openmc.data.WattEnergy¶
- class openmc.data.WattEnergy(a, b, u)[source]¶
Energy-dependent Watt spectrum represented as
\[f(E \rightarrow E') = \frac{e^{-E'/a}}{I} \sinh \left ( \sqrt{bE'} \right ) \]- Parameters
a (openmc.data.Tabulated1D) – Energy-dependent parameters tabulated as function of incident neutron energy
b (openmc.data.Tabulated1D) – Energy-dependent parameters tabulated as function of incident neutron energy
u (float) – Constant introduced to define the proper upper limit for the final particle energy such that \(0 \le E' \le E - U\)
- Variables
b (a,) – Energy-dependent parameters tabulated as function of incident neutron energy
u (float) – Constant introduced to define the proper upper limit for the final particle energy such that \(0 \le E' \le E - U\)
- classmethod from_ace(ace, idx)[source]¶
Create a Watt fission spectrum from an ACE table
- Parameters
ace (openmc.data.ace.Table) – An ACE table
idx (int) – Offset to read from in XSS array (default of zero)
- Returns
Watt fission spectrum
- Return type
- classmethod from_endf(file_obj, params)[source]¶
Generate Watt fission spectrum from an ENDF evaluation
- Parameters
file_obj (file-like object) – ENDF file positioned at the start of a section for an energy distribution.
params (list) – List of parameters at the start of the energy distribution that includes the LF value indicating what type of energy distribution is present.
- Returns
Watt fission spectrum
- Return type