小型核供热堆负荷跟踪瞬态和反应性事故过程稳压特性及其稳定性研究  

Study on Pressurizer Characteristics and Stability of Load Tracking Transient and Reactivity Accident in Small Nuclear Heating Reactors

作　　者：谢菲[1] 李金才[1] 解衡[1] 

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

出　　处：《核动力工程》2016年第4期142-147,共6页Nuclear Power Engineering

摘　　要：以清华大学的摩洛哥海水淡化项目(NHR-10)为原型,建立小型一体化自然循环核供热堆分析模型,分析负荷跟踪瞬态工况、反应性引入事故下,核供热堆稳压特性和稳定性。结果表明:一体化核供热堆的堆芯出口欠热度变化小,对于保证堆瞬态过程中堆芯内不发生沸腾十分有利;上部气室容积大小对于瞬态过程中上部气室压力变化趋势有影响;初始堆芯出口欠热度的大小对瞬变过程影响很小,对最终结果影响不大;从反应性扰动分析来看,一体化核供热堆压水运行方式时具有良好的稳定性。Taking the Moroccan desalination projects （NHR-10） developed by Tsinghua University as the prototype, the small integrated natural circulation nuclear heating reactor model was established. By the study of the load tracking transient condition and reactivity accident, the pressurizer characteristics and stability of the performance of nuclear heating reactor were analyzed. The results indicate that the subcooling of outlet in integrated nuclear heating reactor is small enough to ensure that boiling does not occur during the transient process of reactor, which is good to PWR. The upper gas space volume has effect on the pressure trends of the reactor during the transient process. Initial subcooling of outlet has little effect on the transient process and final result. Integrated nuclear heating reactor has good stability in PWR run mode.

关 键 词：核供热堆 负荷跟踪 稳定性 

分 类 号：TL33[核科学技术—核技术及应用]