钠冷快堆用放射性核素捕集器综述

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

Nuclear Engineering and Design Pub Date : 2025-08-06 DOI:10.1016/j.nucengdes.2025.114354

R. Sudha, Chinmay Routray, Rajesh Ganesan, V. Jayaraman

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引用次数: 0

摘要

在钠冷却快堆中，活化腐蚀产物（如54Mn、60Co和58Co）和裂变产物（如137Cs）（在燃料销失效的情况下）的传输所产生的放射性会限制初级回路组件的维护。此外，该活动建立在主要组件去污期间产生大量高放射性液体流出物的组件上。使用合适的捕集器材料加入放射性核素捕集器将减少主要组分的活度积累。根据印度英迪拉甘地原子研究中心（IGCAR）的研究成果，设计并制造了一个用于捕获137Cs的芯内放射性核素捕集器和一个用于捕获54Mn的胶囊子组件。本文综述了用于快堆活性腐蚀产物和裂变产物的放射性核素捕集器的发展。

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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Radionuclide traps for sodium-cooled fast reactors–A review

In sodium-cooled fast reactors, the radioactivity resulting from transport of activated corrosion products such as ⁵⁴Mn, ⁶⁰Co and ⁵⁸Co and fission products such as ¹³⁷Cs (in the event of fuel pin failure) causes constraints on access for maintenance of primary loop components. In addition, the activity builds on components that generate large volumes of highly radioactive liquid effluents during the decontamination of the primary components. Incorporation of a radionuclide trap using a suitable trap material would reduce the activity buildup in primary components. Based on the studies carried out in Indira Gandhi Centre for Atomic Research (IGCAR), India, an in-core radionuclide trap for ¹³⁷Cs and a capsule sub-assembly to trap ⁵⁴Mn were designed and fabricated. This work presents a review of the development of radionuclide traps for the chosen activated corrosion product and fission product for fast reactors.

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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.