Evaluation of radiation shielding properties of concrete with oil shale ash and basalt-boron fiber additives for spent nuclear fuel casks

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

Nuclear Engineering and Design Pub Date : 2025-05-01 DOI:10.1016/j.nucengdes.2025.114110

Andrius Slavickas , Hando Tohver , Maryna Holiuk , Andrejs Krasnikovs , Riho Mõtlep , Volodymyr Gulik

引用次数: 0

Abstract

Cement-based concretes are commonly used for managing radioactive waste due to their low cost and acceptable radiation shielding properties. However, the potential of using oil shale ash as an admixture in concrete for the radioactive waste packaging has been left unnoticed. The present work aims to demonstrate the radiation shielding properties of developed concrete mixes with the oil shale ash and basalt-boron fibers for the spent nuclear fuel management at the Ignalina NPP. Concrete composite materials were placed in the CONSTOR RBMK-1500/M2 cask model to estimate radiation shielding properties. OpenMC, MCNP, SCALE and Serpent codes were used for the estimation of radiation shielding properties. It was demonstrated that the cask with developed concrete composite material can meet the safety limit.

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油页岩灰和玄武岩硼纤维掺合物对乏燃料桶混凝土辐射屏蔽性能的评价

水泥基混凝土由于其低成本和可接受的辐射屏蔽性能，通常用于管理放射性废物。然而，使用油页岩灰作为放射性废物包装混凝土的外加剂的潜力一直被忽视。本研究旨在展示油页岩灰分和玄武岩硼纤维混合混凝土的辐射屏蔽性能，用于伊格纳利纳核电站的乏燃料管理。将混凝土复合材料放入CONSTOR RBMK-1500/M2木桶模型中，估算其辐射屏蔽性能。采用OpenMC、MCNP、SCALE和Serpent编码对辐射屏蔽性能进行估计。试验结果表明，所研制的混凝土复合材料能够满足安全要求。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.