Simulation data for Exploring the Impact of Heterogeneous Cm-244 Distribution on Neutron Flux within Fukushima Daiichi Fuel Debris

These data was generated using Geant4 for the contribution in the
International Topical Workshop on Fukushima-Daiichi Decommissioning
Research 2024 (FDR2024). The contribution was a presentation, with an
abstract as follows: Understanding the distribution of neutron source
within fuel debris is crucial for assessing radiation hazards and safety
measures in nuclear accident scenarios. In this study, a systematic
approach to investigate the effects of the heterogeneous distribution of
Cm-244 neutron source on neutron flux distribution within the Fukushima
Daiichi Nuclear Power Plant is proposed. Using Geant4 Monte Carlo
simulations, various scenarios with different concentrations and spatial
distribution of Cm-244 within a cylindrical corium volume were modelled.
By varying concentration levels and distribution patterns, different
configurations of neutron sources that influence neutron flux distribution
were analysed. The research findings provide insights into the spatial
variability of neutron flux within fuel debris, enhancing the development
of radiation protection strategies and decommissioning efforts. This
research contributes to advancing our understanding of nuclear accident
consequences and enhancing safety measures in nuclear
facilities.Description