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

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 (B4C), a material renowned for its neutron...

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Bibliographic Details
Main Authors: P. Gokul, J. Ashok Kumar, R. Preetha, Sudipta Chattopadhyaya, Pew Basu, M. Menaka, V. Subramanian, B. Venkatraman, Dhanya Sathyan, K. Jayanarayanan, Mini K. Madhavan
Format: Article
Language:English
Published: Elsevier 2025-07-01
Series:Case Studies in Construction Materials
Subjects:
Boron carbide
Radiation shielding concrete
Neutron shielding
Radiation attenuation
Mechanical properties
Neutron attenuation
Online Access:http://www.sciencedirect.com/science/article/pii/S2214509525001524
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