池式钠火事故下燃烧产物气溶胶行为研究

孙洪平; 邓坚; 罗跃建; 张明; 许幼幼; 武小莉; 刘丽莉; 陈冲; 秋穗正; 苏光辉

doi:10.13832/j.jnpe.2022.05.0100

池式钠火事故下燃烧产物气溶胶行为研究

doi: 10.13832/j.jnpe.2022.05.0100

1.
中国核动力研究设计院核反应堆系统设计技术重点实验室，成都，610213
2.
西安交通大学，西安，710049

详细信息

作者简介:
孙洪平（1991—），男，工程师，博士研究生，现主要从事核反应堆热工水力及安全分析研究，E-mail: 420001189@qq.com

中图分类号: TL334
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- 被引次数: 0
出版历程
- 收稿日期: 2021-09-10
- 修回日期: 2021-11-02
- 刊出日期: 2022-10-12

Research on Aerosol Behavior of Combustion Products under Sodium Pool Fire Accident

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
Xi’an Jiaotong University, Xi’an, 710049, China

摘要

摘要: 在钠冷快堆的安全评估中，分析钠泄露导致的池式钠火事故下燃烧产物的气溶胶行为尤为重要。本文采用将池式钠火燃烧模型与气溶胶动力学模型耦合的方式，开发了池式钠火事故下燃烧产物气溶胶行为分析程序REBAC-SFR，基于该程序模拟了SAPFIRE-D1和ABCOVE池式钠火实验，并与实验数据进行了对比。结果表明，本文开发的程序具有良好的可靠性和正确性，可为钠工艺间内池式钠火事故下燃烧产物气溶胶行为分析研究提供理论工具。
- 池式钠火 /
- 燃烧产物 /
- 气溶胶 /
- 程序开发
Abstract: In the safety assessment of sodium-cooled fast reactor (SFR), it is particularly important to analyze the aerosol behavior of combustion products in sodium pool fire accident caused by sodium leakage. In this paper, the analytical program REBAC-SFR for aerosol behavior of combustion products in sodium pool fire accident is developed by coupling the sodium pool fire combustion model with the aerosol dynamics model. Based on this program, SAPFIRE-D1 and ABCOVE sodium pool fire experiments are simulated and compared with the experimental data. The results show that the program developed in this paper has good reliability and correctness, and can provide a theoretical tool for the analysis of the aerosol behavior of combustion products under the sodium pool fire in the sodium process room.
- Sodium pool fire /
- Combustion product /
- Aerosol /
- Code development

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图 1 程序计算流程图

Figure 1. Program Calculation Flow Chart

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图 2 氧气体积份额计算值与实验值的对比

Figure 2. Comparison of Calculated and Experimental Values of Oxygen Volume Fraction

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图 3 钠池表面温度计算值与实验值的对比

Figure 3. Comparison of Calculated and Experimental Values of Sodium Pool Surface Temperature

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图 4 燃烧室气体温度计算值与实验值的对比

Figure 4. Comparison of Calculated and Experimental Values of Combustion Chamber Gas Temperature

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图 5 混凝土墙壁温度计算值与实验值的对比

Figure 5. Comparison of Calculated and Experimental Values of Concrete Wall Temperature

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图 6 REBAC-SFR计算值与实验值的对比

Figure 6. Comparison of Calculated and Experimental Values of REBAC-SFR

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图 7 悬浮气溶胶浓度计算值与实验值的对比

Figure 7. Comparison of Calculated and Experimental Values of Suspended Aerosol Concentration

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图 8 悬浮气溶胶质量中值直径的计算值与实验值对比

Figure 8. Comparison of Calculated and Experimental Values of Median Particle Diameter of Suspended Aerosol

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表 1 SAPFIRE-D1实验条件

Table 1. Experimental Conditions of SAPFIRE-D1

参数名	参数值
燃烧舱室体积/m³	73.4
壁面面积/m²	104
燃烧锅面积/m²	2.25
钠注入总量/kg	550
舱室初始压力/Pa	104364
气体与壁面初始温度/℃	55
燃烧锅初始温度/℃	55
燃烧舱室氧气体积浓度/%	21
钠注入时间/min	3.5

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表 2 AB1、AB2实验条件

Table 2. Experimental Conditions of AB1 and AB2

实验参数	参数值
实验参数	AB1	AB2
气体平均温度/K	299.65	293.65
容器内平均压力/kPa	125	128
氧气体积浓度/%	19.8	20.9
钠注入总质量/kg	875.15	875.15
燃烧面积/m²	4.4	4.4
燃烧时间/s	3600	3600
蒸汽注入时间段/s	—	960~4560
蒸汽注入速率/(kg·s⁻¹)	—	0.019
“—”——无此项

