Novel geopolymer materials for fast and thermal neutron shielding

In this work, we developed novel geopolymer (GP) composites for neutron shielding applications by dispersing up to 50 wt % polyethylene (PE) and boron carbide (B 4 C) powders into a potassium-based GP (KGP) matrix. We measured their attenuation coefficients to fast neutrons using a spontaneous fission 252 Cf source and a fusion deuterium–tritium generator and to thermal neutrons using a moderated 252 Cf source. The PE-based KGP were designed to reduce the neutron primary energy through neutron–hydrogen collisions, while 10 B in B 4 C was exploited to capture and stop thermal neutrons. The fast-neutron shielding properties of 50 wt % PE-KGP were superior, with an attenuation coefficient to fission neutrons up to 30% higher than that of high-density concrete. The B 4 C-based KGP formulation with B 4 C at 25 wt % and 50 wt % outperforms commercial boron-loaded flexible materials by approximately 18% and 50%, respectively. In simulation, we combined KGP with PE and B 4 C dispersants. A prototypical material comprised of 50 wt % PE-KGP and 50 wt % B 4 C-KGP significantly outperformed barite in reducing the dose due to fission-based spectra, similar to those found at nuclear reactors. Additionally, KGP shows excellent adhesive properties, high-temperature resistance, and can be molded into any size or shape, as well as 3D or 4D printed. Therefore, PE and B 4 C-loaded KGP and associated manufacturing techniques can be effectively employed in nuclear power plants and other facilities that rely on intense neutron sources, significantly enhancing their safety and cost-effectiveness. • Developed and characterized novel potassium-based geopolymer (KGP) composites for fast and thermal neutron shielding. • Showed that B 4 C-loaded KGP outperforms commercial boron-loaded materials for thermal neutron shielding. • Emphasized the potential of 3D and 4D printing for manufacturing customized neutron shielding components. • Proposed KGP-based composites as cost-effective and efficient shielding solutions for nuclear power plants and fuel cycle facilities.

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Publication Details

Journal
Annals of Nuclear Energy
Published
2025-03-31
DOI
https://doi.org/10.1016/j.anucene.2025.111388
Citations
4
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
Field-Weighted Citation Impact
2.07

Funders

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article

Novel geopolymer materials for fast and thermal neutron shielding

Angela Di Fulvio, Jianxin Zhou, Waltraud M. Kriven, Ali Özer et al.
4 citations
Annals of Nuclear Energy
Graphite, nuclear technology, radiation studies
2.07
article

Novel geopolymer materials for fast and thermal neutron shielding

Angela Di Fulvio, Jianxin Zhou, Waltraud M. Kriven, Ali Özer, Alexander W. L. Fields, Shaffer H. Bauer
article en
4 citations

Abstract

In this work, we developed novel geopolymer (GP) composites for neutron shielding applications by dispersing up to 50 wt % polyethylene (PE) and boron carbide (B 4 C) powders into a potassium-based GP (KGP) matrix. We measured their attenuation coefficients to fast neutrons using a spontaneous fission 252 Cf source and a fusion deuterium–tritium generator and to thermal neutrons using a moderated 252 Cf source. The PE-based KGP were designed to reduce the neutron primary energy through neutron–hydrogen collisions, while 10 B in B 4 C was exploited to capture and stop thermal neutrons. The fast-neutron shielding properties of 50 wt % PE-KGP were superior, with an attenuation coefficient to fission neutrons up to 30% higher than that of high-density concrete. The B 4 C-based KGP formulation with B 4 C at 25 wt % and 50 wt % outperforms commercial boron-loaded flexible materials by approximately 18% and 50%, respectively. In simulation, we combined KGP with PE and B 4 C dispersants. A prototypical material comprised of 50 wt % PE-KGP and 50 wt % B 4 C-KGP significantly outperformed barite in reducing the dose due to fission-based spectra, similar to those found at nuclear reactors. Additionally, KGP shows excellent adhesive properties, high-temperature resistance, and can be molded into any size or shape, as well as 3D or 4D printed. Therefore, PE and B 4 C-loaded KGP and associated manufacturing techniques can be effectively employed in nuclear power plants and other facilities that rely on intense neutron sources, significantly enhancing their safety and cost-effectiveness. • Developed and characterized novel potassium-based geopolymer (KGP) composites for fast and thermal neutron shielding. • Showed that B 4 C-loaded KGP outperforms commercial boron-loaded materials for thermal neutron shielding. • Emphasized the potential of 3D and 4D printing for manufacturing customized neutron shielding components. • Proposed KGP-based composites as cost-effective and efficient shielding solutions for nuclear power plants and fuel cycle facilities.

Annals of Nuclear EnergyVol. 218
University of Illinois Urbana-Champaign (US)
U.S. Army Corps of Engineers, Engineer Research and Development Center, Construction Engineering Research Laboratory
Openalex Percentile: Top 14%
Graphite, nuclear technology, radiation studies
2.07
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