5MW 核供热堆高欠热沸腾的特性研究  

Characteristic study of highly subcooled boiling in the 5MW nuclear heating reactor

作　　者：张达芳[1] 李金才[1] 

机构地区：[1]清华大学核能技术设计研究院

出　　处：《清华大学学报（自然科学版）》1998年第4期10-13,共4页Journal of Tsinghua University(Science and Technology)

基　　金：国家"八五"科技攻关项目

摘　　要：通过在子通道分析程序ＣＯＢＲＡ－ⅢＣ／ＭＩＴ２中引入能够计算高欠热沸腾区空泡份额的Ｂｏｗｒｉｎｇ模型，定量验证了５ＭＷ核供热堆（ＮＨＲ－５）功率运行时高欠热空泡的存在，且额定工况下堆芯平均空泡率为１．０６×１０－２，并研究了这类空泡的产生及其分布特征。以此为基础，在冷却剂系统分析程序ＲＥＴＲＡＮ－０２中补充高欠热沸腾计算模型，对负荷自跟随特性实验和自稳定性实验进行了分析计算，给出了分析结果与实验结果的比较。同时还研究了高欠热空泡的反应性反馈在动态过程中的作用及其特点。That there is a certain void content in the core of the 5MW nuclear heating reactor (NHR 5) under power operation conditions has been inferred by a special experiment. The inference above is verified using COBRA ⅢC/MIT2 and RETRAN 02 with a highly subcooled boiling calculation model, while average void fraction under the rated condition is 1.06×10 -2 . Characteristics of highly subcooled void are also investigated. The analysis results are consistent with the experiments of self regulation and self stabilization. The analyses also indicate that the reactivity feedback of highly subcooled void has an important influence on various operation transients and accidents of the NHR 5.

关 键 词：供热堆 高欠热沸腾 子通道分析 动态过程分析 

分 类 号：TL413.23[核科学技术—核技术及应用]