Update paper.md

Co-authored-by: Jonathan Shimwell <[email protected]>

paper.md

@@ -40,7 +40,9 @@ Accurate modelling of neutron sources is critical for fusion energy research, un
 In this context, OpenMC is a widely used tool for neutron transport simulations [@romano_openmc_2015].
 However, creating realistic neutron source models for fusion applications can be a time-consuming and error-prone process, requiring detailed knowledge of plasma physics and significant coding effort.
 
-Traditionally, researchers have implemented their own custom neutron source definitions, which often results in redundant work and inconsistencies between studies. 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 and potential errors in simulations.
+Traditionally, researchers have implemented their own custom neutron source definitions, which often results in redundant work and inconsistencies between studies.
+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. 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.