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表 3 ABCOVE实验中气溶胶动力学参数设置

Table 3. Aerosol Kinetic Parameter Settings in ABCOVE Experiment

气溶胶参数	参数值
气溶胶参数	AB1	AB2
气溶胶密度/(g·cm⁻³)	2.42	2.50
几何标准差	2.0	2.0
质量中值直径/μm	0.5	0.5
动力学形状因子	1.0	1.0
颗粒滑移修正因子	1.37	1.37
扩散边界层厚度/m	1×10⁻⁵	1×10⁻⁵
气体与颗粒热导率之比	0.05	0.05
颗粒黏附系数	1.0	1.0
湍流能量耗散率/(m⁻²·s⁻³)	0.001	0.001
凝聚形状因子	1.0	1.0
热适应系数	1.0	1.0

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表 4 悬浮气溶胶沉积质量计算值与实验值的对比 kg

Table 4. Comparison of Calculated and Experimental Values of Suspended Aerosol Deposition Mass kg

位置	AB1实验		AB2实验
位置	计算值	实验值	计算值	实验值
容器穹顶	0.02	0.20	0.194	0.18
圆柱筒体	0.22	1.32	0.20	1.20
容器底部	16.60	17.60	17.70	18.80
内部构件	19.70	20.79	17.50	18.45
总计	36.50	39.91	35.40	38.63

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参考文献(14)

[1]	LOCATELLI G, MANCINI M, TODESCHINI N. Generation IV nuclear reactors: current status and future prospects[J]. Energy Policy, 2013, 61: 1503-1520. doi: 10.1016/j.enpol.2013.06.101
[2]	王琦安,龙斌,王西涛,等. 中国钠冷快堆材料研发体系的研究[J]. 钢铁研究学报,2014, 26(9): 1-6.
[3]	BUKSHA Y K, BAGDASSAROV Y E, KIRYUSHIN A I, et al. Operation experience of the BN-600 fast reactor[J]. Nuclear Engineering and Design, 1997, 173(1-3): 67-79. doi: 10.1016/S0029-5493(97)00097-6
[4]	IIDA K, ASADA Y, OKABAYASHI K, et al. Simplified analysis and design for elevated temperature components of Monju[J]. Nuclear Engineering and Design, 1987, 98(3): 305-317. doi: 10.1016/0029-5493(87)90008-2
[5]	张东辉, 任丽霞. 快堆安全分析[M]. 北京: 中国原子能出版传媒有限公司, 2011: 105-106.
[6]	喻宏. 快堆钠火分析研究[D]. 北京: 中国原子能科学研究院, 2000: 9.
[7]	HILLARD R K. Summary of HEDL sodium fire tests: HEDL-SA-1669, CONF-7811137-1[R]. Richland: Hanford Engineering Development Laboratory, 1978.
[8]	LE SAUX W, MALET J C, BARTHEZ M. Experimental study of sodium jet fires with high flow rates[R]. Vienna: International Atomic Energy Agency (IAEA), 1996.
[9]	CHERDRON W. Review of the sodium fire experiments including sodium-concrete-reactions and summary of the results[R]. Vienna: International Atomic Energy Agency (IAEA), 1996.
[10]	BEIRIGER P, HOPENFELD J, SILBERBERG M, et al. SOFIRE II user report: AI-AEC-13055[R]. Canoga Park: Atomics International, 1973.
[11]	LEE Y B, PARK S K. A study on the development of advanced model to predict the sodium pool fire[J]. Journal of the Korean Nuclear Society, 1997, 29(3): 240-250.
[12]	GELBARD F. MAEROS user manual: NUREG/CR-1391, SAND-80-0822[R]. Albuquerque: Sandia National Laboratories, 1982.
[13]	MIYAKE O, MIYAHARA S, OHNO S, et al. Sodium pool combustion codes for evaluation of fast breeder reactor safety[J]. Journal of Nuclear Science and Technology, 1991, 28(2): 107-121. doi: 10.1080/18811248.1991.9731330
[14]	HILLIARD R K, MCCORMACK J D, POSTMA A K. Aerosol behavior during sodium pool fires in a large vessel: CSTF tests AB1 and AB2: HEDL-TME-79-28, TRN: 79-018400[R]. Richland: Hanford Engineering Development Laboratory, 1979.