印度典型研究反应堆在通电处理期间托盘杆组件内部流动诱发振动的实验研究

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

Annals of Nuclear Energy Pub Date : 2025-04-23 DOI:10.1016/j.anucene.2025.111511

A. Ravi Kiran , M.K. Agrawal , Renuka Patel , S.K. Sinha

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引用次数: 0

摘要

研究堆中的托盘棒组件是对堆芯内样品进行辐照的一种设备。对于托盘杆组件的通电提升，必须确保其在冷却剂流动引起的轴流诱发振动下的完整性。在本工作中，证明了确定托盘杆组件轴流诱导振动响应的方法。利用内部流动测试设备，对典型印度研究堆（IRR）的“通电盘棒”轴流诱导振动响应进行了实验研究。提出了在轴流诱导振动载荷下“通电”托盘杆组件的三个条件。第一个是允许振动速度，第二个是允许位移，第三个是允许流速。对总成进行了自由振动分析，得到了总成的动态特性，并与实验结果进行了比较。

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Experimental study of internal flow induced vibration of tray rod assembly during on-power handling in a typical Indian research reactor

A tray rod assembly in a research reactor is a facility that irradiates samples inside reactor core. For on-power lifting of the tray rod assembly, it is necessary to ensure its integrity under axial flow induced vibrations, resulting from coolant flow. In the present work, methodology for qualifying the axial flow induced vibration response of a tray rod assembly is demonstrated. Experiments are conducted to study the axial flow induced vibration response of an ‘on-power tray rod’ of a typical Indian Research Reactor (IRR), using an in-house flow test facility. Three conditions are proposed for the qualification of ‘on-power’ tray rod assembly under axial flow induced vibration load. First one is the permissible vibration velocity, second one is the permissible displacement and the third one is the permissible flow velocity. Free vibration analysis of the assembly is carried out to obtain the dynamic characteristics and to compare with experimental results.

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.