NUCLEAR TECHNIQUES, Volume. 46, Issue 7, 070606(2023)
Development of flow blockage model for core heat transfer and its application in QUENCH experiment
Figures & Tables(16)
Fig. 1. Illustration of fuel claddings after a LOCA simulation during a PHEBUS-LOCA experiment
Fig. 2. Heat and mass transfer phenomena during LOCA with ballooning of fuel claddings
Fig. 4. Illustration of flow blockage model (a) The top view of the fuel assembly, (b) The front view of the fuel assembly
Fig. 9. Cladding temperature variation at axial elevations of 950 mm, 750 mm, 550 mm, and 450 mm
Fig. 11. Blockage rate of coolant channel at different radial rings
Fig. 12. Comparison of experimental and simulated values of cladding hoop strain and temperature for rod #4
Table 1. Events and phases of the QUENCH-L0
View tableView in ArticleTable 1. Events and phases of the QUENCH-L0
阶段Phase 时间Time / s 事件Event 0. 预备阶段
Preparation
-1 000 开始记录数据，Tmax = 800 K，电功率为4.62 kW
Start data recording, Tmax = 800 K, electrical power at 4.62 kW
I. 加热阶段
Heating phase
0 以最大电加热功率启动瞬态Start of transient with max electrical power increase rate 2 电功率27 kW Electrical power 27 kW 186.6 将电功率转换为3.4 kW，Tmax = 1 317 K，电功率为41 kW
Switch of the electrical power to decay heat of 3.4 kW, Tmax = 1 317 K, electrical power 41 kW
II. 冷却阶段
Cooldown phase
200 达到包壳壁面最大温度，Tmax = 1 349 K
Cladding surface temperature maximum reached, Tmax = 1 349 K
217.8 启动快速蒸汽供应管线（50 g·s-1）并接入到蒸汽（2 g·s-1）和氩气（6 g·s-1）缓慢供应管线
Initiation of rapid steam supply line (50 g·s-1) additionally to slow steam supply (2 g·s-1) and carrier argon (6 g·s-1)
223⁓225 包壳快速冷却至400 K Rapid cladding cooling to 400 K 237⁓263 将棒束温度增加到660 K Increase of bundle temperature to 660 K III. 淹没阶段
Flooding phase
362 启动应急冷却水供应，关闭蒸汽供应，将氩气切换到从棒束顶部供应
Initiation of quench water supply, switch-off of steam supply, switch of argon to bundle top supply
387 达到最大骤冷速率100 g·s-1 Maximum quench rate (100 g·s-1) reached 480 组件完全被水淹没 Bundle completely filled with water 528 关闭加热电源，Tmax = 333 K Electrical power switched off, Tmax = 333 K 1 100 数据记录结束 End of data recording
Table 2. Cladding burst
View tableView in ArticleTable 2. Cladding burst
燃料棒编号
Fuel rod number
实验值[
18 ]Experiment
耦合系统
ISAA-FRTMB
SOCRAT/V3[ 19 ]Rod #4 114.6 s at 1 073 K
(高度 967.8 mm)
(Elevation 967.8 mm)
118.81 s at 1 101.49 K
(高度 950 mm)
(Elevation 950 mm)
150.56 s at 1 077.35 K
(高度 950 mm)
(Elevation 950 mm)
Rod #3 119.2 s at 1 089 K
(高度 954 mm)
(Elevation 954 mm)
119.63 s at 1 112.52 K
(高度 950 mm)
(Elevation 950 mm)
146.52 s at 1 066.36 K
(高度 950 mm)
(Elevation 950 mm)
Rod #11 167.2 s at 1 141 K
(高度 957.8 mm)
(Elevation 957.8 mm)
169.76 s at 1 115.35 K
(高度 950 mm)
(Elevation 950 mm)
138.43 s at 1 192.68 K
(高度 950 mm)
(Elevation 950 mm)
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Pengcheng GAO, Bin ZHANG, Hao YANG, Jianqiang SHAN. Development of flow blockage model for core heat transfer and its application in QUENCH experiment[J]. NUCLEAR TECHNIQUES, 2023, 46(7): 070606
Paper Information
Category: Research Articles
Received: Mar. 29, 2022
Accepted: --
Published Online: Aug. 3, 2023
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