The data enclosed in this repository is associated with the manuscript for an article submitted to the European Physical Journal - Nuclear mid February 2019. The article is an adaptation of an article presented at the ICONE26 Conference in London, July 2018. Some of the neutronic data also presented in the article was presented at the CFD4NRS-7 Workshop in Shanghai, September 2018. The figures and tables presents the specifications and results of the neutron simulations performed for these papers. They show cross-sections, power distributions and variation of effective multiplification factor with temperature and population density. The data is in the form of figures and tables. The figures in the corresponding directory were prepared using bash scripts, python version 2.7, gnuplot version 4.6 and latex to extract and analyse simulated data. The tables in the corresponding directory were prepared using bash scripts and python version 2.7 to extract and analyse simulated data. The python scripts can be found in the repository. Note that numpy is a requirement. The raw data was prepared using the SCARF (scarf.rl.ac.uk) and the University of Liverpool (https://www.liverpool.ac.uk/csd/advanced-research-computing/facilities/high-performance-computing/). The data was generated by the solvers DYN3D-MG (https://www.hzdr.de/db/Cms?pOid=11771&pNid=542) and SERPENT (http://montecarlo.vtt.fi/). DYN3D-MG modelled the nodal diffusion neutronic behaviour of the molten salt fast reactor. SERPENT (version 2.1.29) modelled the neutronic behaviour of the molten salt fast reactor using the Monte Carlo method.EPSRC Grant No. EP/R001618/1; H2020-EU.1.2.2. - FET Proactive 671564