摘要
核电厂严重事故下,管道与设备将经历极端高温、高压的情况,快速卸压管道作为严重事故下卸压的唯一途径,保证其流道畅通性至关重要,为此,开展“华龙一号”严重事故下快速卸压管道流道畅通性研究。对严重事故下快速卸压管道和稳压器进行传热分析,得到了管道和稳压器的温度变化情况。采用弹性分析的方法模拟了快速卸压管道在严重事故下的变形过程,得到了温度与变形的关系。建立三维模型,引入材料非线性,开展了快速卸压管道弹簧支架和阻尼器位置模拟研究,获取了严重事故下管道弹簧支架与阻尼器所处的状态。针对温度高于450℃的情况,分析了高温蠕变对管道完整性的影响。选取快速卸压管道上变形最大的10个位置开展了管道截面剩余面积研究,得到了严重事故下快速卸压管道最小剩余面积比以及管道最小流通面积。研究结果表明,“华龙一号”严重事故下快速卸压管道流道仍然能保证畅通性,“华龙一号”快速卸压管道能保证反应堆堆芯不会发生熔化。
Both pipelines and the equipment experience extreme high temperature and pressure in sever accident of the nuclear power plant.As the only way to relieve pressure in case of severe accident,it is very important to ensure the smoothness of the flow channel of rapid pressures relief pipeline.In this paper,the study on the smoothness of the flow channel of rapid pressure relief pipeline in severe accident of HPR 1000 is carried out.Heat transfer analysis is done for rapid pressure relief pipeline and pressurizer in severe accident.The temperature changes of pipeline and pressurizer are obtained.The deformation process of rapid pressure relief pipeline in severe accident is simulated by elastic analysis method.The relationship between temperature and deformation is obtained.The 3D model is established,and the material non-linearity is introduced.The simulation study on the position of spring support and damper of rapid pressure relief pipeline is carried out,and the status of spring support and damper of pipeline under severe accident is obtained.The influence of high temperature creep on pipeline integrity is analyzed for the case of temperature higher than 450℃.10 positions with the largest deformation on the rapid pressures relief pipeline are selected to study the residual area of the pipeline section,and the minimum residual area ratio and the minimum flow area of the pipeline under severe accidents are obtained.The research results show that the flow channel of the rapid pressures relief pipeline can still ensure the smoothness under the severe accident of HPR 1000,and the rapid pressures relief pipeline of HPR 1000 can ensure that the reactor core will not melt.
作者
卢喜丰
王新军
艾红雷
吕勇波
何风
李柄锦
张权
Lu Xifeng;Wang Xinjun;Ai Honglei;Lyu Yongbo;He Feng;Li Bingjin;Zhang Quan(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2023年第1期134-140,共7页
Nuclear Power Engineering
关键词
严重事故
快速卸压管道
蠕变
畅通性
Severe accident
Rapid pressure relief pipeline
Creep
Smoothness
