反应堆燃料元件破损当量诊断方法  

Diagnostic Method for Damage Equivalent of Reactor Fuel Elements

作　　者：林晓玲[1] 刘翠红 Lin Xiaoling;Liu Cuihong(Unit 92609,Beijing,100077,China)

机构地区：[1]92609部队,北京100077

出　　处：《核动力工程》2022年第5期115-118,共4页Nuclear Power Engineering

摘　　要：破损当量是衡量反应堆燃料元件破损严重程度的重要指标,但破损当量无法直接测量,在决策应用中不具有可操作性,需要建立与破损当量对应的可监测指标。本文结合实践经验,分析确定了可用于燃料元件破损诊断的典型核素,建立了反应堆一回路冷却剂中裂变产物核素活度浓度与燃料元件破损当量之间的传递关系;给出了一回路冷却剂取样分析实验方法,并指出实验过程中应注意的问题;建立了采用监测一回路冷却剂中典型裂变产物核素活度浓度诊断破损当量的方法,并分析了诊断中不确定度的主要影响因素。本研究为反应堆燃料元件破损当量诊断提供了技术方法。Damage equivalent is an important index to measure the severity of reactor fuel element damage.However,the damage equivalent is not operable in the decision-making application because it cannot be directly measured.It is necessary to establish the monitoring index corresponding to the damage equivalent.Based on practical experience,the typical nuclides that can be used for damage diagnosis are analyzed and determined,and the transfer relationship between the activity concentration of fission product nuclides in the reactor primary circuit coolant and the damage equivalent of fuel elements is established;the experimental method of sampling and analyzing the primary circuit coolant is given,and the issues that should be paid attention to in the experimental process are pointed out;a method for diagnosing the damage equivalent by monitoring the nuclide activity concentration of typical fission products in the primary circuit coolant is established,and the main factors affecting the uncertainty in the diagnosis are analyzed.This study provides a technical method for diagnosis of reactor fuel element damage equivalent.

关 键 词：燃料元件 破损当量 诊断 裂变产物核素 活度浓度 取样分析 

分 类 号：TL323[核科学技术—核技术及应用]