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.
Authors
- Angela Di Fulvio (ORCID: https://orcid.org/0000-0001-5244-7179)
- Jianxin Zhou (ORCID: https://orcid.org/0000-0002-6600-9564)
- Waltraud M. Kriven (ORCID: https://orcid.org/0000-0002-2983-5760)
- Ali Özer (ORCID: https://orcid.org/0000-0002-4207-8207)
- Alexander W. L. Fields (ORCID: https://orcid.org/0009-0004-5287-2705)
- Shaffer H. Bauer
Institutions
- University of Illinois Urbana-Champaign (US)
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
- U.S. Army Corps of Engineers
- Engineer Research and Development Center
- Construction Engineering Research Laboratory