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铅基快堆自然循环实验台架比例分析方法研究
引用本文:赵鹏程,朱恩平,余红星,翟鹏迪,邓声文,夏榜样,陈宝文.铅基快堆自然循环实验台架比例分析方法研究[J].核动力工程,2020,41(6):207-213.
作者姓名:赵鹏程  朱恩平  余红星  翟鹏迪  邓声文  夏榜样  陈宝文
作者单位:中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213;南华大学核科学技术学院,湖南衡阳,421001;南华大学核燃料循环技术与装备湖南省协同创新中心,湖南衡阳,421001,南华大学核科学技术学院,湖南衡阳,421001,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,南华大学核科学技术学院,湖南衡阳,421001,南华大学核科学技术学院,湖南衡阳,421001,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213,中国核动力研究设计院核反应堆系统设计技术重点实验室,成都,610213
基金项目:核燃料循环技术与装备协同创新中心开放基金项目;湖南省教育厅优秀青年项目;湖南省自然科学基金;国家自然科学基金
摘    要:铅基快堆具有良好的自然循环能力,研究其自然循环特性对提高反应堆固有安全性具有重要价值,而比例分析方法是建立合理可行铅基快堆自然循环实验台架的理论基础。本文通过无量纲化典型自然循环铅基快堆一回路系统的流体控制方程,确定主要的无量纲相似准则群;基于所构建的无量纲相似准则数对小型自然循环铅基快堆SNCLFR-10开展比例分析,获得双环路单相自然循环实验台架的几何和热工水力设计参数;对比分析额定工况下SNCLFR-10和缩比实验台架的关键热工水力参数,开展铅基快堆自然循环实验台架比例分析方法验证。研究结果表明,SNCLFR-10和缩比台架的关键热工参数模拟结果比值与理论推导比例关系吻合良好,建立的铅基快堆自然循环实验台架比例分析方法合理可行。 

关 键 词:铅基快堆    自然循环    比例分析方法    相似准则

Research on Scaling Analysis Method for Natural Circulation Test Facility of Lead-Based Fast Reactor
Zhao Pengcheng,Zhu Enping,Yu Hongxing,Zhai Pengdi,Deng Shengwen,Xia Bangyang,Chen Baowen.Research on Scaling Analysis Method for Natural Circulation Test Facility of Lead-Based Fast Reactor[J].Nuclear Power Engineering,2020,41(6):207-213.
Authors:Zhao Pengcheng  Zhu Enping  Yu Hongxing  Zhai Pengdi  Deng Shengwen  Xia Bangyang  Chen Baowen
Abstract:Lead-based fast reactors have good natural circulation capabilities, and its natural circulation characteristics is of great value to improve the inherent safety of the reactor, and the scaling analysis method is the theoretical basis for establishing a reasonable and feasible lead-based fast reactor natural circulation test facility. In this paper, the main similarity groups could be determined by using dimensionless fluid governing equations of typical natural circulation lead-based fast reactor primary cooling system. Based on the constructed dimensionless similarity groups, the scaling analysis of small natural circulation lead-based fast reactor named SNCLFR-10 was carried out to obtain the geometric and thermal hydraulic design parameters of the dual-loop single-phase natural circulation experimental facility. The scaling method of the lead-based fast reactor natural circulation test facility was verified by comparing and analyzing the key thermal and hydraulic parameters of SNCLFR-10 and the scaled-down test facility under rated conditions. The research results show that the key thermal-hydraulic parameter ratios of SNCLFR-10 and the scaled-down facility are in good agreement with the theoretically deduced ratio, and the established lead-based fast reactor natural circulation experimental facility scaling analysis method is reasonable and feasible. 
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