diff --git a/paper.md b/paper.md
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@@ -49,7 +49,9 @@ Traditionally, researchers have implemented their own custom neutron source defi
 For example, spatial distributions, temperature effects, and fuel compositions must be correctly parameterised to ensure the fidelity of the simulations.
 The lack of standardised tools for these tasks introduces variability, potential errors in simulations and a lack of reproducibility.
 
-`openmc-plasma-source` addresses these challenges by providing a standardised and easy-to-use interface for defining neutron sources in OpenMC. The package implements the equations for neutron distributions based on established models, such as those described in @fausser_tokamak_2012 and fusion energy spectra from the NeSST tool @Crilly_NESST_-_Neutron_2024. By automating the setup process and including extensive documentation and examples, it reduces barriers to entry for researchers new to OpenMC or neutron source modelling.
+`openmc-plasma-source` addresses these challenges by providing a standardised and easy-to-use interface for defining neutron sources in OpenMC.
+The package implements the equations for neutron distributions based on established models, such as those described in @fausser_tokamak_2012 and fusion energy spectra from the NeSST tool [@Crilly_NESST_-_Neutron_2024].
+By automating the setup process and including extensive documentation and examples, it reduces barriers to entry for researchers new to OpenMC or neutron source modelling.
 
 # Pre-Built Configurations
 
@@ -65,7 +67,9 @@ With pre-built configurations for tokamak, ring, and point sources, `openmc-plas
 
 # Custom Energy Spectra
 
-`openmc-plasma-source` allows for customisation of neutron energy spectra based on varying fusion fuel compositions and spatial parameters. Users can define different fuel mixtures (e.g., DT, DD, TT) with associated spatially resolved temperature and density profiles, ensuring accurate and precise energy distributions. This flexibility is crucial for capturing the full range of neutron behaviours in complex fusion scenarios (see \autoref{fig:energy_spectra}).
+`openmc-plasma-source` allows for customisation of neutron energy spectra based on varying fusion fuel compositions and spatial parameters.
+Users can define different fuel mixtures (e.g., DT, DD, TT) with associated spatially resolved temperature and density profiles, ensuring accurate and precise energy distributions.
+This flexibility is crucial for capturing the full range of neutron behaviours in complex fusion scenarios (see \autoref{fig:energy_spectra}).
 
 ![Neutron Energy Spectra for different fusion fuels.\label{fig: energy spectra}](energy_spectra.svg)