一体化核供热堆Ⅱ型主回路单相自然循环实验比例分析与设计  

Scaling Analysis and Design for Integrated Nuclear Heating ReactorⅡ Major Loop Test Facility Under Single Phase Natural Circulation

作　　者：刘洋[1] 贾海军[1] 吴磊[1] 

机构地区：[1]清华大学核能与新能源技术研究院先进反应堆工程和安全教育部重点实验室,北京100084

出　　处：《原子能科学技术》2012年第B12期788-791,共4页Atomic Energy Science and Technology

基　　金：国防科工局民用核能"NHR200-Ⅱ型核供热堆关键技术研究和关键设备验证"项目资助

摘　　要：小型一体化反应堆技术是目前研究的热点。在清华大学核能与新能源技术研究院原有的NHR200-Ⅰ型的基础上,开发了NHR200-Ⅱ型核供热堆,较大幅度的提升了热工参数,适用于城市集中供热、生产工业蒸汽、海水淡化等非发电领域。为研究NHR200-Ⅱ型核供热堆高温、高压系统自然循环运行特性,需开展实验研究。比例分析是主回路系统单相自然循环实验本体装置设计的理论依据和前提。对主回路流体、固体控制方程无量纲化,确定单相自然循环的相似特征数组合(Richardson数等6项)。在实验条件允许的范围内,为了减小模拟失真,实验装置使用等物性流体,其轴向长度比例为1:1,平均表面热流密度比例为1:1,流道面积比例为1:210。The small integrated nuclear reactor has drawn attention.On the basis of the NHR200-Ⅰ,the integrated nuclear heating reactor NHR200-Ⅱ was developed by Institute of Nuclear and New Energy Technology in Tsinghua University.The NHR200-Ⅱ reactor major loop thermal parameters were increased,and made it suitable for heating,industrial steam supply and sea water desalinization.In order to discover the natural circulation behavior under high temperature and pressure,the experiment study was needed.The scaling analysis provided the theoretical basis for determining the characteristics scale of the test facility.The similarity groups（Richardson number,etc.） could be determined using the dimensionless fluid and solid governing equations.In order to reduce the distortion,the test facility used the fluid with same property as the prototype.The axial length scale ratio and core surface average heat flux density ratio was 1∶1,and the flow area ratio was 1∶210.

关 键 词：核供热堆 自然循环 比例分析 

分 类 号：TL334[核科学技术—核技术及应用]