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...

詳細記述

書誌詳細
出版年:Case Studies in Construction Materials
主要な著者: P. Gokul, J. Ashok Kumar, R. Preetha, Sudipta Chattopadhyaya, Pew Basu, M. Menaka, V. Subramanian, B. Venkatraman, Dhanya Sathyan, K. Jayanarayanan, Mini K. Madhavan
フォーマット: 論文
言語:英語
出版事項: Elsevier 2025-07-01
主題:
オンライン・アクセス:http://www.sciencedirect.com/science/article/pii/S2214509525001524