Analysis of the continuous operational characteristics of the control rod eddy current retarder

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-09-22 DOI:10.1016/j.anucene.2025.111888

Hongyu Wu, He Yan, Yujie Dong, Xingzhong Diao

{"title":"Analysis of the continuous operational characteristics of the control rod eddy current retarder","authors":"Hongyu Wu, He Yan, Yujie Dong, Xingzhong Diao","doi":"10.1016/j.anucene.2025.111888","DOIUrl":null,"url":null,"abstract":"<div><div>The control rod eddy current retarder (CRECR) serves as the primary damping device during the control rod dropping process in the high temperature gas-cooled reactor, converting the gravitational potential energy into eddy current losses inside the conductor disk of CRECR. In order to analyze the torque performance of CRECR during continuous operation, a multi-node coupling method for electromagnetic and thermal simulation was proposed, and an electromagnetic-thermal coupling simulation model was established. Subsequently, the model was experimentally verified and the influence of speed, operating time and compensation claddings were analyzed. The torque deviation remains consistently below 7 % within 300 s. Additionally, continuous operation at speeds exceeding 300 rpm resulted in non-ignorable changes in component temperature and torque, necessitating careful consideration in engineering tests. Furthermore, a torque rebound phenomenon was observed during continuous operation, indicating that using compensation claddings can effectively mitigate the impact of thermal fade and improve the torque stability.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111888"},"PeriodicalIF":2.3000,"publicationDate":"2025-09-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925007054","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

The control rod eddy current retarder (CRECR) serves as the primary damping device during the control rod dropping process in the high temperature gas-cooled reactor, converting the gravitational potential energy into eddy current losses inside the conductor disk of CRECR. In order to analyze the torque performance of CRECR during continuous operation, a multi-node coupling method for electromagnetic and thermal simulation was proposed, and an electromagnetic-thermal coupling simulation model was established. Subsequently, the model was experimentally verified and the influence of speed, operating time and compensation claddings were analyzed. The torque deviation remains consistently below 7 % within 300 s. Additionally, continuous operation at speeds exceeding 300 rpm resulted in non-ignorable changes in component temperature and torque, necessitating careful consideration in engineering tests. Furthermore, a torque rebound phenomenon was observed during continuous operation, indicating that using compensation claddings can effectively mitigate the impact of thermal fade and improve the torque stability.

查看原文本刊更多论文

控制棒涡流缓速器连续工作特性分析

控制棒涡流缓速器（CRECR）是高温气冷堆控制棒跌落过程中的主阻尼装置，将重力势能转化为控制棒导体盘内的涡流损耗。为了分析CRECR连续运行时的转矩性能，提出了一种多节点电磁与热耦合仿真方法，并建立了电磁-热耦合仿真模型。通过实验对模型进行了验证，并分析了速度、运行时间和补偿包层对模型的影响。在300s内，扭矩偏差始终保持在7%以下。此外，在超过300转/分钟的速度下连续运行会导致组件温度和扭矩的不可忽视的变化，需要在工程测试中仔细考虑。此外，在连续运行过程中观察到转矩反弹现象，表明使用补偿包层可以有效缓解热衰减的影响，提高转矩稳定性。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

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.