定位检测破损燃料组件的堆芯啜吸法  

In-core sipping method for the identification of failed fuel assemblies

作　　者：吴中旺[1] 张亚军[1] 

机构地区：[1]清华大学核能技术设计研究院,北京100084

出　　处：《清华大学学报（自然科学版）》2000年第12期79-81,共3页Journal of Tsinghua University(Science and Technology)

摘　　要：破损燃料组件定位检测系统是为了确保反应堆安全运行、及时处理燃料包壳破损事故的安全重要设备。根据目前国际上对有元件盒反应堆采用的堆芯啜吸法 ,即在反应堆换料期间或发生燃料包壳破损事故时 ,停堆后直接从仍在堆芯位置的元件盒中取样 ,进行放射性测量和分析 ,从而鉴别出有破损的燃料组件的方法 ,作者设计了 2 0 0 MW低温核供热堆破损燃料组件定位检测系统。该设计既有国际同类设备的先进水平 ,又结合了低温核供热堆的特点和我国国情 ,保证了 2 0 0The failed fuel assembly identification system is an important safety system which ensures safe operations of reactor and immediate treatment of failed fuel rod cladding. The system uses an internationally recognized method to identify failed fuel assemblies in a reactor with fuel element cases. The in core sipping method is customary used to identify failed fuel assemblies during refueling or after fuel rod cladding failure accidents. The test is usually performed after reactor shutdown by taking samples from each fuel element case while the cases are still in their original core positions. The sample activity is then measured to identify failed fuel assemblies. A failed fuel assembly identification system was designed for the NHR 200 based on the properties of the NHR 200 and national requirements. The design provides an internationally recognized level of safety to ensure the safety of NHR 200.

关 键 词：安全 破损燃料组件 定位 堆芯啜吸法 

分 类 号：TL413.2[核科学技术—核技术及应用] TL364.3