NUCLEAR TECHNIQUES, Volume. 46, Issue 2, 020601(2023)
Control rod ejection accident simulation and sensitivity analysis of large advanced pressurized water reactor
Figures & Tables(6)
Fig. 1. Results of BOL HFP case in the control rod ejection accident sensitivity analysis
Fig. 2. Results of BOL HZP case in the control rod ejection accident sensitivity analysis
Fig. 3. Results of EOL HFP case in the control rod ejection accident sensitivity analysis
Fig. 4. Results of EOL HZP case in the control rod ejection accident sensitivity analysis
Table 1. Results of key parameters in the control rod ejection accident analysis
View tableView in ArticleTable 1. Results of key parameters in the control rod ejection accident analysis
事故工况 Accident condition BOL HZP BOL HFP EOL HZP EOL HFP 功率水平 Power level / %FP 0 101 0 101 弹棒价值 Worth of ejected rod / %Δk 0.50 0.35 0.80 0.35 缓发中子份额 Delayed neutron fraction / % 0.49 0.49 0.44 0.44 反应性反馈权重因子 Reactivity feedback weighting factor 2.155 1.232 3.309 1.355 停堆反应性 Shutdown reactivity / %Δk 2.0 4.0 2.0 4.0 弹棒后FQ FQ after ejected rod 12.0 5.0 22.0 6.0 最高燃料芯块平均温度 Maximum average fuel pellet temperature / ℃ 803 2 211 1 627 2 174 最高燃料中心温度 Maximum fuel center temperature / ℃ 963 2 739 1 956 2 688 最高包壳平均温度 Maximum average cladding temperature / ℃ 582 1 222 1 046 1 198 最大燃料储能 Maximum fuel energy storage / cal·g-1 54.8 174.9 122.0 171.4 热点处的燃料熔化百分比 Percentage of fuel melting at hot spot / % 0 4.05 0 5.40 归一化功率峰值 Normalized power peak 0.36 3.02 17.09 3.58
Table 2. Sequence of the control rod ejection accident
View tableView in ArticleTable 2. Sequence of the control rod ejection accident
事故工况Accident condition 时间
Time / s
BOL HFP 控制棒开始弹出Control rod begins to eject 0.00 达到功率量程高中子通量高整定值Reach the high setting value of high neutron flux in the power range 0.03 核功率达到峰值Reach peak nuclear power 0.14 控制棒开始落入堆芯Control rods begin to fall into the core 0.93 峰值包壳温度出现Peak cladding temperature appears 2.46 峰值热流密度出现Peak heat flux appears 2.46 峰值燃料中心温度出现Peak fuel center temperature appears 4.09 BOL HZP 控制棒开始弹出Control rod begins to eject 0.00 达到功率量程高中子通量高整定值Reach the high setting value of high neutron flux in the power range 1.76 核功率达到峰值Reach peak nuclear power 1.85 控制棒开始落入堆芯Control rods begin to fall into the core 2.66 峰值包壳温度出现Peak cladding temperature appears 3.84 峰值热流密度出现Peak heat flux appears 3.86 峰值燃料中心温度出现Peak fuel center temperature appears 4.47 EOL HFP 控制棒开始弹出Control rod begins to eject 0.00 达到功率量程高中子通量高整定值Reach the high setting value of high neutron flux in the power range 0.03 核功率达到峰值Reach peak nuclear power 0.14 控制棒开始落入堆芯Control rods begin to fall into the core 0.93 峰值包壳温度出现Peak cladding temperature appears 2.38 峰值热流密度出现Peak heat flux appears 2.40 峰值燃料中心温度出现Peak fuel center temperature appears 4.47 EOL HZP 控制棒开始弹出Control rod begins to eject 0.00 达到功率量程高中子通量高整定值Reach the high setting value of high neutron flux in the power range 0.21 核功率达到峰值Reach peak nuclear power 0.25 控制棒开始落入堆芯Control rods begin to fall into the core 1.11 峰值包壳温度出现Peak cladding temperature appears 1.03 峰值热流密度出现Peak heat flux appears 1.04 峰值燃料中心温度出现Peak fuel center temperature appears 2.74
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Bing LAN, Xinyi PAN, Shihe YU, Yan YI. Control rod ejection accident simulation and sensitivity analysis of large advanced pressurized water reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(2): 020601
Paper Information
Category: Research Articles
Received: Aug. 17, 2022
Accepted: --
Published Online: Mar. 2, 2023
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