10MWt固态燃料熔盐堆控制棒失控抽出事故分析  

Accident analyses of uncontrolled rod cluster control assembly bank withdrawal for 10-MWt thorium-based molten salt reactor-solid fuel

作　　者：靖剑平[1] 刘雅宁[2] 贾斌[1] 高新力[1] 孙微[1] 左嘉旭[1] 张春明[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082 [2]中国科学院过程工程研究所,北京100190

出　　处：《核技术》2016年第10期82-88,共7页Nuclear Techniques

基　　金：中国科学院战略性先导科技专项(No.XDA02050500)资助~~

摘　　要：钍基熔盐堆核能系统项目是中科院先导科技专项之一,其战略性目标是研发第四代熔盐冷却裂变反应堆核能系统。基于10 MWt固态燃料熔盐堆的系统设计,开发了适用于球床式反应堆系统的安全分析软件,并以高温气冷堆为对象对程序计算结果的准确性进行了验证。基于该软件程序,对固态燃料球床堆(Thorium Molten Salt Reactor-Solid Fuel,TMSR-SF)控制棒失控抽出事故进行了分析计算,研究了不同停堆限值及各停堆信号对事故的影响。计算结果表明,超功率停堆限值越高,出口温度限值越大,信号延迟时间越长,反应堆停堆越晚,堆芯功率和燃料最高温度越高。在TMSR-SF控制棒失控抽出事故下,燃料最高温度不超过860°C,远低于1 600°C的熔化温度限值。Background： Thorium-based molten salt reactor nuclear power system project is one of the “Strategic Priority Program” of Chinese Academy of Sciences, and its strategic goal is to develop the fourth generation molten- salt cooled fission reactor nuclear power system. Based on the system design of 10-MWt molten salt reactor-solid fuel, a safety analysis software is developed for the pebble bed reactor system and verified the correctness and accuracy for the high-temperature gas-cooled reactor of results calculatedvia this software program.Purpose： This study aims at accident analyses of uncontrolled rod cluster control assembly bank withdrawal for thorium molten salt reactor-solid fuel （TMSR-SF） by using the developed program.Methods： The TMSR-SF reactor core model is built according to the designed parameters. Analyses of the impacts of different shutdown limits and shutdown signals on the withdrawal accident of the TMSR-SF uncontrolled rod cluster control assembly bank is carried out through the safety analysis models such as neutron kinetics model, fluid flow and heat transfer model, control model,etc., in the developed program.Results：In the withdrawal accident of the uncontrolled rod cluster control assembly bank of the TMSR-SF, the maximum temperature of the reactor fuel temperature is no more than 860℃.Conclusions： Computional results show that the higher the limit value of over power shutdown is, the greater the outlet temperature is; the longer the signal delay time is, the later the reactor shutdown happens, and the higher the core power and fuel temperature is. Compared with the limit value of shutdown, the outlet temperature reaches the limit later in time sequence, the maxumum fuel temperature is much lower than the fuel pebble melting temperature limit of 1600℃ under no circumstances.

关 键 词：固态燃料熔盐堆 安全分析 控制棒失控抽出事故 程序开发 

分 类 号：TL99[核科学技术—核技术及应用]