# 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
Returns

Maxwell distribution

Return type

openmc.data.MaxwellEnergy

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

openmc.data.MaxwellEnergy

classmethod from_hdf5(group)[source]

Generate Maxwell distribution from HDF5 data

Parameters

group (h5py.Group) – HDF5 group to read from

Returns

Maxwell distribution

Return type

openmc.data.MaxwellEnergy

to_hdf5(group)[source]

Write distribution to an HDF5 group

Parameters

group (h5py.Group) – HDF5 group to write to