模块式小型堆失水事故后堆芯硼浓度分析研究  

Analysis of Core Boron Concentration Following LOCA Accident for Small Module Reactors

作　　者：丁书华[1] 党高健[1] 李喆[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610213

出　　处：《核动力工程》2018年第1期173-176,共4页Nuclear Power Engineering

摘　　要：分析评价了模块式小型堆失水事故后可能出现的堆芯硼浓度过度累积问题,基于硼质量守恒原理,推导堆芯硼浓度演变的控制方程,计算分析了自动卸压系统阀门开启前的短期运行期间和开启后长期运行期间的堆芯硼浓度变化规律。结果表明,模块式小型堆的非能动专设安全系统设计能够防止失水事故后的堆芯硼结晶和重返临界。This paper is an evaluation of the potential buildup of boron in the core following the loss of coolant accident for small module reactors. The controlling equation for boron concentration is derived base on the mass conservation of the boron. The potential for boron buildup is evaluated in the short term before automatic depressurization system actuation as well as in the long term during containment recirculation. The results indicate that the passive safety injection systems could prevent the boron from building up significantly in the core and the core from returning to criticality during the long term containment recirculation.

关 键 词：模块式小型堆 非能动专设安全系统 失水事故 硼浓度 

分 类 号：TL364.4[核科学技术—核技术及应用]