Authors:

Parker Smith

Date Created:

Not specified

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About Paper:

Increasing applications in space propulsion and nuclear reactor development necessitate the development of advanced radiation shields to protect sensitive electronics and individuals from ionizing radiation. This research project uses OpenMC, a community-developed Monte Carlo N-Particle (MCNP) simulation tool, to evaluate the effectiveness of various composite materials in mitigating gamma and neutron radiation. OpenMC's capabilities allow for precise modeling of radiation interactions, offering a cost-effective and efficient virtual testing ground that avoids physical experimentation constraints and potential mishaps. We simulate and assess the shielding capacity of different composites, both layered and in mixed powder form, to develop materials that can effectively shield both photons and neutrons. Comparing the simulation results with experimental data, validates the models and confirms the efficacy of the proposed shielding solutions. These results can be used to minimize the risk of radiation-induced damage to critical systems, ensuring their integrity and longevity in hazardous environments. Keywords: Radiation Shielding; Gamma Radiation; Neutron Radiation; OpenMC

Source:

Purdue University / 2024

Topics:

No topics listed

Co-authors:

Parker Smith