openmc.data.MaxwellEnergy¶
- class openmc.data.MaxwellEnergy(theta, u)[source]¶
Simple Maxwellian fission spectrum represented as
\[f(E \rightarrow E') = \frac{\sqrt{E'}}{I} e^{-E'/\theta(E)} \]- Parameters
theta (openmc.data.Tabulated1D) – Tabulated 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
theta (openmc.data.Tabulated1D) – Tabulated 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=0)[source]¶
Create a Maxwell distribution 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
Maxwell distribution
- Return type
- classmethod from_endf(file_obj, params)[source]¶
Generate Maxwell distribution 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
Maxwell distribution
- Return type