CFETR事故源项评估数据
收藏国家基础学科公共科学数据中心2024-03-05 收录
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https://www.nbsdc.cn/general/dataDetail?id=64edc724bb16e07753c348f3&type=1
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资源简介:
该数据集主要面向CFETR的安全设计于评估。项目完成了 CFETR 聚变堆始发事件的事故序列建模和分析,从而选取典型的 LOCA 事故序列,为聚变堆LOCA事故源项评估工作奠定了基础:分析了高压氦气冷却剂系统回路在真空室内的典型 LOCA 事故破口位置和大小,确定始发事件清单、事故进程和安全系统响应情况,完成始发事件的事故序列建模和分析,评估真空室在所选择的典型 LOCA 事故工况下对应的可移动放射性氚、钨粉尘等放射性核素的种类和初始盘存量。完成了事故初始条件与瞬态假设的设定,主要包括:事故前初始运行条件、事故破口位置与破口数量、事故发生时叠加全厂失电假设、事故瞬态持续时间等。最后,选择可信度高的事故分析程序对LOCA事故进行建模分析,完成CFETR典型LOCA事故后氚泄漏量分析与粉尘泄漏量分析,并根据分析结果,完成事故后氚与粉尘通过厂房、通风系统与除氚系统泄漏到环境中的释放途径与释放量分析。
This dataset is primarily intended for the safety design and assessment of CFETR. The project completed accident sequence modeling and analysis of initiating events for the CFETR fusion reactor, and selected typical LOCA (Loss of Coolant Accident) accident sequences, laying a foundation for the source term assessment of CFETR LOCA accidents. The typical break positions and sizes of high-pressure helium coolant system loops in the vacuum vessel were analyzed; the initiating event list, accident progression and safety system response were determined; and accident sequence modeling and analysis of initiating events were completed. The types and initial inventory of radionuclides including mobile radioactive tritium and tungsten dust corresponding to the vacuum vessel under the selected typical LOCA accident conditions were evaluated. The setting of accident initial conditions and transient assumptions was also completed, mainly including: pre-accident initial operating conditions, break positions and number of breaks during the accident, superimposed total plant power loss assumption at the time of accident occurrence, and accident transient duration. Finally, a highly credible accident analysis code was selected to model and analyze the LOCA accident, completing the analysis of tritium release amount and dust release amount after the typical CFETR LOCA accident. Based on the analysis results, the release pathways and release amounts of tritium and dust into the environment through the plant building, ventilation system and tritium removal system after the accident were analyzed.
提供机构:
核工业西南物理研究院
搜集汇总
数据集介绍

背景与挑战
背景概述
该数据集面向CFETR聚变堆的安全设计与评估,专注于LOCA事故序列的建模和分析,评估了放射性氚和钨粉尘的泄漏量。数据集提供了事故初始条件设定、泄漏途径分析等关键信息,支持核安全研究,数据量较小(3.82MB),包含3个文件,来源于国家重点研发计划项目。
以上内容由遇见数据集搜集并总结生成



