An Assessment of Replacing Aluminum Tubes Hosting Nuclear Fuels with Stainless Steel in a Subcritical Nuclear Reactor

Diego Medina-Castro, Héctor René Vega-Carrillo, Antonio Baltazar-Raigosa, Tzinnia Gabriela Soto-Bernal, Régulo López-Callejas and Benjamín Gonzalo Rodríguez-Méndez ()
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Diego Medina-Castro: Plasma Physics Laboratory, National Institute for Nuclear Research, Carretera México-Toluca S/N, Ocoyoacac 52750, Mexico
Héctor René Vega-Carrillo: Radiobiology Academic Group, Academic Unit for Nuclear Studies, Autonomous University of Zacatecas, Cipres 10, Fracc. La Peñuela, Zacatecas 98068, Mexico
Antonio Baltazar-Raigosa: Radiobiology Academic Group, Academic Unit for Nuclear Studies, Autonomous University of Zacatecas, Cipres 10, Fracc. La Peñuela, Zacatecas 98068, Mexico
Tzinnia Gabriela Soto-Bernal: School of Engineering and Sciences, Tecnologico de Monterrey, Av. Eugenio Garza Sada 1500, Aguascalientes 20328, Mexico
Régulo López-Callejas: Plasma Physics Laboratory, National Institute for Nuclear Research, Carretera México-Toluca S/N, Ocoyoacac 52750, Mexico
Benjamín Gonzalo Rodríguez-Méndez: Plasma Physics Laboratory, National Institute for Nuclear Research, Carretera México-Toluca S/N, Ocoyoacac 52750, Mexico

Energies, 2025, vol. 18, issue 12, 1-20

Abstract: This computational study using MCNP5 evaluated the feasibility of replacing 6061-T6 aluminum with 316L stainless steel (SS-316L) for the tubes hosting the uranium slugs in the subcritical nuclear reactor Nuclear Chicago model 9000, thereby contributing to its preservation as a key resource for nuclear research and education in Mexico. Simulations and dosimetric analyses (ICRP/ICRU) confirmed subcriticality in both configurations. Notably, SS-316L demonstrated an effective attenuation of peripheral gamma radiation and a reduction in the ambient neutron dose, indicating a considerable improvement in radiological safety. Although a reduction in thermal and epithermal neutron fluence was observed, the similarity in the gamma spectrum suggests no significant alteration for gamma spectroscopic experiments. In conclusion, SS-316L presents a promising alternative that enhances radiological safety and reactor longevity, making it a worthy consideration as a replacement material. Further experimental investigation is recommended to assess material activation and the gamma dose in the vicinity of the fuel.

Keywords: subcritical reactor; tubes for fuel slugs; Monte Carlo; effective multiplication factor; spectrometry and dosimetry (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2025
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