Development of boron carbide concrete for enhanced radiation shielding in nuclear reactors

Concrete is widely utilized as a radiation shielding material fortified by its neutron attenuation property, affordability, mouldability, easy availability and strength characteristics. This study examined the effectiveness of incorporation of Boron Carbide (B 4 C), a material renowned for its neutron attenuation properties as a fine aggregate replacement in concrete, to enhance its neutron shielding capabilities without compromising the strength. This research provides insights into the development of special concrete for radiation shielding, in diverse nuclear and medical applications. The radiation shielding concrete (RSC) was prepared by replacing fine aggregate with B 4 C in various percentages 5 %, 10 % and 15 %. The workability, mechanical properties and neutron attenuation characteristics of B 4 C admixed concrete were compared with those of ordinary concrete. Results showed that the inclusion of B 4 C slightly reduced workability, with a 9.5 % slump reduction in samples containing 15 % B 4 C. Compressive strength exhibited a minor reduction at higher B 4 C levels, maintaining the target strength of 30 MPa at 15 % B 4 C, while split tensile and flexural strength showed negligible changes. Microstructural analysis indicated a minor increase in porosity with increasing B 4 C content. Hence the results demonstrate a substantial improvement in neutron shielding with minimal strength reduction. Additionally, gamma shielding showed comparable performance to normal concrete. Hence, the test results demonstrated that the inclusion of Boron Carbide significantly enhances the neutron shielding performance of concrete, devoid of any compromise on the latter's integrity. • Boron Carbide (B 4 C) as an additive to improve concrete’s neutron and gamma shielding properties. • Replacing fine aggregate with B 4 C provides a new approach to improve radiation efficiency and structural integrity. • Detailed studies confirm the superior attenuation properties of B 4 C modified concrete. • B 4 C concrete outperforms conventional concrete in both neutron and gamma radiation shielding. • B 4 C concrete as a promise for use in nuclear, medical, and other facilities requiring radiation shielding.

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Publication Details

Journal
Case Studies in Construction Materials
Published
2025-02-01
DOI
https://doi.org/10.1016/j.cscm.2025.e04354
Citations
6
Primary Topic
Radiation Shielding Materials Analysis
Type
article
Field-Weighted Citation Impact
3.11

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article

Development of boron carbide concrete for enhanced radiation shielding in nuclear reactors

M. Menaka, Karingamanna Jayanarayanan, V. Subramanian, Sudipta Chattopadhyaya et al.
6 citations
Case Studies in Construction Materials
Radiation Shielding Materials Analysis
3.11
article

Development of boron carbide concrete for enhanced radiation shielding in nuclear reactors

M. Menaka, Karingamanna Jayanarayanan, V. Subramanian, Sudipta Chattopadhyaya, P. Radhakrishnan, Dhanya Sathyan, Mini K. Madhavan, Pew Basu, B. Venkatraman, J Ashok Kumar, P V Gokul
article en
6 citations

Abstract

Concrete is widely utilized as a radiation shielding material fortified by its neutron attenuation property, affordability, mouldability, easy availability and strength characteristics. This study examined the effectiveness of incorporation of Boron Carbide (B 4 C), a material renowned for its neutron attenuation properties as a fine aggregate replacement in concrete, to enhance its neutron shielding capabilities without compromising the strength. This research provides insights into the development of special concrete for radiation shielding, in diverse nuclear and medical applications. The radiation shielding concrete (RSC) was prepared by replacing fine aggregate with B 4 C in various percentages 5 %, 10 % and 15 %. The workability, mechanical properties and neutron attenuation characteristics of B 4 C admixed concrete were compared with those of ordinary concrete. Results showed that the inclusion of B 4 C slightly reduced workability, with a 9.5 % slump reduction in samples containing 15 % B 4 C. Compressive strength exhibited a minor reduction at higher B 4 C levels, maintaining the target strength of 30 MPa at 15 % B 4 C, while split tensile and flexural strength showed negligible changes. Microstructural analysis indicated a minor increase in porosity with increasing B 4 C content. Hence the results demonstrate a substantial improvement in neutron shielding with minimal strength reduction. Additionally, gamma shielding showed comparable performance to normal concrete. Hence, the test results demonstrated that the inclusion of Boron Carbide significantly enhances the neutron shielding performance of concrete, devoid of any compromise on the latter's integrity. • Boron Carbide (B 4 C) as an additive to improve concrete’s neutron and gamma shielding properties. • Replacing fine aggregate with B 4 C provides a new approach to improve radiation efficiency and structural integrity. • Detailed studies confirm the superior attenuation properties of B 4 C modified concrete. • B 4 C concrete outperforms conventional concrete in both neutron and gamma radiation shielding. • B 4 C concrete as a promise for use in nuclear, medical, and other facilities requiring radiation shielding.

Case Studies in Construction MaterialsVol. 22
Indira Gandhi Centre for Atomic Research (IN), Amrita Vishwa Vidyapeetham (IN)
Board of Research in Nuclear Sciences
Openalex Percentile: Top 9%
Radiation Shielding Materials Analysis
3.11
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