Study on thermal expansion reactivity of CEFR control rod drive mechanism

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Bian Xinyuan, Ke Guotu, Zhang Jian
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引用次数: 0

Abstract

During the power test phase of CEFR, the power reactivity measurement test was carried out. The results showed that there was a large deviation between the theoretical calculation and the experimental measurement. It is necessary to analyze the causes of deviation and correct it. The main reason for the deviation is thermal expansion. As the sodium temperature rises, thermal expansion occurs in the control rod drive mechanism, main vessel, core, distribution header, moving component and absorber in the control rod. The relative displacement causes the control rod shift downwards and insert negative reactivity. This paper calculates the thermal expansion of each part and corrects the theoretical calculation. The theoretical calculated of power reactivity is −486pcm, and the total reactivity obtained by theoretical calculation and correction is −943.43pcm. The results show that the relative deviation be-tween theoretical and experimental reactivity decreased from 54.83 % to 12.32 %.
CEFR控制棒驱动机构热膨胀反应性研究
在CEFR功率试验阶段,进行了功率无功性测量试验。结果表明,理论计算与实验测量存在较大偏差。有必要分析产生偏差的原因并加以纠正。产生偏差的主要原因是热膨胀。随着钠温度的升高,控制棒内的控制棒驱动机构、主容器、堆芯、配线头、移动部件、吸收器等发生热膨胀。相对位移导致控制杆下移并插入负反应性。本文对各部件的热膨胀进行了计算,并对理论计算进行了修正。理论计算得到的功率反应度为- 486pcm,经理论计算和修正得到的总反应度为- 943.43pcm。结果表明,理论反应性与实验反应性的相对偏差由54.83%减小到12.32%。
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 Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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