摘要
秦山核电站是我国第一座自行设计,自己建造的核电站。其燃料组件是压水堆释放能量的核心部件。它要在高温、高压、含硼水、高中子通量密度以及腐蚀、冲刷、振动等恶劣条件下长期工作,燃料组件的性能直接关系到核电站的可靠性、经济性、先进性。为获得燃料元件的各种性能同燃耗的关系并为物理计算提供检验数据,将其组件按设计要求进行辐照考验。
The basic concept and method for burnup determination of irradiated reactor fuel element by computer based Ge(Li) γ ray spectrometer are described for the tested fuel elements from Qinshan power plant. Experimental results of seven cutting positions and the average burnup value of one rod are given. Dead time correction,spectrum data reduction,irradiation history correction and sample preparation are presented.
出处
《核化学与放射化学》
CAS
CSCD
北大核心
1992年第4期246-252,共7页
Journal of Nuclear and Radiochemistry
关键词
燃耗
燃料元件
Γ能谱法
Destructive determination, Burnup, Fuel element, Gamma spectrum method, Fission product, Burnup monitor.
