input.rst
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@ -1520,7 +1520,7 @@ The ``<tally>`` element accepts the following sub-elements:
.. code-block:: xml
<filter type="energy" bins="0.0 1.0 20.0" />
<filter type="energy" bins="0.0 1.0e6 20.0e6" />
then two energy bins will be created, one with energies between 0 and
1 MeV and the other with energies between 1 and 20 MeV.
@ -1535,7 +1535,7 @@ The ``<tally>`` element accepts the following sub-elements:
.. code-block:: xml
<filter type="energyout" bins="0.0 1.0 20.0" />
<filter type="energyout" bins="0.0 1.0e6 20.0e6" />
then two post-collision energy bins will be created, one with
energies between 0 and 1 MeV and the other with energies between
@ -1854,7 +1854,7 @@ The ``<tally>`` element accepts the following sub-elements:
| |particles. The neutrino energy does not contribute |
| |to this response. The prompt and delayed |
| |:math:`\gamma`-rays are assumed to deposit their |
| |energy locally. Units are MeV per source particle. |
| |energy locally. Units are eV per source particle. |
+----------------------+---------------------------------------------------+
|fission-q-prompt |The prompt fission energy production rate. This |
| |energy comes in the form of fission fragment |
@ -1863,7 +1863,7 @@ The ``<tally>`` element accepts the following sub-elements:
| |incident energy and it requires that the nuclear |
| |data library contains the optional fission energy |
| |release data. Energy is assumed to be deposited |
| |locally. Units are MeV per source particle. |
| |locally. Units are eV per source particle. |
+----------------------+---------------------------------------------------+
|fission-q-recoverable |The recoverable fission energy production rate. |
| |This energy comes in the form of fission fragment |
@ -1874,7 +1874,7 @@ The ``<tally>`` element accepts the following sub-elements:
| |incident neutron energy and it requires that the |
| |nuclear data library contains the optional fission |
| |energy release data. Energy is assumed to be |
| |deposited locally. Units are MeV per source |
| |deposited locally. Units are eV per source |
| |paticle. |
+----------------------+---------------------------------------------------+
|decay-rate |The delayed-nu-fission-weighted decay rate where |
@ -2256,7 +2256,7 @@ attributes/sub-elements:
The width of mesh cells in each direction.
:energy:
Energy bins [in MeV], listed in ascending order (e.g. 0.0 0.625e-7 20.0)
Energy bins [in eV], listed in ascending order (e.g. 0.0 0.625 20.0e6)
for CMFD tallies and acceleration. If no energy bins are listed, OpenMC
automatically assumes a one energy group calculation over the entire
energy range.