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出 处:《核动力工程》2016年第5期46-50,共5页Nuclear Power Engineering
摘 要:从燃料元件内生成^(137)Cs、^(134)Cs的核反应过程出发,建立精确的数学物理模型,得到反应堆一回路冷却剂中^(137)Cs、^(134)Cs放射性活度与燃料组件内^(235)U燃耗关系的精确解和简化解。分别给出了简化解、ORIGEN2.0计算结果和精确解的比较。研究表明:只要通过化学测量得到反应堆一回路中^(134)Cs与^(137)Cs的活度比(RCs),即可由本文建立的精确解模型计算得到破损燃料元件的燃耗值,从而达到快速定位破损燃料元件的目的。Based on the nuclear reaction of ^137Cs and ^134Cs in the fuel assembly, the accurate mathematical and physical calculation models were established. The exact and simplified solutions of relationships between radioactivity of the two nuclides in the primary coolant and burn-up of ^235U in the fuel assembly were obtained. The comparisons of simplified solution, ORIGEN2.0 calculation result and exact solution were carried out as well. The result showed that, if only the RCs, ratio of ^134Cs/^137Cs in the primary coolant, is obtained by hydrochemistry measurement, burn-up of the ruptured fuel assembly can be calculated with the analytical solution model, so as to locate the ruptured fuel assembly rapidly.
关 键 词:137Cs ^134CS 放射性活度 燃料组件 235U燃耗
分 类 号:TL326[核科学技术—核技术及应用]
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