摘要
针对模块式小型核反应堆(SMR)稳压器波动管破口事故建立了MELCOR计算模型,采用该模型对波动管破口触发的严重事故进程进行了模拟;并对其相关的热工水力参数进行分析研究,同时对比分析了不同破口面积对事故进程和结果的影响。分析结果表明:波动管破口尺寸为0.002 m^2时,事故进程最为严重,该结果可为SMR的严重事故管理导则提供参考依据。
The potential surge line break should be fully considered in the research and analysis of severe accidents for SMR. Therefore, the severe accident analysis model was established based on the design characteristics of SMR. The severe accident process is simulated, and the thermal-hydraulic phenomena and the effects of different break sizes under the pressurizer surge line break accident are analyzed. he. The results suggested that the most serious accident process happened when the break area is 0.002m2. Thus, this paper suggested to use this accident as the limit condition to provide reference for the formulation of the severe accident management guideline.
作者
尹莎莎
罗涵禹
秋穗正
黄伟
陈志辉
田野
方华伟
Yin Shasha;Luo Hanyu;Qiu Suizheng;Huang Wei;Chen Zhihui;Tian Ye;Fang Huawei(Science and Technology on Reactor System Design Technology Laboratory,Nuclear Power Institute of China,Chengdu,610213,China;School of Nuclear and Science and Technology,Xi'an Jiao tong University,Xi'an,710049,China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2019年第4期113-116,共4页
Nuclear Power Engineering
