自然对流应急模式下快堆燃料组件中碱性冷却剂沸腾的研究

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
A. P. Sorokin, N. A. Denisova, Yu. A. Kuzina, G. A. Sorokin
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引用次数: 0

摘要

本文介绍了IPPE JSC在自然循环条件下对单燃料组件和并联燃料组件(FAs)模型中碱性液态金属沸腾时的热交换和循环稳定性进行的实验结果。结果表明,液态金属在FAs中沸腾的复杂结构是在多种因素的影响下形成的,具有稳定模式和振荡模式,并可能过渡到脱离核沸腾。研究了燃料棒表面粗糙度对两相束状液态金属流换热及流动方式的影响。本文介绍了在堆芯上方有钠腔的FA模型中钠沸腾换热的实验结果,证明了在FAs中燃料棒模拟器长期冷却的可能性。给出了沸腾过程中传热的依赖关系和两相液态金属流动的模式图。计算结果与实验结果吻合较好,表明碱金属在单模式熔体和平行熔体系统中沸腾过程的数值模拟与实验结果吻合较好。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Study of alkaline coolant boiling in the fuel assemblies of fast reactors in emergency modes with natural convection

The article presents the results of experiments conducted by the IPPE JSC on heat exchange and circulation stability during boiling of alkaline liquid metals in the models of single and parallel fuel assemblies (FAs) under natural circulation conditions. It is shown that the complex structure of liquid metal boiling in FAs is formed under the influence of various factors and is characterized by both stable and oscillatory modes, as well as possible transition to departure from nucleate boiling. The influence of the fuel rod surface roughness on the heat exchange and flow modes of a two-phase liquid metal flow in bundles is shown. The presented results of experiments on the heat exchange during sodium boiling in an FA model with a sodium cavity above the reactor core demonstrate the possibility of long-term cooling of fuel rod simulators in FAs. The dependence on the heat transfer during boiling and a map of the modes for a two-phase liquid metal flow in the FA are presented. The agreement between the results of computational simulation and experiments on alkaline metal boiling in a single model FA and a system of parallel FAs is shown.

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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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