卡轴事故下事故容错燃料对核反应堆安全潜在影响分析

吴和鑫; 金德升; 苟军利; 单建强; 程毅

doi:10.13832/j.jnpe.2023.S1.0075

卡轴事故下事故容错燃料对核反应堆安全潜在影响分析

doi: 10.13832/j.jnpe.2023.S1.0075

1.
西安交通大学能源与动力工程学院，西安，710049
2.
中广核研究院有限公司，广东深圳，518026

详细信息

作者简介:
吴和鑫（1996—），男，博士研究生，现从事反应堆运行安全方面的研究工作，E-mail: blanket@stu.xjtu.edu.cn

中图分类号: TL33
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- 被引次数: 0
出版历程
- 收稿日期: 2023-02-06
- 修回日期: 2023-03-28
- 刊出日期: 2023-06-15

Analysis of Potential Impact of ATFs on Reactor Safety under Shaft-Stuck Accident

1.
School of Energy and Power Engineering, Xi’an Jiaotong University, Xi’an, 710049, China
2.
China Nuclear Power Technology Research Institute, Shenzhen, Guangdong, 518026, China

摘要

摘要: 为分析卡轴工况下事故容错燃料（ATF）对反应堆安全的潜在影响，以中国改进型三环路压水堆（CPR1000）为参考电站，基于系统分析程序NUSOL-SYS进行了二次开发，研究了不同ATF组合在卡轴工况下的表现，并对ATF包壳表面特性变化可能引起的换热系数和临界热流密度（CHF）变化开展了敏感性分析。分析结果表明，在卡轴工况下，ATF包壳表面特性变化导致的换热系数和CHF变化会对芯块最高温度和包壳峰值温度（PCT）产生较大影响，热导率大的ATF芯块能极大地降低芯块温度，比热容大的ATF材料能降低PCT。
- 事故容错燃料(ATF) /
- 系统分析程序 /
- 事故分析
Abstract: To analyze the potential impact of accident tolerant fuel (ATF) on reactor safety under pump shaft-stuck accident, China's improved three-loop pressurized water reactor CPR1000 was used as reference power station to carry out second development based on the system analysis code NUSOL-SYS. The performance of CPR1000 with different ATF combinations under pump shaft-stuck accident was studied, and the sensitivity analysis was carried out to study the change of heat transfer coefficient and critical heat flux (CHF) caused by the change of ATF cladding surface characteristics. The results show that the change of heat transfer coefficient and CHF caused by the change of ATF cladding surface characteristics has a great influence on the maximum temperature of pellets and the peak cladding temperature (PCT). ATF pellets with high thermal conductivity can greatly reduce the pellet temperature, while ATF materials with high specific heat capacity can reduce the PCT.
- Accident tolerant fuel (ATF) /
- System analysis code /
- Accident analysis

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图 1 卡轴事故下不同ATF的热点芯块温度

Figure 1. Hot Spot Pellet Temperature of Different ATFs under Shaft-Stuck Accident

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图 2 卡轴事故下不同ATF的包壳最高温度

Figure 2. Peak Cladding Temperature of Different ATFs under Shaft-Stuck Accident

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图 3 卡轴事故下不同燃料组合归一化芯块最高温度

Figure 3. Normalized Maximum Pe llet Temperature of Different Fuel Combinations under Shaft-Stuck Accident

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图 4 卡轴事故下不同燃料组合归一化PCT

Figure 4. Normalized Peak Cladding Temperature of Different Fuel Combinations under Pump Shaft-Stuck Acciden

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表 1 CPR1000卡轴事故基本假设条件

Table 1. Basic Assumption of CPR1000 Pump Shaft-Stuck Accident

参数名	参数值
功率/MW	2953
一回路压力/MPa	15.29
热点因子	2.25
功率分布形式	顶部功率峰
停堆棒价值/pcm	4000
流量低信号	85.8%名义流量
1pcm=10⁻⁵

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表 2 CPR1000卡轴事故序列

Table 2. Shaft-Stuck Accident Sequence of CPR1000

事故序列	触发时间/s
泵235转轴卡死	0
低流量触发停堆信号	0.04
控制棒开始下落	1.05
汽轮机脱扣	5.05

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表 3 卡轴事故下不同ATF主要参数对比

Table 3. Key Paramaters of Different ATFs under Pump Shaft-Stuck Accident

芯块+包壳燃料组合	芯块最高温度/℃	PCT/℃	热点氧化产热/W	气隙压力/MPa
UO₂+Zr	2183.13	868.55	326.54812	6.32197
UO₂+SiC	2112.89	873.46	1.72287	6.31983
UO₂+FeCrAl	2181.42	869.25	0.01207	6.32258
FCM+Zr	1095.15	832.38	272.38910	6.31787
FCM+SiC	1076.18	837.38	1.32034	6.31615
FCM+FeCrAl	1094.83	832.67	0.00788	6.31882
UO₂（+13.6% BeO）+Zr	1278.63	824.70	234.96321	6.32043
UO₂（+13.6% BeO）+SiC	1242.04	824.88	1.03070	6.31781
UO₂（+13.6% BeO）+FeCrAl	1277.66	824.84	0.00629	6.31922

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参考文献(11)

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