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  • AbstractFDR24V0.docx

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    Date added: 13/03/25

  • README.txt

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    Date added: 13/03/25

  • FDR2024_Application_form_for_Japan.xlsx

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    Date added: 13/03/25

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DOI

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

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Description

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.
Date made available2024
PublisherLancaster University

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