A comprehensive study on factors influencing radiation shielding concrete characteristics

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-09-16 DOI:10.1016/j.nucengdes.2025.114466

Ashutosh Nanda , Saubhagya Kumar Panigrahi

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引用次数: 0

Abstract

Radiation shielding concrete (RSC) is a construction material against radiation exposure due to its effective shielding ability, adequate mechanical along with durability characteristics, cost-effectiveness, and abundant versatility. The radiation exposure is detrimental to both living anatomy and structural integrity, hence, the structural radiation shielding through RSC is essential. Being a heterogeneous material, several factors associated with different RSC constituents, like aggregate, binder, additive, and matrix composite, can influence its properties, thus limiting the usefulness of the most sensitive RSC structure, as even minor radiation penetration can have severe consequences for public health and safety. Hence, an attempt has been made to create a comprehensive database on the alternative materials in RSC formation. Literature for review was selected based on a rigorous keyword search through various databases such as ‘SCOPUS’, ‘Google Scholar’, ‘Science Direct’, etc. This manuscript highlights the RSC’s progress and development across the world and discusses the various RSC characteristics through different factors associated with the RSC constituents, influencing the radiation shielding ability of both hydrated RSC (HRSC) and geopolymerised RSC (GRSC) against gamma-rays and neutron particles. Through a map study of these factors and characteristics, the identified primary factors governing the realization of RSC, along with its property development, are high-density aggregate, fiber addition, and nanoparticle addition. The most preferred material constituents for RSC production, along with their optimal dosages, are identified. The maximum attainable RSC attenuation capacity against Gamma-ray and Neutrons using the mentioned most preferred material constituents is 0.30–––0.40 cm⁻¹ and 0.10–––0.20 cm⁻¹, respectively. A comparison is made between the materials utilized in a few prime reactors in India and the preferred constituent materials through this review work. In the event of meager accomplishments in research work concerning factors associated with RSC components, the current review can be treated as a platform for researchers in this field.

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辐射屏蔽混凝土特性影响因素的综合研究

辐射屏蔽混凝土（RSC）由于其有效的屏蔽能力、足够的力学和耐久性、成本效益和丰富的通用性，是一种抗辐射暴露的建筑材料。辐射暴露对活体解剖和结构完整性都是有害的，因此，通过RSC进行结构辐射屏蔽是必不可少的。作为一种非均质材料，与不同RSC成分相关的几个因素，如骨料、粘合剂、添加剂和基质复合材料，可能影响其性能，从而限制了最敏感的RSC结构的用途，因为即使是微小的辐射穿透也可能对公众健康和安全造成严重后果。因此，已试图建立一个关于可选材料编制的综合数据库。通过对SCOPUS、b谷歌Scholar、Science Direct等数据库进行严格的关键词搜索，选择文献进行综述。本文重点介绍了RSC在世界范围内的进展和发展，并通过与RSC成分相关的不同因素讨论了RSC的各种特性，影响水合RSC （HRSC）和地聚合RSC （GRSC）对伽马射线和中子粒子的辐射屏蔽能力。通过对这些因素和特征的图谱研究，确定了控制RSC实现及其性能发展的主要因素是高密度骨料、纤维添加和纳米颗粒添加。确定了RSC生产中最优选的材料成分及其最佳剂量。使用上述最优选的材料成分，对伽马射线和中子可达到的最大RSC衰减能力分别为0.30—0.40 cm - 1和0.10—0.20 cm - 1。通过这项审查工作，对印度几个主反应堆使用的材料和优选的组成材料进行了比较。如果在与RSC成分相关的因素的研究工作中取得了微薄的成就，本综述可以被视为该领域研究人员的平台。

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来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.