缓发中子计算燃料元件破损方法研究  

Method Study on Calculating Fuel Element Failures by Delayed Neutrons

作　　者：徐治龙[1] 刘兴民[1] 刘勇进 常猛[3] 孙微[3] 李春[3] 

机构地区：[1]中国原子能科学研究院反应堆工程研究设计所 [2]92330部队 [3]环境保护部核与辐射安全中心

出　　处：《原子能科学技术》2013年第B06期168-171,共4页Atomic Energy Science and Technology

摘　　要：当燃料元件发生破损时,裂变产物会释放到主冷却剂中,引起主冷却剂放射性水平增加。根据燃料元件破损的监测数据,采用一定的计算方法,计算燃料元件破损数目,可为核电厂处理元件破损事故、确保反应堆和人员安全提供重要依据。本文对缓发中子先驱核产生、释放、迁移和探测器响应等过程进行深入研究,并对每个过程建立了数学计算模型,形成了1套根据缓发中子监测数据来计算燃料元件破损数目的方法。该方法可适用于多数反应堆的燃料元件破损数目计算。Once fuel element was failed,the fission products would be released into the primary coolant,leading to the increasing of radioactivity level of the primary coolant.According to the monitoring data of fuel element failure,using a certain calculation method,the number of failed fuel elements was calculated,which can be provided the important basis for dealing with the accident of fuel element failure and ensuring the security of the reactor and staff.In this paper,the behaviors of the delayed neutron precursors,including its birth,releasing and migration,and the response of detector were studied,and the mathematical models for every process were built.Combined with these models,the method to calculate the number of failed fuel elements was formed,which can be applied to the calculation of the number of failed fuel elements for many type of reactors.

关 键 词：反应堆 主冷却剂 缓发中子 燃料元件破损 

分 类 号：TL363[核科学技术—核技术及应用]