小型模块化反应器用热管分析工具的发展:钠性质相关性

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY
T. Beuthe, Aleksandar Vasić, C. Azih, Pablo Diazgomezmaqueo
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引用次数: 0

摘要

先进的小型模块化反应堆通过增加被动热传输和安全系统的利用,努力提高反应堆的安全性。实现这一设计目标的一种创新手段是在正常和异常运行条件下使用碱金属热管冷却反应堆。热管模型已添加到ARIANT热工水力规范中,以实现反应堆建模并支持新反应堆的设计和许可。饱和流体特性是该模型的基本输入。因此,这篇文章提供了一个全面的比较概述,最好的可用钠饱和度的相关性发展在过去的一个世纪。结果表明,热管模型所需的大多数钠性质相关性都是相对明确的,并且可以提供使用它们的建议。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Development Of Analysis Tools For Heat Pipes Used In Small Modular Reactors: Sodium Property Correlations
Advanced small modular reactors strive to improve reactor safety though increased utilization of passive heat transport and safety systems. An innovative means of meeting this design goal is to use alkali metal heat pipes to cool the reactor under both normal and abnormal operating conditions. A heat pipe model has been added to the ARIANT thermalhydraulic code to enable reactor modelling and support the design and licensing of new reactors. Saturation fluid properties are a fundamental input to this model. Consequently, this article provides a comprehensive comparative overview of the best available sodium saturation property correlations developed over the past century. The results show most of the sodium property correlations needed to model a heat pipe are relatively well defined and recommendations for their use can be provided.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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