玄武岩-硼纤维增强混凝土：中子辐射屏蔽的可持续解决方案

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-05-16 DOI:10.1016/j.nucengdes.2025.114150

Maryna Holiuk , Iryna Romanenko , Hennadii Odynokin , Anatolii Nosovskyi , Vitalii Pastsuk , Madis Kiisk , Olexander Biland , Anthony DiBenedetto , Yurii Chuvashov , Iryna Diduk , Volodymyr Gulik

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引用次数: 0

摘要

先进复合材料的发展对于满足核能日益增长的需求，特别是对辐射屏蔽的需求至关重要。本研究探讨了玄武岩-硼纤维增强混凝土作为一种提高混凝土中子屏蔽性能的创新材料的潜力。玄武岩-硼纤维增强混凝土结合了玄武岩纤维的力学优势和硼-10的中子吸收能力，为核反应堆屏蔽应用提供了一个有前途的解决方案。在两种配置（带镉喷嘴和不带镉喷嘴）下使用Pu-Be中子源的实验评估表明，与普通混凝土相比，即使玄武岩-硼纤维剂量较低，也会导致中子通量减少约5%。互补的Serpent Monte Carlo模拟验证了这些发现，并进一步表明提高玄武岩硼纤维产量和增加纤维用量可以显著提高屏蔽性能。研究结果表明，玄武岩-硼纤维增强混凝土不仅可以改善中子屏蔽，还可以解决核反应堆中与生物屏蔽混凝土相关的关键老化问题。硼-10在纤维结构中的均匀分布可以增强中子吸收，特别是在生物屏蔽的近表层，那里中子诱导的降解是最严重的。此外，纤维增强可以减轻微裂纹，提高断裂韧性，延长反应堆屏蔽结构的使用寿命。这一特点对核电站尤为重要，因为生物屏蔽的完整性直接影响到核电站的安全性和运行效率。这项研究突出了玄武岩-硼纤维增强混凝土作为一种成本效益高、耐用、可扩展的核能中子屏蔽材料的潜力。研究结果为其在核反应堆屏蔽和辐射防护系统中的广泛应用奠定了基础，解决了该领域当前和未来的挑战。

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Basalt-boron fiber reinforced concrete: A sustainable solution for neutron radiation shielding

The development of advanced composite materials is essential for addressing the growing demands of nuclear energy, particularly for radiation shielding. This study investigates the potential of basalt-boron fiber reinforced concrete as an innovative material to enhance the neutron shielding properties of concrete. Basalt-boron fiber reinforced concrete combines the mechanical benefits of basalt fiber with the neutron absorption capabilities of boron-10, offering a promising solution for nuclear reactor shielding applications. Experimental evaluations using a Pu-Be neutron source under two configurations – with and without cadmium nozzles – demonstrate that even low basalt-boron fiber dosages result in a neutron flux reduction of approximately 5% compared to plain concrete. Complementary Serpent Monte Carlo simulations validated these findings and further suggested that improved basalt-boron fiber production and increased fiber dosage can significantly enhance shielding performance.

The findings reveal that basalt-boron fiber reinforced concrete not only improves neutron shielding but also addresses critical ageing issues associated with biological shielding concrete in nuclear reactors. The uniform distribution of boron-10 within the fiber structure enables enhanced neutron absorption, particularly in the near-surface layers of biological shielding, where neutron-induced degradation is most severe. Furthermore, the fiber reinforcement mitigates microcracking, enhances fracture toughness, and prolongs the operational lifespan of reactor shielding structures. This feature is particularly crucial for nuclear power plants, where the integrity of biological shielding directly impacts safety and operational efficiency.

This study highlights the potential of basalt-boron fiber reinforced concrete as a cost-effective, durable, and scalable neutron shielding material for nuclear energy applications. The results establish a foundation for its broader application in nuclear reactor shielding and radiation protection systems, addressing both current and future challenges in the field.

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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.