Study on Nuclide Diffusion in Closed Environment of Marine Reactor with Large Break Loss of Coolant Accident
-
摘要: 基于严重事故分析程序MELCOR耦合计算流体力学软件CFD-FLUENT研究方法，采用MELCOR对船用反应堆失水事故进行分析，结果作为CFD-FLUENT模拟实验的初始条件，对船用反应堆大破口严重失水事故在堆舱内的放射性核素扩散进行研究。研究结果表明，泄漏时间在45 min时，放射性核素扩散至冷却剂进口、出口位置，而在14 min时放射性核素已经开始向安全壳扩散；在51 min时，放射性核素开始从安全壳破口向安全壳外扩散；在87 min时，放射性核素开始向邻舱扩散。本研究计算结果可为核事故的应急决策提供理论支持和数据支撑。
-
关键词:
- 船用反应堆 /
- 大破口失水事故 /
- 核素扩散 /
- MELCOR耦合CFD-FLUENT
Abstract: Based on the research method of severe accident analysis program MELCOR coupled computational fluid dynamics software CFD-FLUENT, MELCOR is used to analyze the loss of coolant accident of marine reactor. The results are used as the initial conditions of CFD-FLUENT simulation experiment to study the diffusion of radionuclides in the reactor compartment with large break loss of coolant accident of marine reactor. The results show that when the leakage time is 45 min, the radionuclides diffuse to the inlet and outlet of the coolant, but at 14 min, the radionuclides begin to spread to the containment, at 51 min, the radionuclides begin to spread from the break of the containment to the containment, and at 87 min, the radionuclides begin to spread to the adjacent compartment. The calculation results of this study can provide theoretical support and data support for emergency decision-making of nuclear accidents.-
Key words:
- Marine reactor /
- LBLOCA /
- Nuclide diffusion /
- MELCOR coupling CFD-FLUENT
-
图 1 船用反应堆舱室分布简化模型图
Figure 1. Simplified Model Diagram of Distribution of Marine Reactor Compartments
图 2 放射性核素泄露后的浓度场分布
Figure 2. Concentration Field Distribution after Radionuclide Leakage
表 1 船用反应堆几何参数表 mm
Table 1. Geometric Parameters of Marine Reactor
参数名 参数值 船用反应堆 长 139600 宽 49600 高 42600 安全壳 内径 12300 外径 12500 高度 25000 压力容器 内径 2900 外径 3000 高度 16500 
下载: 导出CSV
表 2 初始条件参数表
Table 2. Parameters of Initial Conditions
关键参数 参数值 破口尺寸/mm 500×650 沉积速度/(cm·s−1) 1.1 粒子密度/(kg·m−3) 8.4 粒子直径/mm 0.8 质量扩散系数/(m2·s−1) 7.5×10−5
下载: 导出CSV
-
[1] 张彦招,张帆,赵新文,等. 船用堆大破口失水叠加全船断电严重事故源项分析[J]. 原子能科学技术,2013, 47(9): 1565-1571. doi: 10.7538/yzk.2013.47.09.1565 [2] 吴斌,贾铭椿,龚军军. 船用堆核事故状态下源项特性及计算方法研究[J]. 海军工程大学学报,2003, 15(5): 87-90. doi: 10.3969/j.issn.1009-3486.2003.05.022 [3] LYU X F, LIU S, JI K, et al. Research on hydrogen risk and hydrogen control system in marine nuclear reactor[J]. Annals of Nuclear Energy, 2020, 141: 107373. doi: 10.1016/j.anucene.2020.107373 [4] OUYANG K H, CHEN W Z, HE Z Y. Analysis of the radioactive atmospheric dispersion induced by ship nuclear power plant severe accident[J]. Annals of Nuclear Energy, 2019, 127: 395-399. doi: 10.1016/j.anucene.2018.12.020 [5] 李子超,周涛,司广成,等. 冬夏海阳核电厂核素在近海域的迁移路径和浓度分布研究[J]. 核动力工程,2020, 41(4): 135-140. [6] 李子超,周涛,司广成,等. 基于拉格朗日方法的核素近海迁移计算[J]. 核动力工程,2020, 41(2): 72-77. [7] 王伟,陈力生,张帆,等. 蒸汽发生器传热管破损叠加全船断电事故放射性分析[J]. 原子能科学技术,2015, 49(5): 871-876. doi: 10.7538/yzk.2015.49.05.0871 [8] 王伟,陈力生,张帆,等. 船用堆全船断电事故源项分析[J]. 原子能科学技术,2014, 48(6): 1038-1043. doi: 10.7538/yzk.2014.48.06.1038 [9] 展锋,张帆,王伟,等. 全船断电叠加安全阀失效事故放射性释放分析[J]. 海军工程大学学报,2014, 26(6): 37-41. [10] KIM J C, JUNG G H, CHO J S, et al. Severe accident analyses for SMART using MELCOR 1.8.6 code[C]. Daejeon, Korea: Proceedings of the KNS Autumn Meeting, 2011. -
计量
- 文章访问数: 293
- HTML全文浏览量: 53
- PDF下载量: 55
- 被引次数: 0
