Preprint / Version 1

Modeling Shielding for Nuclear fission Powered Aircrafts

##article.authors##

  • Rishit Gupta Related

DOI:

https://doi.org/10.58445/rars.1683

Keywords:

engineering, Nuclear fission Powered Aircrafts

Abstract

 Global carbon emissions are increasing every year, and we need clean energy alternatives. This research focuses on modeling a simplified shielding structure for nuclear fission powered aircraft using OpenMC, a simulation software used to simulate neutron transport in nuclear reactors . A Constructive Solid Geometry (CSG) spherical model was used to represent the shielding, and the reactor structure, making high-level assumptions about the model.Nuclear fission-powered aircrafts, demonstrated in the 1950s were used for propulsion, but this was put to a stop due to the nonproliferation and global security concerns. Furthermore, there was not enough shielding to protect the passengers and avionics from harmful radiations, and the government no longer had a need for these aircrafts so they defunded this field. This is important because as we approach the future, CO2 emission rates increase year by year, ultimately worsening climate change. New methods of clean energy and sustainability must be discovered and one method would be through using nuclear reactors however these reactors do produce radioactive waste. However, due to recent technologies that can reprocess the radioactive waste, which is recycled and produced into nuclear fuel, making fission powered aircrafts a sustainable way to travel. Additionally it is an efficient form of travel as nuclear fuel can produce a significant amount of energy. While this is an efficient and cleaner method of air travel, there are safety measures that must be taken to ensure that this type of reactor propulsion technology is safe to operate without portraying any risks to those onboard or any damage to avionics. This paper models a simple geometry using OpenMC, using uranium-238 as our reactor fuel source, and polyethylene and lead as our shielding material. The goal from testing in OpenMC is to assess the effectiveness of shielding to minimize radiation being emitted from the reactor.



References

Thornton, G. (1963). Introduction to nuclear propulsion-introduction and background lecture 1, Feb. 26-28, 1963 (No. NASA-CR-52961).

( Aug. 1, 2023. ) U.S. Energy Information Administration - EIA - independent statistics and analysis. Nuclear explained - U.S. Energy Information Administration (EIA).

Hu, G., Zhang, H., & Liu, Q. (2020). Review on sensors to measure control rod position for nuclear reactors. Annals of Nuclear Energy, 144, 107485.

Touran, N. (2007, April 21). What is a nuclear moderator? What Is Nuclear?

Nuclear 101: How does a nuclear reactor work? | Department of Energy. Office of Nuclear Energy . (2023, August 2).

Thibeault, S. A., Fay, C. C., Lowther, S. E., Earle, K. D., Sauti, G., Kang, J. H., ... & McMullen, A. M. (2012). Radiation shielding materials containing hydrogen, boron, and nitrogen: Systematic computational and experimental study (No. HQ-E-DAA-TN33851).

Paul K. Romano, Nicholas E. Horelik, Bryan R. Herman, Adam G. Nelson, Benoit Forget, and Kord Smith, “OpenMC: A State-of-the-Art Monte Carlo Code for Research and Development,”Ann. Nucl. Energy, 82, 90–97 (2015).

MacPherson, H. G. (1985, March 15). The Molten Salt Reactor Adventure. https://dpl6hyzg28thp.cloudfront.net/media/MSadventure.pdf

Molten salt reactors. World Nuclear Association. (n.d.). https://world-nuclear.org/information-library/current-and-future-generation/molten-salt-reactors

Chen, Y. Q., & Yan, B. H. (2023). The technology of shielding design for nuclear reactors: a review. Progress in Nuclear Energy, 161, 104741.

Schaeffer, N. M. (1973). Reactor shielding for nuclear engineers (No. TID-25951). Radiation Research Associates, Inc., Fort Worth, Tex.(USA).

] LeBlanc, D. (2010). Molten salt reactors: A new beginning for an old idea. Nuclear Engineering and design, 240(6), 1644-1656.

]Rom, F. E. (1971). Status of the nuclear powered airplane. Journal of Aircraft, 8(1), 26-33.

Laurence, G. C. (1956). Shielding for reactors. British Journal of Applied Physics, 7(S5), S54.

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2024-10-02

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