Study on Influence of Containment Venting on Hydrogen Risk of Spent Fuel Building under Severe Accident
-
摘要: 以我国某三代压水堆核电厂为例，选取了2个典型严重事故工况，采用严重事故一体化程序MAAP开展建模与计算，对安全壳排气的过程及对乏燃料厂房造成的氢气风险进行了分析。结果表明，如果不考虑乏燃料厂房的通风系统，从安全壳内释放的混合气体由于水蒸气的冷凝，会对乏燃料厂房造成一定的氢气风险；如果考虑乏燃料厂房通风系统的作用，乏燃料厂房的氢气风险将会消除。Abstract: Taking a domestic Ⅲ generation pressurized water reactor nuclear power plant as an example, two typical severe accident conditions are selected, modeling and calculation with Modular Accident Analysis Program(MAAP) are carried out, and the process of containment venting and the hydrogen risk to the spent fuel building are analyzed. The results show that if the ventilation system of the spent fuel building is not considered, the mixed gas released from the containment will cause a certain hydrogen risk to the spent fuel building due to the condensation of water vapor. If the role of the ventilation system of the spent fuel building is considered, the hydrogen risk in the spent fuel building will be eliminated.
-
Key words:
- Severe accident /
- Containment venting /
- Spent fuel building /
- Hydrogen risk
-
图 5 乏燃料厂房大气成分（工况1）
Figure 5. Atmospheric Composition in Spent Fuel Building (Condition 1)
图 6 安全壳内及乏燃料厂房氢气浓度（工况1）
Figure 6. Concentration of Hydrogen in Containment and Spent Fuel Building (Condition 1)
图 8 乏燃料厂房大气成分（工况2）
Figure 8. Atmospheric Composition in Spent Fuel Building (Condition 2)
图 9 安全壳内及乏燃料厂房氢气浓度（工况2）
Figure 9. Concentration of Hydrogen in Containment and Spent Fuel Building (Condition 2)
表 1 基本设计参数
Table 1. Basic Design Parameters
参数名 反应堆热
功率/MW反应堆运行
压力/MPa冷却剂平均
温度/℃安全壳自由
容积/m3参数值 3400 15.41 300.9 58339 
下载: 导出CSV
表 2 事故进程
Table 2. Accident Process
事件 时间/s 一回路发生小破口 0 反应堆停堆 150 CMT启动 166 CMT水位低 1964 ADS-4开启 2873 安注箱开始注入 2892 安注箱排空 3111 堆芯出口温度超过650℃ 4343 堆腔淹没开启 4711 堆芯熔融物跌落至下封头 7531 安全壳压力超过0.762 MPa，根据SAMG，操作员对
安全壳开始手动排气89972
下载: 导出CSV
-
[1] 濮继龙. 压水堆核电厂安全与事故对策[M]. 北京: 中国原子能出版社, 1995: 187-194. [2] 王高鹏,朱文韬,牛世鹏,等. 核电厂安全壳过滤排放严重事故管理策略研究[J]. 核科学与工程,2019, 39(4): 595-600. doi: 10.3969/j.issn.0258-0918.2019.04.015 [3] 林继铭,陈鹏,张世顺. 核电厂安全壳超压失效概率及过滤排放系统启动压力分析[J]. 核动力工程,2011, 32(3): 10-14. [4] 周志贵. 秦山二期安全壳超压后的过滤及卸压[D]. 上海: 上海交通大学, 2007: 21-24. [5] 周彦,佟立丽,曹学武. 低流速排放下气溶胶水洗模型[J]. 原子能科学技术,2020, 54(5): 923-929. doi: 10.7538/yzk.2019.youxian.0405 [6] 唐琪, 王立峰. 安全壳过滤排放系统8EUF存在的安全隐患和应对措施[C]//中国核科学技术进展报告(第四卷)——中国核学会2015年学术年会论文集第10册(核安全分卷). 绵阳: 中囯原子能出版社, 2015: 108-112. [7] Fauske Associates LLC. MAAP4 Modular accident analysis program for LWR power plants user’s manual[M]. USA, Illinois: EPRI, 1994: 43-46. -
计量
- 文章访问数: 153
- HTML全文浏览量: 34
- PDF下载量: 33
- 被引次数: 0
